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Sample records for nuclear desalination plants

  1. Application of Nuclear Energy for Seawater Desalination: Design Concepts of Nuclear Desalination Plants

    SciTech Connect

    Faibish, R.S.; Konishi, T.; Gasparini, M.

    2002-07-01

    Nuclear energy is playing an important role in electricity generation, producing 16% of the world's electricity. However, most of the world's energy consumption is in the form of heat, in which case nuclear energy could also play an important role. In particular, process heat for seawater desalination using nuclear energy has been of growing interest to some Member States of the International Atomic Energy Agency over the past two decades. This growing interest stems from increasingly acute freshwater shortages in many arid and semi-arid zones around the world. Indeed, several national and international nuclear desalination demonstration programs are already under way or being planned. Of particular interest are projects for seawater nuclear desalination plants in coastal regions, where saline feed water can serve the dual purpose of cooling water for the nuclear reactor and as feed water for the desalination plant. In principle any nuclear reactor can provide energy (low-grade heat and/or electricity), as required by desalination processes. However, there are some additional requirements to be met under specific conditions in order to introduce nuclear desalination. Technical issues include meeting more stringent safety requirements (nuclear reactors themselves and nuclear-desalination integrated complexes in particular), and performance improvement of the integrated systems. Economic competitiveness is another important factor to be considered for a broader deployment of nuclear desalination. For technical robustness and economic competitiveness a number of design variants of coupling configurations of nuclear desalination integrated plant concepts are being evaluated. This paper identifies and discusses various factors, which support the attractiveness of nuclear desalination. It further summarizes some of the key approaches recommended for nuclear desalination complex design and gives an overview of various design concepts of nuclear desalination plants, which

  2. Source book for planning nuclear dual-purpose electric/distillation desalination plants

    SciTech Connect

    Reed, S.A.

    1981-02-01

    A source book on nuclear dual-purpose electric/distillation desalination plants was prepared to assist government and other planners in preparing broad evaluations of proposed applications of dual-purpose plants. The document is divided into five major sections. Section 1 presents general discussions relating to the benefits of dual-purpose plants, and spectrum for water-to-power ratios. Section 2 presents information on commercial nuclear plants manufactured by US manufacturers. Section 3 gives information on distillation desalting processes and equipment. Section 4 presents a discussion on feedwater pretreatment and scale control. Section 5 deals with methods for coupling the distillation and electrical generating plants to operate in the dual mode.

  3. Desalination Plant Optimization

    Energy Science and Technology Software Center (ESTSC)

    1992-10-01

    MSF21 and VTE21 perform design and costing calculations for multistage flash evaporator (MSF) and multieffect vertical tube evaporator (VTE) desalination plants. An optimization capability is available, if desired. The MSF plant consists of a recovery section, reject section, brine heater, and associated buildings and equipment. Operating costs and direct and indirect capital costs for plant, buildings, site, and intakes are calculated. Computations are based on the first and last stages of each section and amore » typical middle recovery stage. As a result, the program runs rapidly but does not give stage by stage parameters. The VTE plant consists of vertical tube effects, multistage flash preheater, condenser, and brine heater and associated buildings and equipment. Design computations are done for each vertical tube effect, but preheater computations are based on the first and last stages and a typical middle stage.« less

  4. Optimal Coupling of a Nuclear Reactor and a Thermal Desalination Plant

    SciTech Connect

    Caruso, G.; Naviglio, A.; Nisan, S.; Bielak, B.; Cinotti, L.; Humphries, J.R.; Martins, N.; Volpi, L.

    2002-07-01

    The present study, performed in the framework of the EURODESAL Project (5. EU FWP), deals with the analysis of the 'optimum' coupling of a PWR and of a HTGR plant with a thermal desalination plant, based on the Multiple Effects process. The reference reactors are the AP600 and the PWR900 as Pressurized reactors and the GT-MHR as Gas reactor. The calculations performed show that there are several technical solutions allowing to couple PWRs and GRs to a ME desalination plant. The optimization criteria concern the technical feasibility of the coupling, producing the maximum quantity of fresh water at the lower cost, without unacceptable reduction of the electrical power produced and without undue health hazard for population. (authors)

  5. Hybrid solar powered desalination plant

    SciTech Connect

    Hamester, H.L.; Husseiny, A.; Lumdstrom, J.; La Porta, C.; McLagan, G.

    1981-01-01

    A solar powered sea water desalination system design is described. The commercial size plant is specified to provide at least 1.8*10/sup 6/m/sup 3//year of product water (<500 kg/m/sup 3/ total dissolved solids) from sea water containing 44,000 kg/m/sup 3/ total dissolved solids. The basis of the design is a two-stage desalination system employing membrane technologies. Membrane technologies were selected since they require about a factor of five less energy than desalination technologies which use distillation.

  6. Preliminary design studies on a nuclear seawater desalination system

    SciTech Connect

    Wibisono, A. F.; Jung, Y. H.; Choi, J.; Kim, H. S.; Lee, J. I.; Jeong, Y. H.; No, H. C.

    2012-07-01

    Seawater desalination is one of the most promising technologies to provide fresh water especially in the arid region. The most used technology in seawater desalination are thermal desalination (MSF and MED) and membrane desalination (RO). Some developments have been done in the area of coupling the desalination plant with a nuclear reactor to reduce the cost of energy required in thermal desalination. The coupling a nuclear reactor to a desalination plant can be done either by using the co-generation or by using dedicated heat from a nuclear system. The comparison of the co-generation nuclear reactor with desalination plant, dedicated nuclear heat system, and fossil fueled system will be discussed in this paper using economical assessment with IAEA DEEP software. A newly designed nuclear system dedicated for the seawater desalination will also be suggested by KAIST (Korea Advanced Inst. of Science and Technology) research team and described in detail within this paper. The suggested reactor system is using gas cooled type reactor and in this preliminary study the scope of design will be limited to comparison of two cases in different operating temperature ranges. (authors)

  7. Economic Considerations of Nuclear Desalination in Korea

    SciTech Connect

    Man-Ki, Lee; Seung-Su, Kim

    2006-07-01

    The objective of this study is to assess the economics of SMART (System-integrated Modular Advanced Reactor) desalination plant in Korea through DEEP (Devaluation Economic Evaluation Program). SMART is mainly designed for the dual purpose of producing water and electricity with the total capacity of 100 MWe which 10 MWe is used for water production and the remains for the electric generation. SMART desalination plant using MED (Multi-Effect Distillation) process is in the stage of the commercial development and its cost information is also being accumulated. In this circumstances, the economic assessment of nuclear desalination by SMART and the effect of water(or electric) supply price to the regional economy is meaningful to the policy maker. This study is focused on the case study analysis about the economics of SMART desalination plant and the meanings of the case study result. This study is composed of two parts. One is prepared to survey the methodology regarding cost allocation between electricity and water in DEEP and the other is for the economic assessment of SMART. The cost allocation methods that have been proposed or used can be classified into two main groups, one is the cost prorating method and the other is the credit method. The cost of an product item in the dual-purpose plant can be determined differently depending on the costing methods adopted. When it comes to applying credit method adopted in this thesis, the production cost of water depends on what kind of the power cost will be chosen in calculating the power credit. This study also analyses the changes of nuclear desalination economics according to the changes of the important factors such as fossil fuel price. I wish that this study can afford to give an insight to the policy maker about SMART desalination plant. (authors)

  8. Removal of Radionuclides from Waste Water at Fukushima Daiichi Nuclear Power Plant: Desalination and Adsorption Methods - 13126

    SciTech Connect

    Kani, Yuko; Kamosida, Mamoru; Watanabe, Daisuke; Asano, Takashi; Tamata, Shin

    2013-07-01

    Waste water containing high levels of radionuclides due to the Fukushima Daiichi Nuclear Power Plant accident, has been treated by the adsorption removal and reverse-osmosis (RO) desalination to allow water re-use for cooling the reactors. Radionuclides in the waste water are collected in the adsorbent medium and the RO concentrate (RO brine) in the water treatment system currently operated at the Fukushima Daiichi site. In this paper, we have studied the behavior of radionuclides in the presently applied RO desalination system and the removal of radionuclides in possible additional adsorption systems for the Fukushima Daiichi waste water treatment. Regarding the RO desalination system, decontamination factors (DFs) of the elements present in the waste water were obtained by lab-scale testing using an RO unit and simulated waste water with non-radioactive elements. The results of the lab-scale testing using representative elements showed that the DF for each element depended on its hydrated ionic radius: the larger the hydrated ionic radius of the element, the higher its DF is. Thus, the DF of each element in the waste water could be estimated based on its hydrated ionic radius. For the adsorption system to remove radionuclides more effectively, we studied adsorption behavior of typical elements, such as radioactive cesium and strontium, by various kinds of adsorbents using batch and column testing. We used batch testing to measure distribution coefficients (K{sub d}s) for cesium and strontium onto adsorbents under different brine concentrations that simulated waste water conditions at the Fukushima Daiichi site. For cesium adsorbents, K{sub d}s with different dependency on the brine concentration were observed based on the mechanism of cesium adsorption. As for strontium, K{sub d}s decreased as the brine concentration increased for any adsorbents which adsorbed strontium by intercalation and by ion exchange. The adsorbent titanium oxide had higher K{sub d}s and it

  9. Performance of solar multiflash desalination plants

    SciTech Connect

    Ruggiero, U.; Ciciolla, C.; Fabiano, M.; Fortunato, B.

    1982-08-01

    In the present paper the authors study the performance of solar multiflash desalination plants. In the first part of the study a computer program is coded for the design and calculation of the steady working conditions of the desalination plant. The code has been tested by comparing the theoretical results with the experimental ones obtained from a prototype and a satisfactory agreement has been found. In the second part of the work the authors study the working condition of the desalination plant connected with a solar system. Finally the unsteady performance of the multiflash desalination plant is also predicted by using another computer program, based on a ''Montecarlo'' simulation algorithm for the generation of the atmospheric conditions. This code simulates the working conditions of the plant in a given period of time by computing all the relevant parameters.

  10. Performance of solar multiflash desalination plants

    NASA Astrophysics Data System (ADS)

    Ruggiero, U.; Ciciolla, C.; Fabiano, M.; Fortunato, B.

    A theoretical model is presented for calculating the steady and unsteady performance of a solar desalinization plant. A Monte Carlo method is used to generate the atmospheric parameters, and a once-through multi-flash desalinization plant is considered, using data from a 100 C operating temperature prototype plant. Energy and mass balances are formulated for the generic stage, a heat balance is defined for the brine heater stage, and a total heat transfer coefficient is calculated for all system stages. Focusing solar collectors are considered for the power source, and an approximation is employed to predict the solar input for a specific time of day. Short and long term thermal losses are analyzed, together with the cost of the water produced. Increases in oil costs are projected to be necessary to make solar powered desalinization plants preferable over conventional plants.

  11. Environmental impact of seawater desalination plants.

    PubMed

    Al-Mutaz, I S

    1991-01-01

    Enormous amounts of seawater are desalted everyday worldwide. The total world production of fresh water from the sea is about 2621 mgd (9.92 million m(3) day(-1) 1985 figures). Desalting processes are normally associated with the rejection of high concentration waste brine from the plant itself or from the pretreatment units as well as during the cleaning period. In thermal processes, mainly multistage flash (MSF) thermal pollution occurs. These pollutants increase the seawater temperature, salinity, water current and turbidity. They also harm the marine environment, causing fish to migrate while enhancing the presence of algae, nematods and tiny molluscus. Sometimes micro-elements and toxic materials appear in the discharged brine.This paper will discuss the impact of the effluents from the desalination plants on the seawater environment with particular reference to the Saudi desalination plants, since they account for about 50% of the world desalination capacity. PMID:24241776

  12. Safety Aspects of Nuclear Desalination with Innovative Systems; the EURODESAL Project

    SciTech Connect

    Alessandroni, C.; Cinotti, L.; Mini, G.; Nisan, S.

    2002-07-01

    The proposed paper reports the results of a preliminary investigation on safety impact deriving from the coupling of a desalination plant with a 600 MWe Passive Design PWR like the AP600 Nuclear Power Plant. This evaluation was performed in the frame of the EURODESAL Project of the 5. EURATOM Framework Programme. (authors)

  13. Desalination

    EPA Science Inventory

    To cope with the rising demand for fresh water, desalination of brackish groundwater and seawater is increasingly being viewed as a pragmatic option for augmenting fresh water supplies. The large scale deployment of desalination is likely to demonstrably increase electricity use,...

  14. A Study on Cost Allocation in Nuclear Power Coupled with Desalination

    SciTech Connect

    Lee, ManKi; Kim, SeungSu; Moon, KeeHwan; Lim, ChaeYoung

    2004-07-01

    As for a single-purpose desalination plant, there is no particular difficulty in computing the unit cost of the water, which is obtained by dividing the annual total costs by the output of fresh water. When it comes to a dual-purpose plant, cost allocation is needed between the two products. No cost allocation is needed in some cases where two alternatives producing the same water and electricity output are to be compared. In these cases, the consideration of the total cost is then sufficient. This study assumes MED (Multi-Effect Distillation) technology is adopted when nuclear power is coupled with desalination. The total production cost of the two commodities in dual-purpose plant can easily be obtained by using costing methods, if the necessary raw data are available. However, it is not easy to calculate a separate cost for each product, because high-pressure steam plant costs cannot be allocated to one or the other without adopting arbitrary methods. Investigation on power credit method is carried out focusing on the cost allocation of combined benefits due to dual production, electricity and water. The illustrative calculation is taken from Preliminary Economic Feasibility Study of Nuclear Desalination in Madura Island, Indonesia. The study is being performed by BATAN (National Nuclear Energy Agency), KAERI (Korean Atomic Energy Research Institute) and under support of the IAEA (International Atomic Energy Agency) started in the year 2002 in order to perform a preliminary economic feasibility in providing the Madurese with sufficient power and potable water for the public and to support industrialization and tourism in Madura Region. The SMART reactor coupled with MED is considered to be an option to produce electricity and potable water. This study indicates that the correct recognition of combined benefits attributable to dual production is important in carrying out economics of desalination coupled with nuclear power. (authors)

  15. Thermal analysis of an innovative heat pump operated desalination plant

    SciTech Connect

    Site, V.D.

    1995-12-31

    Sea and brackish water desalination can contribute to solve the problem of fresh water shortage in many and regions of the world. Nowadays most of the installed desalination plants employ distillation processes, like Multistage Flash (MSF), Multi effect Distillation (MED) and Vapor Compression (VC). VC process is called Mechanical Vapor Compression (MVC) when it employs a mechanical compressor, while it is called Thermal Compression when it employs a steam-ejector compressor. In this paper a new distillation plant for the treatment of sea water for drinking water purposes is presented. The most innovative feature of this system is the use of a heat pump as part of the desalting unit. The use of the heat pump in the proposed system enables desalting water evaporation and steam condensation at the same temperature, unlike conventional VC desalting systems where a steam compression stage is necessary. A thermal analysis of the heat pump-operated desalination (HPD) plant and a comparison between the HPD and a conventional MVC plant is presented, in order to determine the main advantages and disadvantages of the new system.

  16. A desalination plant with solar and wind energy

    NASA Astrophysics Data System (ADS)

    Chen, H.; Ye, Z.; Gao, W.

    2013-12-01

    The shortage of freshwater resources has become a worldwide problem. China has a water shortage, although the total amount of water resources is the sixth in the world, the per capita water capacity is the 121th (a quarter of the world's per capita water capacity), and the United Nations considers China one of the poorest 13 countries in the world in terms of water. In order to increase the supply of fresh water, a realistic way is to make full use of China's long and narrow coastline for seawater desalination. This paper discusses a sea water desalination device, the device adopts distillation, uses the greenhouse effect principle and wind power heating principle, and the two-type start is used to solve the problem of vertical axis wind turbine self-starting. Thrust bearings are used to ensure the stability of the device, and to ensure absorbtion of wind energy and solar energy, and to collect evaporation of water to achieve desalination. The device can absorb solar and wind energy instead of input energy, so it can be used in ship, island and many kinds of environment. Due to the comprehensive utilization of wind power and solar power, the efficiency of the device is more than other passive sea water desalting plants, the initial investment and maintenance cost is lower than active sea water desalting plant. The main part of the device cannot only be used in offshore work, but can also be used in deep sea floating work, so the device can utilise deep sea energy. In order to prove the practicability of the device, the author has carried out theory of water production calculations. According to the principle of conservation of energy, the device ais bsorbing solar and wind power, except loose lost part which is used for water temperature rise and phase transition. Assume the inflow water temperature is 20 °C, outflow water temperature is 70 °C, the energy utilization is 60%, we can know that the water production quantity is 8 kg/ m2 per hour. Comparing with the

  17. Nuclear Security for Floating Nuclear Power Plants

    SciTech Connect

    Skiba, James M.; Scherer, Carolynn P.

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  18. Performance analysis of an OTEC plant and a desalination plant using an integrated hybrid cycle

    SciTech Connect

    Uehara, Haruo; Miyara, Akio; Ikegami, Yasuyuki; Nakaoka, Tsutomu

    1996-05-01

    A performance analysis of an OTEC plant using an integrated hybrid cycle (I-H OTEC Cycle) has been conducted. The I-H OTEC cycle is a combination of a closed-cycle OTEC plant and a spray flash desalination plant. In an I-H OTEC cycle, warm sea water evaporates the liquid ammonia in the OTEC evaporator, then enters the flash chamber and evaporates itself. The evaporated steam enters the desalination condenser and is condensed by the cold sea water passed through the OTEC condenser. The optimization of the I-H OTEC cycle is analyzed by the method of steepest descent. The total heat transfer area of heat exchangers per net power is used as an objective function. Numerical results are reported for a 10 MW I-H OTEC cycle with plate-type heat exchangers and ammonia as working fluid. The results are compared with those of a joint hybrid OTEC cycle (J-H OTEC Cycle).

  19. The photovoltaic-powered water desalination plant 'SORO' design, start up, operating experience

    NASA Astrophysics Data System (ADS)

    Neuhaeusser, G.; Mohn, J.; Petersen, G.

    Design features, operational parameters, and test results of a year of operation of the SORO prototype photovoltaic (PV) reverse osmosis salt water desalinization plant are described. Chemicals are added to the salt water to control the pH, prevent formation of compounds which could plug the flow system, and kill bacteria and slime which might grow in the solution. The water is pressurized and forced into contact with membranes which separate the fresh water from the brackish or sea water. The flow rate in the project was 180 l/h, with the main electrical energy load being the high pressure pump and the well pump. Batteries are charged before current is switched to power the desalinization system. The plant yielded 1.50 cu of fresh water/day and is concluded to be a viable design for scale-up to larger production figures, besides being economically competitive with solar desalinization installations where the salt content is 2000 ppm.

  20. Integration of solar process heat into an existing thermal desalination plant in Qatar

    NASA Astrophysics Data System (ADS)

    Dieckmann, S.; Krishnamoorthy, G.; Aboumadi, M.; Pandian, Y.; Dersch, J.; Krüger, D.; Al-Rasheed, A. S.; Krüger, J.; Ottenburger, U.

    2016-05-01

    The water supply of many countries in the Middle East relies mainly on water desalination. In Qatar, the water network is completely fed with water from desalination plants. One of these power and desalination plants is located in Ras Abu Fontas, 20 km south of the capital Doha. The heat required for thermal desalination is provided by steam which is generated in waste heat recovery boilers (HRB) connected to gas turbines. Additionally, gas fired boilers or auxiliary firing in the HRBs are used in order to decouple the water generation from the electricity generation. In Ras Abu Fontas some auxiliary boilers run 24/7 because the HRB capacity does not match the demand of the desalination units. This paper contains the techno-economic analysis of two large-scale commercial solar field options, which could reduce the fuel consumption significantly. Both options employ parabolic trough technology with a nominal saturated steam output of 350 t/h at 15 bar (198°C, 240 MW). The first option uses direct steam generation without storage while the second relies on common thermal oil in combination with a molten salt thermal storage with 6 hours full-load capacity. The economic benefit of the integration of solar power depends mainly on the cost of the fossil alternative, and thus the price (respectively opportunity costs) of natural gas. At a natural gas price of 8 US-/MMBtu the internal rate of return on equity (IRR) is expected at about 5%.

  1. Economic Evaluation of Nuclear Reactor Coupling with Seawater Desalination Facility

    SciTech Connect

    Danrong Song; Tong Liu; Hua Zhao

    2006-07-01

    Nowadays only 1/2000 of overall fresh water resource can be used in the world, 1.1 billion people in the world are short of safety drinkable water, so the supply of freshwater is one of the major problems facing to the world in 21. century. China is one of the thirteen water-poorest countries and fresh water has become a choke point of the economic development in those water-poor regions. The desalination of sea water is a very important way to find new fresh water resource and sea water is inexhaustible. (authors)

  2. An Advanced Reverse Osmosis Technology For Application in Nuclear Desalination Facilities

    SciTech Connect

    Humphries, J.R.; Davies, K.; Ackert, J.A.

    2002-07-01

    The lack of adequate supplies of clean, safe water is a growing global problem that has reached crisis proportions in many parts of the world. It is estimated that 1.5 billion people do not have access to adequate supplies of safe water, and that as a result nearly 10,000 people die every day and thousands more suffer from a range of debilitating illnesses due to water related diseases. Included in this total is an estimated 2.2 million child deaths annually. As the world's need for additional sources of fresh water continues to grow, seawater and brackish water desalination are providing an increasingly important contribution to the solution of this problem. Because desalination is an energy intensive process, nuclear desalination provides an economically attractive and environmentally sound alternative to the burning of fossil fuels for desalination. Nevertheless, the enormity of the problem dictates that additional steps must be taken to improve the efficiency of energy utilization and reduce the cost of water production in order to reduce the financial and environmental burden to communities in need. An advanced reverse osmosis (RO) desalination technology has been developed that emphasizes a nontraditional approach to system design and operation, and makes use of a sophisticated design optimization process that can lead to highly optimized design configurations and operating regimes. The technology can be coupled with a nuclear generating station (NGS) to provide an integrated facility for the co-generation of both water and electricity. Waste heat from the NGS allows the use of 'preheated' feedwater into the RO system, improving the efficiency of the RO process and reducing the cost of water production. Because waste heat, rather than process heat, is used the desalination system can be readily coupled to any existing or advanced reactor technology with little or no impact on reactor design and operation and without introducing additional reactor safety

  3. Bioindicators as metrics for environmental monitoring of desalination plant discharges.

    PubMed

    de-la-Ossa-Carretero, J A; Del-Pilar-Ruso, Y; Loya-Fernández, A; Ferrero-Vicente, L M; Marco-Méndez, C; Martinez-Garcia, E; Giménez-Casalduero, F; Sánchez-Lizaso, J L

    2016-02-15

    Development of desalination projects requires simple methodologies and tools for cost-effective and environmentally-sensitive management. Sentinel taxa and biotic indices are easily interpreted in the perspective of environment management. Echinoderms are potential sentinel taxon to gauge the impact produced by brine discharge and the BOPA index is considered an effective tool for monitoring different types of impact. Salinity increase due to desalination brine discharge was evaluated in terms of these two indicators. They reflected the environmental impact and recovery after implementation of a mitigation measure. Echinoderms disappeared at the station closest to the discharge during the years with highest salinity and then recovered their abundance after installation of a diffuser reduced the salinity increase. In the same period, BOPA responded due to the decrease in sensitive amphipods and the increase in tolerant polychaete families when salinities rose. Although salinity changes explained most of the observed variability in both indicators, other abiotic parameters were also significant in explaining this variability. PMID:26781455

  4. Planning and Design of Seawater Reverse Osmosis Desalination Plants Marine Outfalls

    NASA Astrophysics Data System (ADS)

    Maalouf, S.; Yeh, W. W.

    2011-12-01

    Increasing demands for water in urban areas and agricultural zones in arid and semi-arid regions have urged planners and regulators to look for alternative renewable water sources. Worldwide, seawater reverse osmosis (SWRO) desalination plants have become an essential supply source for the production of fresh water in such regions. Disposal of their wastes, however, has not been fully and properly addressed. This study presents a strategy for the analysis and design of optimal disposal systems of hypersaline wastes that are generated by SWRO desalination plants. The study evaluates current disposal methods and recommends ways to effectively employ multiport marine outfalls for this purpose. Such outfalls emerged as reliable means for conveying wastes from process plants, to include wastewater treatment and power plants, into the coastal waters. Their proper use, however, in conjunction with SWRO desalination plants is still in its beginning stage, and much work needs to be done to employ them effectively. Therefore, the main objective of this research is to provide design engineers with effective procedures that meet environmental permitting requirements and restrictions, while ascertaining adequate hydrodynamic performance. The study is tested by employing a simulation model and examining its reliability under many parameter perturbation scenarios. This is further extended by providing a solution to the same problem using a heuristic approach.

  5. Identified Natural Hazards May Cause Adverse Impact on Sustainability of Desalination Plants in Red Sea

    NASA Astrophysics Data System (ADS)

    Aburizaiza, O. S.; Zaigham, N. A.; Nayyar, Z. A.; Mahar, G. A.; Siddique, A.; Eusufi, S. N.

    2011-12-01

    The Red Sea and its surrounding countries have harsh arid climatic conditions where fast growth of the socio-economic activities and rapid change of lifestyle have caused tremendous stress on water to the level of acute crisis. To meet the water demands, the Red Sea countries have adopted seawater desalination giving priority against their land-based resources. Saudi Arabia is the largest desalinated-water producers in the Red Sea and has practically no adequate backup plan in case of sudden unforeseen emergency. Out of about 3.64 million m3/day, Saudi Arabia is alone being desalinated about 3.29 m3/day seawater from Red Sea and more projects are in progress. Present integrated research study has identified some of natural and anthropogenic hazards, which may be major threats to the quality of the seawater as well as to the desalination plants themselves. Results of present study reveal that the submarine complex morphologic features may cause the isolation of Red Sea from any of the open sea, the increase in the seismicity trends, the active volcanism causing unique longitudinal as well as transverse deformations of the axial trough particularly in the southern part of the Red Sea, the consistently generating enormous hot-brine tectonic-factory all along the deeper parts of the Red Sea rifting trough and other related issues. Considering the identified odd conditions, the total dependence on seawater desalination may not be worthwhile for sustainable water management strategy and consequent socio-economic developments in future. It is recommended that the priority should also be given mainly in three main disciplines to meet the future water challenges - one, developing reliable backup water management; second, alternate options for the supplementary resources of water; and third, the development and immediate implementation of the water-use conservation strategy plan.

  6. Composition and Variability of Biofouling Organisms in Seawater Reverse Osmosis Desalination Plants ▿ †

    PubMed Central

    Zhang, Minglu; Jiang, Sunny; Tanuwidjaja, Dian; Voutchkov, Nikolay; Hoek, Eric M. V.; Cai, Baoli

    2011-01-01

    Seawater reverse osmosis (SWRO) membrane biofouling remains a common challenge in the desalination industry, but the marine bacterial community that causes membrane fouling is poorly understood. Microbial communities at different stages of treatment processes (intake, cartridge filtration, and SWRO) of a desalination pilot plant were examined by both culture-based and culture-independent approaches. Bacterial isolates were identified to match the genera Shewanella, Alteromonas, Vibrio, and Cellulophaga based on 16S rRNA gene sequencing analysis. The 16S rRNA gene clone library of the SWRO membrane biofilm showed that a filamentous bacterium, Leucothrix mucor, which belongs to the gammaproteobacteria, accounted for nearly 30% of the clone library, while the rest of the microorganisms (61.2% of the total clones) were related to the alphaproteobacteria. 16S rRNA gene terminal restriction fragment length polymorphism (T-RFLP) analysis indicated that bacteria colonizing the SWRO membrane represented a subportion of microbes in the source seawater; however, they were quite different from those colonizing the cartridge filter. The examination of five SWRO membranes from desalination plants located in different parts of the world showed that although the bacterial communities from the membranes were not identical to each other, some dominant bacteria were commonly observed. In contrast, bacterial communities in source seawater were significantly different based on location and season. Microbial profiles from 14 cartridge filters collected from different plants also revealed spatial trends. PMID:21551282

  7. Composition and variability of biofouling organisms in seawater reverse osmosis desalination plants.

    PubMed

    Zhang, Minglu; Jiang, Sunny; Tanuwidjaja, Dian; Voutchkov, Nikolay; Hoek, Eric M V; Cai, Baoli

    2011-07-01

    Seawater reverse osmosis (SWRO) membrane biofouling remains a common challenge in the desalination industry, but the marine bacterial community that causes membrane fouling is poorly understood. Microbial communities at different stages of treatment processes (intake, cartridge filtration, and SWRO) of a desalination pilot plant were examined by both culture-based and culture-independent approaches. Bacterial isolates were identified to match the genera Shewanella, Alteromonas, Vibrio, and Cellulophaga based on 16S rRNA gene sequencing analysis. The 16S rRNA gene clone library of the SWRO membrane biofilm showed that a filamentous bacterium, Leucothrix mucor, which belongs to the gammaproteobacteria, accounted for nearly 30% of the clone library, while the rest of the microorganisms (61.2% of the total clones) were related to the alphaproteobacteria. 16S rRNA gene terminal restriction fragment length polymorphism (T-RFLP) analysis indicated that bacteria colonizing the SWRO membrane represented a subportion of microbes in the source seawater; however, they were quite different from those colonizing the cartridge filter. The examination of five SWRO membranes from desalination plants located in different parts of the world showed that although the bacterial communities from the membranes were not identical to each other, some dominant bacteria were commonly observed. In contrast, bacterial communities in source seawater were significantly different based on location and season. Microbial profiles from 14 cartridge filters collected from different plants also revealed spatial trends. PMID:21551282

  8. Operational Optimization of Large-Scale Parallel-Unit SWRO Desalination Plant Using Differential Evolution Algorithm

    PubMed Central

    Wang, Xiaolong; Jiang, Aipeng; Jiangzhou, Shu; Li, Ping

    2014-01-01

    A large-scale parallel-unit seawater reverse osmosis desalination plant contains many reverse osmosis (RO) units. If the operating conditions change, these RO units will not work at the optimal design points which are computed before the plant is built. The operational optimization problem (OOP) of the plant is to find out a scheduling of operation to minimize the total running cost when the change happens. In this paper, the OOP is modelled as a mixed-integer nonlinear programming problem. A two-stage differential evolution algorithm is proposed to solve this OOP. Experimental results show that the proposed method is satisfactory in solution quality. PMID:24701180

  9. Operational optimization of large-scale parallel-unit SWRO desalination plant using differential evolution algorithm.

    PubMed

    Wang, Jian; Wang, Xiaolong; Jiang, Aipeng; Jiangzhou, Shu; Li, Ping

    2014-01-01

    A large-scale parallel-unit seawater reverse osmosis desalination plant contains many reverse osmosis (RO) units. If the operating conditions change, these RO units will not work at the optimal design points which are computed before the plant is built. The operational optimization problem (OOP) of the plant is to find out a scheduling of operation to minimize the total running cost when the change happens. In this paper, the OOP is modelled as a mixed-integer nonlinear programming problem. A two-stage differential evolution algorithm is proposed to solve this OOP. Experimental results show that the proposed method is satisfactory in solution quality. PMID:24701180

  10. Robust Operation of a System of Reservoir and Desalination Plant using a Multi-Objective Optimization Framework

    NASA Astrophysics Data System (ADS)

    Ng, T.; Bhushan, R.

    2013-12-01

    In many cities, the water supply system is under stress due to increased competition for reliable fresh water supplies from population growth and climate uncertainties resulting in water insecurity. One method to augment fresh water supplies is seawater desalination, which converts seawater to fresh water for industrial and domestic potable and non-potable uses. We propose to address this issue of water supply scarcity and uncertainty in coastal metropolitan cities by developing a robust operating policy for the joint operation of a desalination plant with a freshwater reservoir system using a multi-objective optimization framework. Due to the unlimited availability of seawater, desalination has a strong potential as a reliable source of water in coastal cities around the world. However, being an energy intensive and expensive process, its application is limited. Reservoir water, while cheaper due to its relatively small cost of transportation to the cities, is often limited and variable in its availability. We observe that combining the operation of a desalination plant with a water supply reservoir leads to more cost efficient and reliable water production than if both were to be operated separately. We model a joint reservoir-desalination system as a multi-objective optimization problem with risk, resilience, and vulnerability as the objective functions, and cost as a constraint. In our simulations, rule curves determine the release from the reservoir as a function of existing storage level, and the remaining demand that is unmet by the release from the reservoir determines the amount of water produced from desalination. The overall cost of the system is the sum of the cost of transporting reservoir water and the cost of energy of desalinating seawater. We employ a genetic algorithm to find the optimal values of the thresholds of the reservoir rule curves and the maximum operating capacity of the desalination plant. We will discuss the tradeoffs between water

  11. An arduino based control system for a brackish water desalination plant

    NASA Astrophysics Data System (ADS)

    Caraballo, Ginna

    Water scarcity for agriculture is one of the most important challenges to improve food security worldwide. In this thesis we study the potential to develop a low-cost controller for a small scale brackish desalination plant that consists of proven water treatment technologies, reverse osmosis, cation exchange, and nanofiltration to treat groundwater into two final products: drinking water and irrigation water. The plant is powered by a combination of wind and solar power systems. The low-cost controller uses Arduino Mega, and Arduino DUE, which consist of ATmega2560 and Atmel SAM3X8E ARM Cortex-M3 CPU microcontrollers. These are widely used systems characterized for good performance and low cost. However, Arduino also requires drivers and interfaces to allow the control and monitoring of sensors and actuators. The thesis explains the process, as well as the hardware and software implemented.

  12. Thermodynamic analysis of osmotic energy recovery at a reverse osmosis desalination plant.

    PubMed

    Feinberg, Benjamin J; Ramon, Guy Z; Hoek, Eric M V

    2013-03-19

    Recent years have seen a substantial reduction of the specific energy consumption (SEC) in seawater reverse osmosis (RO) desalination due to improvements made in hydraulic energy recovery (HER) as well as RO membranes and related process technologies. Theoretically, significant potential for further reduction in energy consumption may lie in harvesting the high chemical potential contained in RO concentrate using salinity gradient power technologies. Herein, "osmotic energy recovery" (OER) is evaluated in a seawater RO plant that includes state-of-the-art RO membranes, plant designs, operating conditions, and HER technology. Here we assume the use of treated wastewater effluent as the OER dilute feed, which may not be available in suitable quality or quantity to allow operation of the coupled process. A two-stage OER configuration could reduce the SEC of seawater RO plants to well below the theoretical minimum work of separation for state-of-the-art RO-HER configurations with a breakeven OER CAPEX equivalent to 42% of typical RO-HER plant cost suggesting significant cost savings may also be realized. At present, there is no commercially viable OER technology; hence, the feasibility of using OER at seawater RO plants remains speculative, however attractive. PMID:23331042

  13. Nuclear Power Plants. Revised.

    ERIC Educational Resources Information Center

    Lyerly, Ray L.; Mitchell, Walter, III

    This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. Among the topics discussed are: Why Use Nuclear Power?; From Atoms to Electricity; Reactor Types; Typical Plant Design Features; The Cost of Nuclear Power; Plants in the United States; Developments in Foreign…

  14. Bacterial community structure and variation in a full-scale seawater desalination plant for drinking water production.

    PubMed

    Belila, A; El-Chakhtoura, J; Otaibi, N; Muyzer, G; Gonzalez-Gil, G; Saikaly, P E; van Loosdrecht, M C M; Vrouwenvelder, J S

    2016-05-01

    Microbial processes inevitably play a role in membrane-based desalination plants, mainly recognized as membrane biofouling. We assessed the bacterial community structure and diversity during different treatment steps in a full-scale seawater desalination plant producing 40,000 m(3)/d of drinking water. Water samples were taken over the full treatment train consisting of chlorination, spruce media and cartridge filters, de-chlorination, first and second pass reverse osmosis (RO) membranes and final chlorine dosage for drinking water distribution. The water samples were analyzed for water quality parameters (total bacterial cell number, total organic carbon, conductivity, pH, etc.) and microbial community composition by 16S rRNA gene pyrosequencing. The planktonic microbial community was dominated by Proteobacteria (48.6%) followed by Bacteroidetes (15%), Firmicutes (9.3%) and Cyanobacteria (4.9%). During the pretreatment step, the spruce media filter did not impact the bacterial community composition dominated by Proteobacteria. In contrast, the RO and final chlorination treatment steps reduced the Proteobacterial relative abundance in the produced water where Firmicutes constituted the most dominant bacterial group. Shannon and Chao1 diversity indices showed that bacterial species richness and diversity decreased during the seawater desalination process. The two-stage RO filtration strongly reduced the water conductivity (>99%), TOC concentration (98.5%) and total bacterial cell number (>99%), albeit some bacterial DNA was found in the water after RO filtration. About 0.25% of the total bacterial operational taxonomic units (OTUs) were present in all stages of the desalination plant: the seawater, the RO permeates and the chlorinated drinking water, suggesting that these bacterial strains can survive in different environments such as high/low salt concentration and with/without residual disinfectant. These bacterial strains were not caused by contamination during

  15. Preliminary research study for the construction of a pilot cogeneration desalination plant in southern California. Water treatment technology program report No. 7 (Final)

    SciTech Connect

    Tadros, S.K.

    1995-05-01

    A conceptual plant design and a slightly conservative cost estimate were developed to evaluate the economic desirability and the overall system efficiency impact. The conceptual design includes a gas turbine-generator set with a heat recovery steam generator to produce electricity and steam. The steam is utilized in the desalination processes. For this study, two desalination technologies were considered: multi-effect distillation and multi-stage flash evaporation.

  16. Reducing the impact of a desalination plant using stochastic modeling and optimization techniques

    NASA Astrophysics Data System (ADS)

    Alcolea, Andres; Renard, Philippe; Mariethoz, Gregoire; Bertone, François

    2009-02-01

    SummaryWater is critical for economic growth in coastal areas. In this context, desalination has become an increasingly important technology over the last five decades. It often has environmental side effects, especially when the input water is pumped directly from the sea via intake pipelines. However, it is generally more efficient and cheaper to desalt brackish groundwater from beach wells rather than desalting seawater. Natural attenuation is also gained and hazards due to anthropogenic pollution of seawater are reduced. In order to minimize allocation and operational costs and impacts on groundwater resources, an optimum pumping network is required. Optimization techniques are often applied to this end. Because of aquifer heterogeneity, designing the optimum pumping network demands reliable characterizations of aquifer parameters. An optimum pumping network in a coastal aquifer in Oman, where a desalination plant currently pumps brackish groundwater at a rate of 1200 m 3/h for a freshwater production of 504 m 3/h (insufficient to satisfy the growing demand in the area) was designed using stochastic inverse modeling together with optimization techniques. The Monte Carlo analysis of 200 simulations of transmissivity and storage coefficient fields conditioned to the response to stresses of tidal fluctuation and three long term pumping tests was performed. These simulations are physically plausible and fit the available data well. Simulated transmissivity fields are used to design the optimum pumping configuration required to increase the current pumping rate to 9000 m 3/h, for a freshwater production of 3346 m 3/h (more than six times larger than the existing one). For this task, new pumping wells need to be sited and their pumping rates defined. These unknowns are determined by a genetic algorithm that minimizes a function accounting for: (1) drilling, operational and maintenance costs, (2) target discharge and minimum drawdown (i.e., minimum aquifer

  17. Dynamic bacterial communities on reverse-osmosis membranes in a full-scale desalination plant.

    PubMed

    Manes, C-L de O; West, N; Rapenne, S; Lebaron, P

    2011-01-01

    To better understand biofouling of seawater reverse osmosis (SWRO) membranes, bacterial diversity was characterized in the intake water, in subsequently pretreated water and on SWRO membranes from a full-scale desalination plant (FSDP) during a 9 month period. 16S rRNA gene fingerprinting and sequencing revealed that bacterial communities in the water samples and on the SWRO membranes were very different. For the different sampling dates, the bacterial diversity of the active and the total bacterial fractions of the water samples remained relatively stable over the sampling period whereas the bacterial community structure on the four SWRO membrane samples was significantly different. The richness and evenness of the SWRO membrane bacterial communities increased with usage time with an increase in the Shannon diversity index of 2.2 to 3.7. In the oldest SWRO membrane (330 days), no single operational taxonomic unit (OTU) dominated and the majority of the OTUs fell into the Alphaproteobacteria or the Planctomycetes. In striking contrast, a Betaproteobacteria OTU affiliated to the genus Ideonella was dominant and exclusively found in the membrane used for the shortest time (10 days). This suggests that bacteria belonging to this genus could be one of the primary colonizers of the SWRO membrane. Knowledge of the dominant bacterial species on SWRO membranes and their dynamics should help guide culture studies for physiological characterization of biofilm forming species. PMID:21108068

  18. Nuclear Power Plant Technician

    ERIC Educational Resources Information Center

    Randall, George A.

    1975-01-01

    The author recognizes a body of basic knowledge in nuclear power plant technoogy that can be taught in school programs, and lists the various courses, aiming to fill the anticipated need for nuclear-trained manpower--persons holding an associate degree in engineering technology. (Author/BP)

  19. NUCLEAR POWER PLANT

    DOEpatents

    Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

    1963-05-14

    A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

  20. Shoreham Nuclear Power Plant

    SciTech Connect

    1992-12-31

    The United States Supreme Court, with PG&E and Silkwood, and in the eight years since, has expanded the acceptable extent of state regulation of commercial nuclear power plants. In PG&E, the Court established the acceptability of state regulation that purports to be concerned with the non-radiological aspects of nuclear plant operations but that, as a practical matter, is concerned with their radiological hazards. In Silkwood, the Court established the acceptability of state regulation of radiological hazards when its impact on federal regulation of radiological hazards is indirect and incidental. Finally, in Goodyear and English, the Court confirmed and elaborated on such state regulation. Subject to political demands either for additional involvement in commercial nuclear power plant regulation or from political interests opposed altogether to nuclear power, some states, in the 1980s, sought to expand even further the involvement of state and local governments in nuclear plant regulation. Indeed, some states sought and in some instances acquired, through innovative and extraordinary means, a degree of involvement in the regulation of radiological hazards that seriously erodes and undermines the role of the federal government in such regulation. In particular, the State of New York concluded with the Long Island Lighting Company (LILCO), in February 1989, an agreement for the purchase of New York of the Shoreham nuclear power plant on Long Island. A response to failed efforts by New York to prevent the issuance by the NRC of a license to LILCO to operate the plant, the agreement was concluded to allow New York to close the plant either altogether or to convert it to a fossil fuel facility. The opposition to the sale of Shoreham is discussed.

  1. Linking near- and far-field hydrodynamic models for simulation of desalination plant brine discharges.

    PubMed

    Botelho, D A; Barry, M E; Collecutt, G C; Brook, J; Wiltshire, D

    2013-01-01

    A desalination plant is proposed to be the major water supply to the Olympic Dam Expansion Mining project. Located in the Upper Spencer Gulf, South Australia, the site was chosen due to the existence of strong currents and their likely advantages in terms of mixing and dilution of discharged return water. A high-resolution hydrodynamic model (Estuary, Lake and Coastal Ocean Model, ELCOM) was constructed and, through a rigorous review process, was shown to reproduce the intricate details of the Spencer Gulf dynamics, including those characterising the discharge site. Notwithstanding this, it was found that deploying typically adopted 'direct insertion' techniques to simulate the brine discharge within the hydrodynamic model was problematic. Specifically, it was found that in this study the direct insertion technique delivered highly conservative brine dilution predictions in and around the proposed site, and that these were grid and time-step dependent. To improve the predictive capability, a strategy to link validated computational fluid dynamics (CFD) predictions to hydrodynamic simulations was devised. In this strategy, environmental conditions from ELCOM were used to produce boundary conditions for execution of a suite of CFD simulations. In turn, the CFD simulations provided the brine dilutions and flow rates to be applied in ELCOM. In order to conserve mass in a system-wide sense, artificial salt sinks were introduced to the ELCOM model such that salt quantities were conserved. As a result of this process, ELCOM predictions were naturally very similar to CFD predictions near the diffuser, whilst at the same time they produced an area of influence (further afield) comparable to direct insertion methods. It was concluded that the linkage of the models, in comparison to direct insertion methods, constituted a more realistic and defensible alternative to predict the far-field dispersion of outfall discharges, particularly with regards to the estimation of brine

  2. Future Energy Benchmark for Desalination: is it Better to have a Power (electricity) Plant with ro or Med/msf?

    NASA Astrophysics Data System (ADS)

    Shahzad, Muhammad Wakil; Ng, Kim Choon; Thu, Kyaw

    2016-06-01

    Power and desalination cogeneration plants are common in many water scared courtiers. Designers and planners for cogeneration face tough challenges in deciding the options:- Is it better to operate a power plant (PP) with the reverse osmosis (i.e., PP+RO) or the thermally-driven multi-effect distillation/multi-stage flashed (PP+MED/MSF) methods. From literature, the RO methods are known to be energy efficient whilst the MED/MSF are known to have excellent thermodynamic synergies as only low pressure and temperature steam are used. Not with-standing the challenges of severe feed seawater of the Gulf, such as the frequent harmful algae blooms (HABs) and high silt contents, this presentation presents a quantitative analyses using the exergy and energetic approaches in evaluating the performances of a real cogeneration plant that was recently proposed in the eastern part of Saudi Arabia. We demonstrate that the process choice of PP+RO versus PP+MED depends on the inherent efficiencies of individual process method which is closely related to innovative process design. In this connection, a method of primary fuel cost apportionment for a co-generation plant with a MED desalination is presented. We show that an energy approach, that captures the quality of expanding steam, is a better method over the conventional work output (energetic) and the energy method seems to be over-penalizing a thermally-driven MED by as much as 22% in the operating cost of water.

  3. Nuclear Plant Inspection

    NASA Technical Reports Server (NTRS)

    1983-01-01

    Engineers from the Power Authority of the State of New York use a Crack Growth Analysis Program supplied by COSMIC (Computer Software Management and Information Center) in one stage of nuclear plant inspection. Welds of the nuclear steam supply system are checked for cracks; radiographs, dye penetration and visual inspections are performed to locate cracks in the metal structure and welds. The software package includes three separate crack growth analysis models and enables necessary repairs to be planned before serious problems develop.

  4. Microfluidic desalination techniques and their potential applications.

    PubMed

    Roelofs, S H; van den Berg, A; Odijk, M

    2015-09-01

    In this review we discuss recent developments in the emerging research field of miniaturized desalination. Traditionally desalination is performed to convert salt water into potable water and research is focused on improving performance of large-scale desalination plants. Microfluidic desalination offers several new opportunities in comparison to macro-scale desalination, such as providing a platform to increase fundamental knowledge of ion transport on the nano- and microfluidic scale and new microfluidic sample preparation methods. This approach has also lead to the development of new desalination techniques, based on micro/nanofluidic ion-transport phenomena, which are potential candidates for up-scaling to (portable) drinking water devices. This review assesses microfluidic desalination techniques on their applications and is meant to contribute to further implementation of microfluidic desalination techniques in the lab-on-chip community. PMID:26226407

  5. Source water quality shaping different fouling scenarios in a full-scale desalination plant at the Red Sea.

    PubMed

    Khan, Muhammad Tariq; Manes, Carmem-Lara de O; Aubry, Cyril; Croué, Jean-Philippe

    2013-02-01

    The complexity of Reverse Osmosis (RO) membrane fouling phenomenon has been widely studied and several factors influencing it have been reported by many researchers. This original study involves the investigation of two different fouling profiles produced at a seawater RO desalination plant installed on a floating mobile barge. The plant was moved along the coastline of the Red Sea in Saudi Arabia. The two locations where the barge was anchored showed different water quality. At the second location, two modules were harvested. One of the modules was pre-fouled by inorganics during plant operation at the previous site while the other was installed at the second site. Fouled membranes were subjected to a wide range of chemical and microbiological characterization procedures. Drastically different fouling patterns were observed in the two membranes which indicates the influence of source water quality on membrane surface modification and on fouling of RO membranes. PMID:23164217

  6. Beloyarsk Nuclear Power Plant

    SciTech Connect

    1997-08-01

    The Beloyarsk Nuclear Power Plant (BNPP) is located in Zarechny, approximately 60 km east of Ekaterinberg along the Trans-Siberian Highway. Zarechny, a small city of approximately 30,000 residents, was built to support BNPP operations. It is a closed city to unescorted visitors. Residents must show identification for entry. BNPP is one of the first and oldest commercial nuclear power plants in Russia and began operations in 1964. As for most nuclear power plants in the Russian Federation, BNPP is operated by Rosenergoatom, which is subordinated to the Ministry of Atomic Energy of the Russian Federation (Minatom). BNPP is the site of three nuclear reactors, Units 1, 2, and 3. Units 1 and 2, which have been shut-down and defueled, were graphite moderated reactors. The units were shut-down in 1981 and 1989. Unit 3, a BN-600 reactor, is a 600 MW(electric) sodium-cooled fast breeder reactor. Unit 3 went on-line in April 1980 and produces electric power which is fed into a distribution grid and thermal power which provides heat to Zarechny. The paper also discusses the SF NIKIET, the Sverdiovsk Branch of NIKIET, Moscow, which is the research and development branch of the parent NIKEIT and is primarily a design institute responsible for reactor design. Central to its operations is a 15 megawatt IVV research reactor. The paper discusses general security and fissile material control and accountability at these two facilities.

  7. Nuclear power plant maintainability.

    PubMed

    Seminara, J L; Parsons, S O

    1982-09-01

    In the mid-1970s a general awareness of human factors engineering deficiencies associated with power plant control rooms took shape and the Electric Power Research Institute (EPRI) awarded the Lockheed Corporation a contract to review the human factors aspects of five representative operational control rooms and their associated simulators. This investigation revealed a host of major and minor deficiencies that assumed unforeseen dimensions in the post- Three Mile Island accident period. In the course of examining operational problems (Seminara et al, 1976) and subsequently the methods for overcoming such problems (Seminara et al, 1979, 1980) indications surfaced that power plants were far from ideal in meeting the needs of maintenance personnel. Accordingly, EPRI sponsored an investigation of the human factors aspects of power plant maintainability (Seminara, 1981). This paper provides an overview of the maintainability problems and issues encountered in the course of reviewing five nuclear power plants. PMID:15676441

  8. Nuclear Plant Data Bank

    SciTech Connect

    Booker, C.P.; Turner, M.R.; Spore, J.W.

    1986-01-01

    The Nuclear Plant Data Bank (NPDB) is being developed at the Los Alamos National Laboratory to assist analysts in the rapid and accurate creation of input decks for reactor transient analysis. The NPDB will reduce the time and cost of the creation or modification of a typical input deck. This data bank will be an invaluable tool in the timely investigation of recent and ongoing nuclear reactor safety analysis. This paper discusses the status and plans for the NPDB development and describes its anticipated structure and capabilities.

  9. Contribution of power and desalination plants to the levels of volatile liquid hydrocarbons in the nearby coastal areas of Kuwait

    SciTech Connect

    Saeed, T.; Khordagui, H.; Al-Hashash, H.

    1999-07-01

    The levels and distribution of volatile liquid hydrocarbons (VLHs) were determined in Kuwait`s coastal areas in the vicinity of outlets of power and desalination plants. About 230 samples were collected from the selected sampling locations over the 4 seasons. The VLHs in the samples were analyzed using Grob`s closed-loop stripping technique and GC with FID and confirmed by GC/MS. The results showed that significant levels of VLHs were present. The levels ranged from 307 to 6,500 ng/L and from 2,880 to 7,811 ng/L in Kuwait Bay and Sulaibekhat Bay, respectively. The annual average for VLHs near Al-Zor power plant ranged from 465 to 4,665 ng/L. Benzenoids formed the bulk (about 80%) of the VLHs present. Comparison with the levels in the outlets indicated that Doha West power plant contributed much higher levels of VLHs to the coastal areas than Al-Zor plant.

  10. Operate a Nuclear Power Plant.

    ERIC Educational Resources Information Center

    Frimpter, Bonnie J.; And Others

    1983-01-01

    Describes classroom use of a computer program originally published in Creative Computing magazine. "The Nuclear Power Plant" (runs on Apple II with 48K memory) simulates the operating of a nuclear generating station, requiring students to make decisions as they assume the task of managing the plant. (JN)

  11. Owners of Nuclear Power Plants

    SciTech Connect

    Reid, R.L.

    2000-01-12

    Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of November 1999. The report is divided into sections representing different aspects of nuclear plant ownership.

  12. Owners of nuclear power plants

    SciTech Connect

    Hudson, C.R.; White, V.S.

    1996-11-01

    Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of July 1996. The report is divided into sections representing different aspects of nuclear plant ownership.

  13. Assessment of the abiotic and biotic effects of sodium metabisulphite pulses discharged from desalination plant chemical treatments on seagrass (Cymodocea nodosa) habitats in the Canary Islands.

    PubMed

    Portillo, E; Ruiz de la Rosa, M; Louzara, G; Ruiz, J M; Marín-Guirao, L; Quesada, J; González, J C; Roque, F; González, N; Mendoza, H

    2014-03-15

    Reverse osmosis membranes at many desalination plants are disinfected by periodic shock treatments with sodium metabisulphite, which have potentially toxic effects to the environment for marine life, although no empirical and experimental evidence for this is yet available. The aim of this study was to characterise for the first time, the physico-chemical modification of the marine environment and its biological effects, caused by hypersaline plumes during these membrane cleaning treatments. The case study was the Maspalomas II desalination plant, located in the south of Gran Canaria (Canary Islands, Spain). Toxicity bioassays were performed on marine species characteristic for the infralittoral soft bottoms influenced by the brine plume (Synodus synodus and Cymodocea nodosa), and revealed a high sensitivity to short-term exposure to low sodium metabisulphite concentrations. The corrective measure of incorporating a diffusion system with Venturi Eductors reduced nearly all the areas of influence, virtually eliminating the impact of the disinfectant. PMID:24495930

  14. Nuclear Power Plant Simulation Game.

    ERIC Educational Resources Information Center

    Weiss, Fran

    1979-01-01

    Presents a nuclear power plant simulation game which is designed to involve a class of 30 junior or senior high school students. Scientific, ecological, and social issues covered in the game are also presented. (HM)

  15. High Energy Utilization, Co-Generation Nuclear power Plants With Static Energy Conversion

    SciTech Connect

    El-Genk, Mohamed S.; Tournier, Jean-Michel P.

    2002-07-01

    In addition to being cost effective, very small nuclear power plants with static energy conversion could meet the needs and the energy mix in underdeveloped countries and remote communities, which may include electricity, residential and industrial space heating, seawater desalination, and/or high temperature process heat or steam for industrial uses. These plants are also an attractive option in naval, marine, and undersea applications, when the absence of a sound signature is highly desirable. An Analysis is performed of Gas Cooled Reactor (CGR) and Liquid Metal Cooled Reactor (LMR), very small nuclear power plants with static energy conversion, using a combination of options. These include Alkali Metal Thermal-to-Electric Converters (AMTECs) and both single segment and segmented thermoelectric converters. The total energy utilization of these plants exceeds 88%. It includes the fraction of the reactor's thermal power converted into electricity and delivered to the Grid at 6.6 kVA and those used for residential and industrial space heating at {approx}370 K, seawater desalination at 400 K, and/or high temperature process heat or steam at {approx}850 K. In addition to its inherently high reliability, modularity, low maintenance and redundancy, static energy conversion used in the present study could deliver electricity to the Grid at a net efficiency of 29.5%. A LMR plant delivers 2-3 times the fraction of the reactor thermal power converted into electricity in a GCR plant, but could not provide for both seawater desalination and high temperature process heat/steam concurrently, which is possible in GCR plants. The fraction of the reactor's thermal power used for non-electrical power generation in a GCR plant is {approx} 10 - 15% higher than in a LMR plant. (authors)

  16. Design and cost of near-term OTEC (Ocean Thermal Energy Conversion) plants for the production of desalinated water and electric power

    NASA Astrophysics Data System (ADS)

    Rabas, T.; Panchal, C. B.; Genens, L.

    There currently is an increasing need for both potable water and power for many islands in the Pacific and Caribbean. The Ocean Thermal Energy Conversion (OTEC) technology fills these needs and is a viable option because of the unlimited supply of ocean thermal energy for the production of both desalinated water and electricity. The OTEC plant design must be flexible to meet the product-mix demands that can be very different from site to site. Different OTEC plants are described that can supply various mixes of desalinated water and vapor; the extremes being either all water and no power or no water and all power. The economics for these plants are also presented. The same flow rates and pipe sizes for both the warm and cold seawater streams are used for different plant designs. The OTEC plant designs are characterized as near-term because no major technical issues need to be resolved or demonstrated. The plant concepts are based on DOE-sponsored experiments dealing with power systems, advanced heat exchanger designs, corrosion and fouling of heat exchange surfaces, and flash evaporation and moisture removal from the vapor using multiple spouts. In addition, the mature multistage flash evaporator technology is incorporated into the plant designs where appropriate. For the supply and discharge warm and cold uncertainties do exist because the required pipe sizes are larger than the maximum currently deployed; 40 inch high density polyethylene pipe at Keahole Point in Hawaii.

  17. Design and cost of near-term OTEC (Ocean Thermal Energy Conversion) plants for the production of desalinated water and electric power. [Ocean Thermal Energy Conversion (OTEC)

    SciTech Connect

    Rabas, T.; Panchal, C.; Genens, L.

    1990-01-01

    There currently is an increasing need for both potable water and power for many islands in the Pacific and Caribbean. The Ocean Thermal Energy Conversion (OTEC) technology fills these needs and is a viable option because of the unlimited supply of ocean thermal energy for the production of both desalinated water and electricity. The OTEC plant design must be flexible to meet the product-mix demands that can be very different from site to site. This paper describes different OTEC plants that can supply various mixes of desalinated water and vapor -- the extremes being either all water and no power or no water and all power. The economics for these plants are also presented. The same flow rates and pipe sizes for both the warm and cold seawater streams are used for different plant designs. The OTEC plant designs are characterized as near-term because no major technical issues need to be resolved or demonstrated. The plant concepts are based on DOE-sponsored experiments dealing with power systems, advanced heat exchanger designs, corrosion and fouling of heat exchange surfaces, and flash evaporation and moisture removal from the vapor using multiple spouts. In addition, the mature multistage flash evaporator technology is incorporated into the plant designs were appropriate. For the supply and discharge warm and cold uncertainties do exist because the required pipe sizes are larger than the maximum currently deployed -- 40-inch high-density polyethylene pipe at Keahole Point in Hawaii. 30 refs., 6 figs., 8 tabs.

  18. The future of seawater desalination: energy, technology, and the environment.

    PubMed

    Elimelech, Menachem; Phillip, William A

    2011-08-01

    In recent years, numerous large-scale seawater desalination plants have been built in water-stressed countries to augment available water resources, and construction of new desalination plants is expected to increase in the near future. Despite major advancements in desalination technologies, seawater desalination is still more energy intensive compared to conventional technologies for the treatment of fresh water. There are also concerns about the potential environmental impacts of large-scale seawater desalination plants. Here, we review the possible reductions in energy demand by state-of-the-art seawater desalination technologies, the potential role of advanced materials and innovative technologies in improving performance, and the sustainability of desalination as a technological solution to global water shortages. PMID:21817042

  19. Dynamic Simulation Nuclear Power Plants

    Energy Science and Technology Software Center (ESTSC)

    1992-03-03

    DSNP (Dynamic Simulator for Nuclear Power-Plants) is a system of programs and data files by which a nuclear power plant, or part thereof, can be simulated. The acronym DSNP is used interchangeably for the DSNP language, the DSNP libraries, the DSNP precompiler, and the DSNP document generator. The DSNP language is a special-purpose, block-oriented, digital-simulation language developed to facilitate the preparation of dynamic simulations of a large variety of nuclear power plants. It is amore » user-oriented language that permits the user to prepare simulation programs directly from power plant block diagrams and flow charts by recognizing the symbolic DSNP statements for the appropriate physical components and listing these statements in a logical sequence according to the flow of physical properties in the simulated power plant. Physical components of nuclear power plants are represented by functional blocks, or modules. Many of the more complex components are represented by several modules. The nuclear reactor, for example, has a kinetic module, a power distribution module, a feedback module, a thermodynamic module, a hydraulic module, and a radioactive heat decay module. These modules are stored in DSNP libraries in the form of a DSNP subroutine or function, a block of statements, a macro, or a combination of the above. Basic functional blocks such as integrators, pipes, function generators, connectors, and many auxiliary functions representing properties of materials used in nuclear power plants are also available. The DSNP precompiler analyzes the DSNP simulation program, performs the appropriate translations, inserts the requested modules from the library, links these modules together, searches necessary data files, and produces a simulation program in FORTRAN.« less

  20. IRIS Reactor a Suitable Option to Provide Energy and Water Desalination for the Mexican Northwest Region

    SciTech Connect

    Alonso, G.; Ramirez, R.; Gomez, C.; Viais, J.

    2004-10-03

    The Northwest region of Mexico has a deficit of potable water, along this necessity is the region growth, which requires of additional energy capacity. The IRIS reactor offers a very suitable source of energy given its modular size of 300 MWe and it can be coupled with a desalination plant to provide the potable water for human consumption, agriculture and industry. The present paper assess the water and energy requirements for the Northwest region of Mexico and how the deployment of the IRIS reactor can satisfy those necessities. The possible sites for deployment of Nuclear Reactors are considered given the seismic constraints and the closeness of the sea for external cooling. And in the other hand, the size of the desalination plant and the type of desalination process are assessed accordingly with the water deficit of the region.

  1. ALARA at nuclear power plants

    SciTech Connect

    Baum, J.W.

    1990-01-01

    Implementation of the As Low As Reasonably Achievable (ALARA) principle at nuclear power plants presents a continuing challenge for health physicists at utility corporate and plant levels, for plant designers, and for regulatory agencies. The relatively large collective doses at some plants are being addressed though a variety of dose reduction techniques. It is planned that this report will include material on historical aspects, management, valuation of dose reduction, quantitative and qualitative aspects of optimization, design, operational considerations, and training. The status of this work is summarized in this report. 30 refs., 1 fig., 6 tabs.

  2. Desalination: the state-of-the-art

    SciTech Connect

    Awerbach, L.

    1984-02-01

    A review of desalination technologies shows a good level of success at acceptable costs, with plants ranging in size from small units used for hotels to those with 40,000 m/sup 3/. This article covers the 2200 plants with 100 m/sup 3/ capacity, beginning with an overview of desalination theory. Multiple-effect distillation is expected to supplant the predominant multistage flash (MSF). Both technologies are described, along with vapor compression (VC) distillation, reverse osmosis, freezing desalination, electrodialysis, and some new developments. 8 figures (DCK)

  3. The Next Generation Nuclear Plant

    SciTech Connect

    Dr. David A. Petti

    2009-01-01

    The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950°C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies.

  4. Advanced nuclear plant control complex

    DOEpatents

    Scarola, Kenneth; Jamison, David S.; Manazir, Richard M.; Rescorl, Robert L.; Harmon, Daryl L.

    1993-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

  5. Sabotage at Nuclear Power Plants

    SciTech Connect

    Purvis, James W.

    1999-07-21

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

  6. Relationship between performance deterioration of a polyamide reverse osmosis membrane used in a seawater desalination plant and changes in its physicochemical properties.

    PubMed

    Suzuki, Tasuma; Tanaka, Ryohei; Tahara, Marina; Isamu, Yuya; Niinae, Masakazu; Lin, Lin; Wang, Jingbo; Luh, Jeanne; Coronell, Orlando

    2016-09-01

    While it is known that the performance of reverse osmosis membranes is dependent on their physicochemical properties, the existing literature studying membranes used in treatment facilities generally focuses on foulant layers or performance changes due to fouling, not on the performance and physicochemical changes that occur to the membranes themselves. In this study, the performance and physicochemical properties of a polyamide reverse osmosis membrane used for three years in a seawater desalination plant were compared to those of a corresponding unused membrane. The relationship between performance changes during long-term use and changes in physicochemical properties was evaluated. The results showed that membrane performance deterioration (i.e., reduced water flux, reduced contaminant rejection, and increased fouling propensity) occurred as a result of membrane use in the desalination facility, and that the main physicochemical changes responsible for performance deterioration were reduction in PVA coating coverage and bromine uptake by polyamide. The latter was likely promoted by oxidant residual in the membrane feed water. Our findings indicate that the optimization of membrane materials and processes towards maximizing the stability of the PVA coating and ensuring complete removal of oxidants in feed waters would minimize membrane performance deterioration in water purification facilities. PMID:27214345

  7. Modelling of nuclear power plant decommissioning financing.

    PubMed

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. PMID:25979740

  8. Disinfection by-product formation during seawater desalination: A review.

    PubMed

    Kim, Daekyun; Amy, Gary L; Karanfil, Tanju

    2015-09-15

    Due to increased freshwater demand across the globe, seawater desalination has become the technology of choice in augmenting water supplies in many parts of the world. The use of chemical disinfection is necessary in desalination plants for pre-treatment to control both biofouling as well as the post-disinfection of desalinated water. Although chlorine is the most commonly used disinfectant in desalination plants, its reaction with organic matter produces various disinfection by-products (DBPs) (e.g., trihalomethanes [THMs], haloacetic acids [HAAs], and haloacetonitriles [HANs]), and some DBPs are regulated in many countries due to their potential risks to public health. To reduce the formation of chlorinated DBPs, alternative oxidants (disinfectants) such as chloramines, chlorine dioxide, and ozone can be considered, but they also produce other types of DBPs. In addition, due to high levels of bromide and iodide concentrations in seawater, highly cytotoxic and genotoxic DBP species (i.e., brominated and iodinated DBPs) may form in distribution systems, especially when desalinated water is blended with other source waters having higher levels of organic matter. This article reviews the knowledge accumulated in the last few decades on DBP formation during seawater desalination, and summarizes in detail, the occurrence of DBPs in various thermal and membrane plants involving different desalination processes. The review also identifies the current challenges and future research needs for controlling DBP formation in seawater desalination plants and to reduce the potential toxicity of desalinated water. PMID:26099832

  9. Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches

    SciTech Connect

    Steven R. Sherman

    2007-06-01

    The U.S. Department of Energy, through its agents the Next Generation Nuclear Plant Project and the Nuclear Hydrogen Initiative, is working on developing the technologies to enable the large scale production of hydrogen using nuclear power. A very important consideration in the design of a co-located and connected nuclear plant/hydrogen plant facility is safety. This study provides an overview of the safety issues associated with a combined plant and discusses approaches for categorizing, quantifying, and addressing the safety risks.

  10. Introduction and overall description of nuclear power plant. Volume I

    SciTech Connect

    Not Available

    1986-01-01

    Topics covered in this volume include content and purpose of booklets; how to study; producing electricity; the fossil fuel power plant; the nuclear power plant; the nuclear reactor; generating steam in a nuclear power plant; using the steam in a nuclear power plant; nuclear power station facilities; and special features of nuclear power plants.

  11. Electromagnetic compatibility of nuclear power plants

    SciTech Connect

    Cabayan, H.S.

    1983-01-01

    Lately, there has been a mounting concern about the electromagnetic compatibility of nuclear-power-plant systems mainly because of the effects due to the nuclear electromagnetic pulse, and also because of the introduction of more-sophisticated and, therefore, more-susceptible solid-state devices into the plants. Questions have been raised about the adequacy of solid-state-device protection against plant electromagnetic-interference sources and transients due to the nuclear electromagnetic pulse. In this paper, the author briefly reviews the environment, and the coupling, susceptibility, and vulnerability assessment issues of commercial nuclear power plants.

  12. Nuclear Power Plant Module, NPP-1: Nuclear Power Cost Analysis.

    ERIC Educational Resources Information Center

    Whitelaw, Robert L.

    The purpose of the Nuclear Power Plant Modules, NPP-1, is to determine the total cost of electricity from a nuclear power plant in terms of all the components contributing to cost. The plan of analysis is in five parts: (1) general formulation of the cost equation; (2) capital cost and fixed charges thereon; (3) operational cost for labor,…

  13. Photocatalysis: Plasmonic solar desalination

    NASA Astrophysics Data System (ADS)

    Liu, Tianyu; Li, Yat

    2016-06-01

    The sustainability of many existing desalination technologies is questionable. Plasmon-mediated solar desalination has now been demonstrated for the first time, using an aluminium structure that absorbs photons spanning the 200 nm to 2,500 nm wavelength range, and is both cheap and 'clean'.

  14. A desalination battery.

    PubMed

    Pasta, Mauro; Wessells, Colin D; Cui, Yi; La Mantia, Fabio

    2012-02-01

    Water desalination is an important approach to provide fresh water around the world, although its high energy consumption, and thus high cost, call for new, efficient technology. Here, we demonstrate the novel concept of a "desalination battery", which operates by performing cycles in reverse on our previously reported mixing entropy battery. Rather than generating electricity from salinity differences, as in mixing entropy batteries, desalination batteries use an electrical energy input to extract sodium and chloride ions from seawater and to generate fresh water. The desalination battery is comprised by a Na(2-x)Mn(5)O(10) nanorod positive electrode and Ag/AgCl negative electrode. Here, we demonstrate an energy consumption of 0.29 Wh l(-1) for the removal of 25% salt using this novel desalination battery, which is promising when compared to reverse osmosis (~ 0.2 Wh l(-1)), the most efficient technique presently available. PMID:22268456

  15. Nuclear power plants for mobile applications

    NASA Technical Reports Server (NTRS)

    Anderson, J. L.

    1972-01-01

    Mobile nuclear powerplants for applications other than large ships and submarines will require compact, lightweight reactors with especially stringent impact-safety design. The technical and economic feasibility that the broadening role of civilian nuclear power, in general, (land-based nuclear electric generating plants and nuclear ships) can extend to lightweight, safe mobile nuclear powerplants are examined. The paper discusses technical experience, identifies potential sources of technology for advanced concepts, cites the results of economic studies of mobile nuclear powerplants, and surveys future technical capabilities needed by examining the current use and projected needs for vehicles, machines, and habitats that could effectively use mobile nuclear reactor powerplants.

  16. Plant nuclear proteomics for unraveling physiological function.

    PubMed

    Yin, Xiaojian; Komatsu, Setsuko

    2016-09-25

    The nucleus is the subcellular organelle that functions as the regulatory hub of the cell and is responsible for regulating several critical cellular functions, including cell proliferation, gene expression, and cell survival. Nuclear proteomics is a useful approach for investigating the mechanisms underlying plant responses to abiotic stresses, including protein-protein interactions, enzyme activities, and post-translational modifications. Among abiotic stresses, flooding is a major limiting factor for plant growth and yields, particularly for soybean. In this review, plant nuclei purification methods, modifications of plant nuclear proteins, and recent contributions to the field of plant nuclear proteomics are summarized. In addition, to reveal the upstream regulating mechanisms controlling soybean responses to flooding stress, the functions of flooding-responsive nuclear proteins are reviewed based on the results of nuclear proteomic analysis of soybean in the early stages of flooding stress. PMID:27004615

  17. Plant water status, ethylene evolution, N(2)-fixing efficiency, antioxidant activity and lipid peroxidation in Cicer arietinum L. nodules as affected by short-term salinization and desalinization.

    PubMed

    Nandwal, Ajit Singh; Kukreja, Sarvjeet; Kumar, Neeraj; Sharma, Praveen Kumar; Jain, Monika; Mann, Anita; Singh, Sunder

    2007-09-01

    Salinity induced changes in ethylene evolution, antioxidant defense system, N(2)-fixing efficiency and membrane integrity in relation to water and mineral status in chickpea (Cicer arietinum L.) nodules were studied under screen house conditions. At vegetative stage (55-65 DAS) plants were exposed to single saline irrigation (Cl(-) dominated) of levels 0, 2.5, 5.0 and 10.0dSm(-1) and sampled after 3d. The other set of treated plants was desalinized by flooding and the plants were sampled after further 3d. Water potential (Psiw) of leaf and osmotic potential (Psis) of leaf and nodules significantly decreased from -0.44 to -0.56MPa and from -0.65 to -1.15MPa and from -0.75 to -1.77MPa, respectively upon salinization. RWC of leaf and nodules also reduced from 86.05% to 73.30% and 94.70% to 89.98%, respectively. The decline in Psis of nodules was due to accumulation of proline and total soluble sugar. In comparison to control, the increase in ethylene (C(2)H(4)) production was 35-108% higher and correspondingly increase in 1-aminocycloprane-1-carboxylic acid (ACC) content (37-126%) and ACC oxidase activity (31-118%) was also noticed. Similarly, marked increase in H(2)O(2) (25-139%) and thiobarbituric acid substances (TBRAS, 11-133%) contents was seen. N(2)-fixing efficiency i.e. N(2)-ase activity, leghemoglobin and N contents of nodules declined significantly after saline irrigation. The induction in specific activity of antioxidant enzymes was confirmed by the increase in activity of superoxide dismutase, peroxidase, ascorbate peroxidase, glutathione reductase and glutathione transferase, whereas reverse was true for catalase. These activated enzymes could not overcome the accumulation of H(2)O(2) in nodules. Ascorbic acid content also declined from 20 to 38%, whereas Na(+)/K(+) ratio and Cl(-) content were significantly enhanced. Upon desalinization, a partial recovery in all above metabolic processes and water relations parameters was noticed. It is suggested that

  18. Desalination of brackish water from oil wells

    SciTech Connect

    Fenton, D.M.

    1991-12-31

    This patent describes an apparatus for producing non-brackish water from brackish water found in an inactivated oil well. It comprises at least one inactive oil well located on an offshore oil platform, the well having a perforated well casing at a level of a geological formation known to contain flowable brackish water; a desalination plant located on the offshore platform receiving flowable brackish water from the inactive oil well; and means to transport the non-brackish water produced by the desalination plant. This patent also describes a method of using an inactivated oil well. It comprises ceasing oil production in an inactive oil well having a well casing that penetrates a plurality of geological formations; recovering brackish water from the inactive oil well from a geological formation containing flowable brackish water; and desalinating the brackish water producing non-brackish water.

  19. Nuclear Power Plant Concrete Structures

    SciTech Connect

    Basu, Prabir; Labbe, Pierre; Naus, Dan

    2013-01-01

    A nuclear power plant (NPP) involves complex engineering structures that are significant items of the structures, systems and components (SSC) important to the safe and reliable operation of the NPP. Concrete is the commonly used civil engineering construction material in the nuclear industry because of a number of advantageous properties. The NPP concrete structures underwent a great degree of evolution, since the commissioning of first NPP in early 1960. The increasing concern with time related to safety of the public and environment, and degradation of concrete structures due to ageing related phenomena are the driving forces for such evolution. The concrete technology underwent rapid development with the advent of chemical admixtures of plasticizer/super plasticizer category as well as viscosity modifiers and mineral admixtures like fly ash and silica fume. Application of high performance concrete (HPC) developed with chemical and mineral admixtures has been witnessed in the construction of NPP structures. Along with the beneficial effect, the use of admixtures in concrete has posed a number of challenges as well in design and construction. This along with the prospect of continuing operation beyond design life, especially after 60 years, the impact of extreme natural events ( as in the case of Fukushima NPP accident) and human induced events (e.g. commercial aircraft crash like the event of September 11th 2001) has led to further development in the area of NPP concrete structures. The present paper aims at providing an account of evolution of NPP concrete structures in last two decades by summarizing the development in the areas of concrete technology, design methodology and construction techniques, maintenance and ageing management of concrete structures.

  20. Subsurface intake systems: Green choice for improving feed water quality at SWRO desalination plants, Jeddah, Saudi Arabia.

    PubMed

    Dehwah, Abdullah H A; Missimer, Thomas M

    2016-01-01

    An investigation of three seawater reverse osmosis facilities located along the shoreline of the Red Sea of Saudi Arabia that use well intake systems showed that the pumping-induced flow of raw seawater through a coastal aquifer significantly improves feed water quality. A comparison between the surface seawater and the discharge from the wells shows that turbidity, algae, bacteria, total organic carbon, most fractions of natural organic matter (NOM), and particulate and colloidal transparent exopolymer particles (TEP) have significant reductions in concentration. Nearly all of the algae, up to 99% of the bacteria, between 84 and 100% of the biopolymer fraction of NOM, and a high percentage of the TEP were removed during transport. The data suggest that the flowpath length and hydraulic retention time in the aquifer play the most important roles in removal of the organic matter. Since the collective concentrations of bacteria, biopolymers, and TEP in the intake seawater play important roles in the biofouling of SWRO membranes, the observed reductions suggest that the desalination facilities that use well intakes systems will have a potentially lower fouling rate compared to open-ocean intake systems. Furthermore, well intake system intakes also reduce the need for chemical usage during complex pretreatment systems required for operation of SWRO facilities using open-ocean intakes and reduce environmental impacts. PMID:26497939

  1. Desalination processes and performance

    SciTech Connect

    Summers, L. J.

    1995-06-01

    Different desalination processes are evaluated for feed, capacity, performance, energy requirements, and cost. These include distillation, reverse osmosis, or electrodialysis. Detailed information is given on distillation processes and membrane processes.

  2. 78 FR 50458 - Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-19

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee Nuclear Power Station, Pilgrim Nuclear Power Station, Request for Action AGENCY: Nuclear Regulatory...

  3. Fighting the Epidemic of Nuclear Plant Leaks.

    ERIC Educational Resources Information Center

    Udell, Richard A.

    1983-01-01

    The current epidemic of steam generator tube leaks alone should put to rest the rosy future once envisioned for nuclear power. It is impossible to regulate quality into a nuclear plant; it must be built and designed that way. The economic impact of the leaks is discussed. (RM)

  4. Questions and Answers About Nuclear Power Plants.

    ERIC Educational Resources Information Center

    Environmental Protection Agency, Washington, DC.

    This pamphlet is designed to answer many of the questions that have arisen about nuclear power plants and the environment. It is organized into a question and answer format, with the questions taken from those most often asked by the public. Topics include regulation of nuclear power sources, potential dangers to people's health, whether nuclear…

  5. Nuclear power plant security assessment technical manual.

    SciTech Connect

    O'Connor, Sharon L.; Whitehead, Donnie Wayne; Potter, Claude S., III

    2007-09-01

    This report (Nuclear Power Plant Security Assessment Technical Manual) is a revision to NUREG/CR-1345 (Nuclear Power Plant Design Concepts for Sabotage Protection) that was published in January 1981. It provides conceptual and specific technical guidance for U.S. Nuclear Regulatory Commission nuclear power plant design certification and combined operating license applicants as they: (1) develop the layout of a facility (i.e., how buildings are arranged on the site property and how they are arranged internally) to enhance protection against sabotage and facilitate the use of physical security features; (2) design the physical protection system to be used at the facility; and (3) analyze the effectiveness of the PPS against the design basis threat. It should be used as a technical manual in conjunction with the 'Nuclear Power Plant Security Assessment Format and Content Guide'. The opportunity to optimize physical protection in the design of a nuclear power plant is obtained when an applicant utilizes both documents when performing a security assessment. This document provides a set of best practices that incorporates knowledge gained from more than 30 years of physical protection system design and evaluation activities at Sandia National Laboratories and insights derived from U.S. Nuclear Regulatory Commission technical staff into a manual that describes a development and analysis process of physical protection systems suitable for future nuclear power plants. In addition, selected security system technologies that may be used in a physical protection system are discussed. The scope of this document is limited to the identification of a set of best practices associated with the design and evaluation of physical security at future nuclear power plants in general. As such, it does not provide specific recommendations for the design and evaluation of physical security for any specific reactor design. These best practices should be applicable to the design and

  6. Stacked microbial desalination cells to enhance water desalination efficiency.

    PubMed

    Chen, Xi; Xia, Xue; Liang, Peng; Cao, Xiaoxin; Sun, Haotian; Huang, Xia

    2011-03-15

    Microbial desalination cell (MDC) is a new method to obtain clean water from brackish water using electricity generated from organic matters by exoelectrogenic bacteria. Anions and cations, derived from salt solution filled in the desalination chamber between the anode and cathode, move to the anode and cathode chambers under the force of electrical field, respectively. On the basis of the primitive single-desalination-chambered MDC, stacked microbial desalination cells (SMDCs) were developed in order to promote the desalination rate in the present study. The effects of desalination chamber number and external resistance were investigated. Results showed that a remarkable increase in the total desalination rate (TDR) could be obtained by means of increasing the desalination cell number and reducing the external resistance, which caused the charge transfer efficiency increased since the SMDCs enabled more pairs of ions separated while one electron passed through the external circuit. The maximum TDR of 0.0252 g/h was obtained using a two-desalination-chambered SMDC with an external resistance of 10 Ω, which was 1.4 times that of single-desalination-chambered MDC. SMDCs proved to be an effective approach to increase the total water desalination rate if provided a proper desalination chamber number and external resistance. PMID:21322552

  7. Improvements in plant performance [Sequoyah Nuclear Plant

    SciTech Connect

    Lorek, M.J.

    1999-11-01

    The improvements in plant reliability and performance at Sequoyah in the last two years can be directly attributed to ten key ingredients; teamwork, management stability, a management team that believes in teamwork, clear direction from the top, a strong focus on human performance, the company wide STAR 7 initiative, strong succession planning, a very seasoned and effective outage management organization, an infrastructure that ensures that the station is focused on the right hardware priorities, and a very strong line organization owned self-assessment program. Continued focus on these key ingredients and realization on a daily basis that good performance can lead to complacency will ensure that performance at Sequoyah will remain at a very high level well into the 21st century.

  8. Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04

    SciTech Connect

    2004-07-01

    Management; Ex-Vessel Debris Coolability and Steam Explosion: Theory and Modeling; Ex-Vessel Debris Coolability and Steam Explosion: Experiments and Supporting Analysis; PRA and Risk-informed Decision Making: Methodology; PRA and Risk-informed Decision Making: Advances in Practice; Use of CFD in Plant Safety Assessment and Related Regulatory Issues; Development and Application of Severe Accident Analysis Code); 6 - Thermal Hydraulic Analysis and Testing (Advances in Two-Phase Flow and Heat Transfer; Advances in CHF and Rod Bundle Thermal Hydraulics; CFD Applications to Water, Liquid Metal, and Gas Reactors; Separate Effects Thermal Hydraulic Experiments and Analysis; Integral Systems Thermal Hydraulic Experiments; Benchmark Analysis and Assessment; Natural Circulation Thermal Hydraulics; Thermal Striping and Thermal Stratification Studies); 7 - Core and Fuel Cycle Concepts and Experiments (Innovations in Core Designs; Advances in Core Design Methodology and Experimental Benchmarking; Advanced Fuel Cycles, Recycling, and Actinide Transmutation; Out of Core Fuel Cycle Issues); 8 - Material and Structural Issues (Structural and Materials Modeling and Analysis; Testing and Analysis of Structures and Materials; Advanced Issues in Welding and Materials; Fuel Design and Irradiation Issues for Next Generation Plants; Materials' Issues for Next Generation Plants); 9 - Nuclear Energy and Sustainability Including Hydrogen, Desalination, and Other Applications (Nuclear Energy Sustainability and Desalination; Nuclear Energy Application - Hydrogen); 10 - Space Power and Propulsion (Space Nuclear Power and Propulsion Systems; Nuclear Thermal Propulsion Concepts; Test and Design Methods; Instrumentation for Space Nuclear Reactors; Materials for Space Reactor Concepts)

  9. Energy Implications of Seawater Desalination (Invited)

    NASA Astrophysics Data System (ADS)

    Cooley, H.; Heberger, M. G.

    2013-12-01

    Freshwater has traditionally come from rivers, lakes, streams, and groundwater aquifers. As demand increases and climate change alters the location and timing of water supply, these traditional sources are becoming unavailable, more difficult, or increasingly expensive to develop. As a result, many communities are switching to alternative sources of water. Interest in pursuing seawater desalination is high in many coastal communities. In California, for example, 17 plants are proposed for development along the California coast and two in Mexico. Water managers are pursing desalination because is a local supply that can help diversify the water supply portfolio. Additionally, it is a reliable supply, which can be especially valuable during a drought. But removing the salt from seawater is an energy-intensive process that consumes more energy per gallon than most other water supply and treatment options. These energy requirements are key factors that will impact the extent and success of desalination in California. Energy requirements for seawater desalination average about 4.0 kWh per cubic meter (m3) of water produced. By comparison, the least energy-intensive options of local sources of groundwater and surface water require 0 - 0.90 kWh per m3; wastewater reuse, depending on treatment levels, may require from 0.26 - 2.2 kWh per m3. Beyond the electricity required for the desalination facility itself, producing any new source of water, including through desalination, increases the amount of energy required to deliver and use the water produced as well as collect, treat, and dispose of the wastewater generated. Energy is the largest single variable cost for a desalination plant, varying from one-third to more than one-half the cost of produced water. Building a desalination plant may reduce a water utility's exposure to water reliability risks at the added expense of an increase in exposure to energy price risk. In dependent on hydropower, electricity prices tend to

  10. 75 FR 66802 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-29

    ... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Regulatory Commission (the Commission) has granted the request of Calvert Cliffs Nuclear Power Plant, LLC... Operating License Nos. DPR-53 and DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and...

  11. Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06

    SciTech Connect

    2006-07-01

    reliability improvements, outage optimization, human factors, plant staffing, outage reduction features, major component reliability, repair and replacement, in-service inspection, and codes and standards. - 5. Plant Safety Assessment and Regulatory Issues Transient and accident performance including LOCA and non-LOCA, severe accident analysis, impact of risk informed changes, accident management, assessment and management of aging, degradation and damage, life extension lessons from plant operations, probabilistic safety assessment, plant safety analysis, reliability engineering, operating and future plants. - 6. Thermal Hydraulic Analysis and Testing Phenomena identification and ranking, computer code scaling applicability and uncertainty, containment thermal hydraulics, component and integral system tests, improved code development and qualification, single and two phase flow; advanced computational thermal hydraulic methods. - 7. Core and Fuel Cycle Concepts and Experiments Core physics, advances in computational reactor analysis, in-core fuel management, mixed-oxide fuel, thorium fuel cycle, low moderation cores, high conversion reactor designs, particle and pebble bed fuel design, testing and reliability; fuel cycle waste minimization, recycle, storage and disposal. - 8. Materials and Structural Issues Fuel, core, RPV and internals structures, advanced materials issues and fracture mechanics, concrete and steel containments, space structures, analysis, design and monitoring for seismic, dynamic and extreme accidents; irradiation issues and materials for new plants. - 9. Nuclear Energy and Sustainability including Hydrogen, Desalination and Other Applications Environmental impact of nuclear and alternative systems, spent fuel dispositions and transmutation systems, fully integrated fuel cycle and symbiotic nuclear power systems, application of advanced designs to non-power applications such as the production of hydrogen, sea water desalination, heating and other co

  12. Video camera use at nuclear power plants

    SciTech Connect

    Estabrook, M.L.; Langan, M.O.; Owen, D.E. )

    1990-08-01

    A survey of US nuclear power plants was conducted to evaluate video camera use in plant operations, and determine equipment used and the benefits realized. Basic closed circuit television camera (CCTV) systems are described and video camera operation principles are reviewed. Plant approaches for implementing video camera use are discussed, as are equipment selection issues such as setting task objectives, radiation effects on cameras, and the use of disposal cameras. Specific plant applications are presented and the video equipment used is described. The benefits of video camera use --- mainly reduced radiation exposure and increased productivity --- are discussed and quantified. 15 refs., 6 figs.

  13. Nuclear plant cancellations: causes, costs, and consequences

    SciTech Connect

    Not Available

    1983-04-01

    This study was commissioned in order to help quantify the effects of nuclear plant cancellations on the Nation's electricity prices. This report presents a historical overview of nuclear plant cancellations through 1982, the costs associated with those cancellations, and the reasons that the projects were terminated. A survey is presented of the precedents for regulatory treatment of the costs, the specific methods of cost recovery that were adopted, and the impacts of these decisions upon ratepayers, utility stockholders, and taxpayers. Finally, the report identifies a series of other nuclear plants that remain at risk of canellation in the future, principally as a result of similar demand, finance, or regulatory problems cited as causes of cancellation in the past. The costs associated with these potential cancellations are estimated, along with their regional distributions, and likely methods of cost recovery are suggested.

  14. Nuclear plant emergency preparedness in Russia.

    PubMed

    Sullivan, Randolph L

    2009-11-01

    An international team of experts conducted a detailed operational review at the Volgodonsk nuclear power plant. The review was the first mission by an International Atomic Energy Agency Operational Safety Review Team to Russia in over a decade. The author reviewed the emergency preparedness program in detail. Emergency preparedness professionals in the West are largely unfamiliar with Russian nuclear plant emergency preparedness programs, and the legacy of Chernobyl may leave some doubt as to their efficacy. This article describes the program in some detail and compares some elements to programs in the United States. The author was favorably impressed with the state of nuclear plant emergency preparedness in the Russian Federation and identified program elements that should be considered for implementation elsewhere. PMID:19820472

  15. 78 FR 55118 - Seismic Instrumentation for Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-09

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Seismic Instrumentation for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Standard review plan-draft section revision; request for comment. SUMMARY: The U.S. Nuclear...

  16. Optimization of nuclear plant preventive maintenance

    SciTech Connect

    McClymonds, S.L.; Winge, D.E.

    1987-01-01

    It is generally accepted that preventive maintenance can achieve greater equipment reliability. Most would also agree that the taking of precautions and checking reduces the need to perform corrective maintenance. In the nuclear industry, however, preventive maintenance has not been completely successful in sustaining equipment reliability levels. This paper presents methods for developing an optimum preventive maintenance program for nuclear power plants, one which will contribute to high plant availability by concentrating resources on those maintenance tasks that are directly applicable to equipment reliability.

  17. Virtual environments for nuclear power plant design

    SciTech Connect

    Brown-VanHoozer, S.A.; Singleterry, R.C. Jr.; King, R.W.

    1996-03-01

    In the design and operation of nuclear power plants, the visualization process inherent in virtual environments (VE) allows for abstract design concepts to be made concrete and simulated without using a physical mock-up. This helps reduce the time and effort required to design and understand the system, thus providing the design team with a less complicated arrangement. Also, the outcome of human interactions with the components and system can be minimized through various testing of scenarios in real-time without the threat of injury to the user or damage to the equipment. If implemented, this will lead to a minimal total design and construction effort for nuclear power plants (NPP).

  18. Active Faults and Nuclear Power Plants

    NASA Astrophysics Data System (ADS)

    Chapman, Neil; Berryman, Kelvin; Villamor, Pilar; Epstein, Woody; Cluff, Lloyd; Kawamura, Hideki

    2014-01-01

    The destruction of the Fukushima Daiichi Nuclear Power Plant (NPP) following the March 2011 Tohoku earthquake and tsunami brought into sharp focus the susceptibility of NPPs to natural hazards. This is not a new issue—seismic hazard has affected the development of plants in the United States, and volcanic hazard was among the reasons for not commissioning the Bataan NPP in the Philippines [Connor et al., 2009].

  19. Modeling Tritium Life cycle in Nuclear Plants

    SciTech Connect

    Hussey, D.; Saunders, P.; Morey, D.; Pitt, N.; Wilson, J.; Claes, B.

    2006-07-01

    The mathematical development of a tritium model for nuclear power plants is presented. The model requires that the water and tritium material balance be satisfied throughout normal operations and shutdown. The model results obtained at the time of publishing include the system definitions and comparison of the model predictions of tritium generations compared to the observed plant data of the Braidwood station. A scenario that models using ion exchange resin to remove coolant boron demonstrates the tritium concentration levels are manageable. (authors)

  20. Holdup measurement for nuclear fuel manufacturing plants

    SciTech Connect

    Zucker, M.S.; Degen, M.; Cohen, I.; Gody, A.; Summers, R.; Bisset, P.; Shaub, E.; Holody, D.

    1981-07-13

    The assay of nuclear material holdup in fuel manufacturing plants is a laborious but often necessary part of completing the material balance. A range of instruments, standards, and a methodology for assaying holdup has been developed. The objectives of holdup measurement are ascertaining the amount, distribution, and how firmly fixed the SNM is. The purposes are reconciliation of material unbalance during or after a manufacturing campaign or plant decommissioning, to decide security requirements, or whether further recovery efforts are justified.

  1. Reverse osmosis desalination: water sources, technology, and today's challenges.

    PubMed

    Greenlee, Lauren F; Lawler, Desmond F; Freeman, Benny D; Marrot, Benoit; Moulin, Philippe

    2009-05-01

    Reverse osmosis membrane technology has developed over the past 40 years to a 44% share in world desalting production capacity, and an 80% share in the total number of desalination plants installed worldwide. The use of membrane desalination has increased as materials have improved and costs have decreased. Today, reverse osmosis membranes are the leading technology for new desalination installations, and they are applied to a variety of salt water resources using tailored pretreatment and membrane system design. Two distinct branches of reverse osmosis desalination have emerged: seawater reverse osmosis and brackish water reverse osmosis. Differences between the two water sources, including foulants, salinity, waste brine (concentrate) disposal options, and plant location, have created significant differences in process development, implementation, and key technical problems. Pretreatment options are similar for both types of reverse osmosis and depend on the specific components of the water source. Both brackish water and seawater reverse osmosis (RO) will continue to be used worldwide; new technology in energy recovery and renewable energy, as well as innovative plant design, will allow greater use of desalination for inland and rural communities, while providing more affordable water for large coastal cities. A wide variety of research and general information on RO desalination is available; however, a direct comparison of seawater and brackish water RO systems is necessary to highlight similarities and differences in process development. This article brings to light key parameters of an RO process and process modifications due to feed water characteristics. PMID:19371922

  2. The Advanced BWR Nuclear Plant: Safe, economic nuclear energy

    SciTech Connect

    Redding, J.R.

    1994-12-31

    The safety and economics of Advanced BWR Nuclear Power Plants are outlined. The topics discussed include: ABWR Programs: status in US and Japan; ABWR competitiveness: safety and economics; SBWR status; combining ABWR and SBWR: the passive ABWR; and Korean/GE partnership.

  3. NUCLEAR POWER PLANT WASTE HEAT HORTICULTURE

    EPA Science Inventory

    The report gives results of a study of the feasibility of using low grade (70 degrees F) waste heat from the condenser cooling water of the Vermont Yaknee nuclear plant for commercial food enhancement. The study addressed the possible impact of laws on the use of waste heat from ...

  4. Modesty garment use at nuclear power plants

    SciTech Connect

    Owen, D.E. ); Johnstone, G. )

    1990-02-01

    This article presents the results of a telephone survey of modesty garment use at U.S. nuclear power plants. Modesty garments are launderable or disposable lightweight garments worn in radiological areas under cloth protective clothing (PCs). The types of modesty garments used, the benefits they provide, and other issues related to their used are discussed.

  5. Finding the flaws in nuclear power plants

    SciTech Connect

    Herbert, E.

    1982-09-01

    Describes how nondestructive, remote testing techniques are being devised to improve the operational safety of nuclear plants. Nondestructive evaluation (NDE) techniques developed by the EPRI include high-energy, portable X-ray systems; ultrasonic methods; advanced eddy-current inspection; and automated inspection. References for further information on NDE are given.

  6. 76 FR 4391 - Calvert Cliffs Nuclear Power Plant, LLC, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-25

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Calvert Cliffs Nuclear Power Plant, LLC, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2; Exemption 1.0 Background Calvert Cliffs Nuclear Power Plant, LLC, the licensee, is the holder of Facility Operating License Nos. DPR-53 and DPR-69...

  7. Impact of socio-economic growth on desalination in the US.

    PubMed

    Ziolkowska, Jadwiga R; Reyes, Reuben

    2016-02-01

    In 2013, around 1336 desalination plants in the United States (US) provided purified water mainly to municipalities, the industry sector and for power generation. In 2013 alone, ∼200 million m(3) of water were desalinated; the amount that could satisfy annual municipal water consumption of more than 1.5 million people in the US. Desalination has proven to be a reliable water supply source in many countries around the world, with the total global desalination capacity of ∼60 million m(3)/day in 2013. Desalination has been used to mitigate water scarcity and lessen the pressure on water resources. Currently, data and information about desalination are still limited, while extensive socio-economic analyses are missing. This paper presents an econometric model to fill this gap. It evaluates the impact of selected socio-economic variables on desalination development in the US in the time span 1970-2013. The results show that the GDP and population growth have significantly impacted the desalination sector over the analyzed time period. The insights into the economics of desalination provided with this paper can be used to further evaluate cost-effectiveness of desalination both in the US and in other countries around the world. PMID:26610194

  8. FIREDATA. Nuclear Power Plant Fire Database

    SciTech Connect

    Wheelis, W.T.

    1986-08-01

    FIREDATA contains raw fire event data from 1965 through June 1985. These data were obtained from a number of reference sources including the American Nuclear Insurers, Licensee Event Reports, Nuclear Power Experience, Electric Power Research Institute Fire Loss Data and then collated into one database developed in the personal computer database management system, dBASE III. FIREDATA is menu-driven and asks interactive questions of the user that allow searching of the database for various aspects of a fire such as: location, mode of plant operation at the time of the fire, means of detection and suppression, dollar loss, etc. Other features include the capability of searching for single or multiple criteria (using Boolean `and` or `or` logical operations), user-defined keyword searches of fire event descriptions, summary displays of fire event data by plant name or calendar date, and options for calculating the years of operating experience for all commercial nuclear power plants from any user-specified date and the ability to display general plant information.

  9. Advanced nuclear plant control room complex

    DOEpatents

    Scarola, Kenneth; Jamison, David S.; Manazir, Richard M.; Rescorl, Robert L.; Harmon, Daryl L.

    1993-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

  10. Global nuclear radiation monitoring using plants

    NASA Astrophysics Data System (ADS)

    Islam, Mohammad; Romero-Talamas, Carlos; Kostov, Dan; Wang, Wanpeng; Liu, Zhongchi; Hussey, Daniel S.; Baltic, Eli; Jacobson, David L.; Gu, Jerry; Choa, Fow-Sen

    2005-05-01

    Plants exhibit complex responses to changes in environmental conditions such as radiant heat flux, water quality, airborne pollutants, soil contents. We seek to utilize the natural chemical and electrophysiological response of plants to develop novel plant-based sensor networks. Our present work focuses on plant responses to high-energy radiation - with the goal of monitoring natural plant responses for use as benchmarks for detection and dosimetry. For our study, we selected a plants cactus, Arabidopsis, Dwarf mango (pine), Euymus and Azela. We demonstrated that the ratio of Chlorophyll a to Chlorophyll b of the leaves has changed due to the exposure gradually come back to the normal stage after the radiation die. We used blue laser-induced blue fluorescence-emission spectra to characterize the pigment status of the trees. Upon blue laser excitation (400 nm) leaves show a fluorescence emission in the red spectral region between 650 and 800nm (chlorophyll fluorescence with maxima near 690nm and 735 nm). Sample tree subjects were placed at a distance of 1m from NIST-certified 241AmBe neutron source (30 mCi), capable of producing a neutron field of about 13 mrem/h. This corresponds to an actual absorbed dose of ~ 1 mrad/h. Our results shows that all plants are sensitive to nuclear radiation and some take longer time to recover and take less. We can use their characteristics to do differential detection and extract nuclear activity information out of measurement results avoid false alarms produced environmental changes. Certainly the ultimate verification can be obtained from genetic information, which only need to be done when we have seen noticeable changes on plant optical spectra, mechanical strength and electrical characteristics.

  11. Safety in nuclear power plants in India

    PubMed Central

    Deolalikar, R.

    2008-01-01

    Safety in nuclear power plants (NPPs) in India is a very important topic and it is necessary to dissipate correct information to all the readers and the public at large. In this article, I have briefly described how the safety in our NPPs is maintained. Safety is accorded overriding priority in all the activities. NPPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, dosimetry, approved standard operating and maintenance procedures, a well-defined waste management methodology, proper well documented and periodically rehearsed emergency preparedness and disaster management plans. The NPPs have occupational health policies covering periodic medical examinations, dosimetry and bioassay and are backed-up by fully equipped Personnel Decontamination Centers manned by doctors qualified in Occupational and Industrial Health. All the operating plants are ISO 14001 and IS 18001 certified plants. The Nuclear Power Corporation of India Limited today has 17 operating plants and five plants under construction, and our scientists and engineers are fully geared to take up many more in order to meet the national requirements. PMID:20040970

  12. Safety in nuclear power plants in India.

    PubMed

    Deolalikar, R

    2008-12-01

    Safety in nuclear power plants (NPPs) in India is a very important topic and it is necessary to dissipate correct information to all the readers and the public at large. In this article, I have briefly described how the safety in our NPPs is maintained. Safety is accorded overriding priority in all the activities. NPPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, dosimetry, approved standard operating and maintenance procedures, a well-defined waste management methodology, proper well documented and periodically rehearsed emergency preparedness and disaster management plans. The NPPs have occupational health policies covering periodic medical examinations, dosimetry and bioassay and are backed-up by fully equipped Personnel Decontamination Centers manned by doctors qualified in Occupational and Industrial Health. All the operating plants are ISO 14001 and IS 18001 certified plants. The Nuclear Power Corporation of India Limited today has 17 operating plants and five plants under construction, and our scientists and engineers are fully geared to take up many more in order to meet the national requirements. PMID:20040970

  13. Autonomous Control of Nuclear Power Plants

    SciTech Connect

    Basher, H.

    2003-10-20

    A nuclear reactor is a complex system that requires highly sophisticated controllers to ensure that desired performance and safety can be achieved and maintained during its operations. Higher-demanding operational requirements such as reliability, lower environmental impacts, and improved performance under adverse conditions in nuclear power plants, coupled with the complexity and uncertainty of the models, necessitate the use of an increased level of autonomy in the control methods. In the opinion of many researchers, the tasks involved during nuclear reactor design and operation (e.g., design optimization, transient diagnosis, and core reload optimization) involve important human cognition and decisions that may be more easily achieved with intelligent methods such as expert systems, fuzzy logic, neural networks, and genetic algorithms. Many experts in the field of control systems share the idea that a higher degree of autonomy in control of complex systems such as nuclear plants is more easily achievable through the integration of conventional control systems and the intelligent components. Researchers have investigated the feasibility of the integration of fuzzy logic, neural networks, genetic algorithms, and expert systems with the conventional control methods to achieve higher degrees of autonomy in different aspects of reactor operations such as reactor startup, shutdown in emergency situations, fault detection and diagnosis, nuclear reactor alarm processing and diagnosis, and reactor load-following operations, to name a few. With the advancement of new technologies and computing power, it is feasible to automate most of the nuclear reactor control and operation, which will result in increased safety and economical benefits. This study surveys current status, practices, and recent advances made towards developing autonomous control systems for nuclear reactors.

  14. Wave energy desalinization

    SciTech Connect

    Hopfe, H.H.

    1982-06-22

    A device for producing fresh water from salt sea water by utilizing the hydrodynamic energy of waves, comprising a buoyant platform; means for mooring the platform; a pump connected to the mooring means; a reservoir for pressurized sea water; a desalination system for extracting fresh water from the sea water; hydraulic flow control means for causing the pump to pump sea water into the sea water reservoir, as motion of the buoyant platform is produced due to the passing of waves beneath it; measuring means for measuring parameters of the sea adjacent the buoyant platform; and a control device connected to control the pressure in the sea water reservoir and the flow of sea water from the reservoir through the desalination system in response to the parameters of the sea.

  15. Water Desalination with Wires.

    PubMed

    Porada, S; Sales, B B; Hamelers, H V M; Biesheuvel, P M

    2012-06-21

    We show the significant potential of water desalination using a novel capacitive wire-based technology in which anode/cathode wire pairs are constructed from coating a thin porous carbon electrode layer on top of electrically conducting rods (or wires). By alternately dipping an array of electrode pairs in freshwater with and in brine without an applied cell voltage, we create an ion adsorption/desorption cycle. We show experimentally how in six subsequent cycles we can reduce the salinity of 20 mM feed (brackish) water by a factor of 3, while application of a cation exchange membrane on the cathode wires makes the desalination factor increase to 4. Theoretical modeling rationalizes the experimental findings, and predicts that system performance can be significantly enhanced by material modifications. To treat large volumes of water, multiple stacks of wire pairs can be used simultaneously in a "merry-go-round" operational mode. PMID:26285717

  16. Taxonomy of the nuclear plant operator's role

    SciTech Connect

    Kisner, R.A.; Fullerton, A.M.; Frey, P.R.; Dougherty, E.M.

    1981-01-01

    A program is presently under way at the Oak Ridge National Laboratory (ORNL) to define the functional design requirements of operational aids for nuclear power plant operators. A first and important step in defining these requirements is to develop an understanding of the operator's role or function. This paper describes a taxonomy of operator functions that applies during all operational modes and conditions of the plant. Other topics such as the influence of automation, role acceptance, and the operator's role during emergencies are also discussed. This systematic approach has revealed several areas which have potential for improving the operator's ability to perform his role.

  17. 75 FR 13323 - James A. Fitzpatrick Nuclear Power Plant; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-19

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION James A. Fitzpatrick Nuclear Power Plant; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (the licensee) is the holder of Facility Operating License No. DPR-59, which authorizes operation of the James A. FitzPatrick Nuclear Power Plant...

  18. Polyphophoinositides components of plant nuclear membranes

    SciTech Connect

    Hendrix, K.W.; Boss, W.F.

    1987-04-01

    The polyphosphoinositides, phosphatidylinositol monophosphate (PIP) and phosphatidylinositol bisphosphate (PIP/sub 2/), have been shown to be important components in signal transduction in many animal cells. Recently, these lipids have been found to be associated with plasma membrane but not microsomal membrane isolated from fusogenic wild carrot cells; however, in that study the lipids of the nuclear membrane were not analyzed. Since polyphosphoinositides had been shown to be associated with the nuclear membranes as well as the plasma membrane in some animal cells, it was important to determine whether they were associated with plant nuclear membranes as well. Cells were labeled for 18h with (/sup 3/H) inositol and the nuclei were isolated by a modification of the procedure of Saxena et al. Preliminary lipid analyses indicate lower amount of PIP and PIP/sub 2/ in nuclear membranes compared to whole protoplasts. This suggests that the nuclear membranes of carrot cells are not enriched in PIP and PIP/sub 2/; however, the Triton X-100 used during the nuclear isolation procedure may have affected the recovery of the lipids. Experiments are in progress to determine the effects of Triton X-100 on lipid extraction.

  19. Improved Economics of Nuclear Plant Life Management

    SciTech Connect

    Bond, Leonard J.; Doctor, Steven R.; Jarrell, Donald B.; Bond, Joseph W D.

    2007-07-31

    The adoption of new on-line monitoring, diagnostic and eventually prognostics technologies has the potential to impact the economics of the existing nuclear power plant fleet, new plants and future advanced designs. To move from periodic inspection to on-line monitoring for condition based maintenance and eventually prognostics will require advances in sensors, better understanding of what and how to measure within the plant; enhanced data interrogation, communication and integration; new predictive models for damage/aging evolution; system integration for real world deployments; quantification of uncertainties in what are inherently ill-posed problems and integration of enhanced condition based maintenance/prognostics philosophies into new plant designs, operation and O&M approaches. The move to digital systems in petrochemical, process and fossil fuel power plants is enabling major advances to occur in the instrumentation, controls and monitoring systems and approaches employed. The adoption within the nuclear power community of advanced on-line monitoring and advanced diagnostics has the potential for the reduction in costly periodic surveillance that requires plant shut-down , more accurate cost-benefit analysis, “just-in-time” maintenance, pre-staging of maintenance tasks, move towards true “operation without failures” and a jump start on advanced technologies for new plant concepts, such as those under the International Gen IV Program. There are significant opportunities to adopt condition-based maintenance when upgrades are implemented at existing facilities. The economic benefit from a predictive maintenance program based upon advanced on-line monitoring and advanced diagnostics can be demonstrated from a cost/benefit analysis. An analysis of the 104 US legacy systems has indicated potential savings at over $1B per year when applied to all key equipment; a summary of the supporting analysis is provided in this paper.

  20. Balance of Plant Requirements for a Nuclear Hydrogen Plant

    SciTech Connect

    Bradley Ward

    2006-04-01

    This document describes the requirements for the components and systems that support the hydrogen production portion of a 600 megawatt thermal (MWt) Next Generation Nuclear Plant (NGNP). These systems, defined as the "balance-of-plant" (BOP), are essential to operate an effective hydrogen production plant. Examples of BOP items are: heat recovery and heat rejection equipment, process material transport systems (pumps, valves, piping, etc.), control systems, safety systems, waste collection and disposal systems, maintenance and repair equipment, heating, ventilation, and air conditioning (HVAC), electrical supply and distribution, and others. The requirements in this document are applicable to the two hydrogen production processes currently under consideration in the DOE Nuclear Hydrogen Initiative. These processes are the sulfur iodide (S-I) process and the high temperature electrolysis (HTE) process. At present, the other two hydrogen production process - the hybrid sulfur-iodide electrolytic process (SE) and the calcium-bromide process (Ca-Br) -are under flow sheet development and not included in this report. While some features of the balance-of-plant requirements are common to all hydrogen production processes, some details will apply only to the specific needs of individual processes.

  1. 75 FR 16869 - Entergy Nuclear Operations, LLC; Palisades Nuclear Plant; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-02

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Entergy Nuclear Operations, LLC; Palisades Nuclear Plant; Exemption 1.0 Background Entergy Nuclear... operation of Palisades Nuclear Plant (PNP). The license provides, among other things, that the facility...

  2. 77 FR 47121 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Units 1 and 2...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-07

    ... Consideration (73 FR 17148; March 31, 2008), states that ``Plant emergencies are extraordinary circumstances... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Units 1 and...

  3. 76 FR 39908 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-07

    ... participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August... COMMISSION Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2.... DPR-53 and DPR-69, for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (CCNPP),...

  4. Fatigue monitoring in Nuclear Power Plants

    SciTech Connect

    Ware, A.G.; Shah, V.N.

    1995-04-01

    This paper summarizes fatigue monitoring methods and surveys their application in the nuclear power industry. The paper is based on a review of the technical literature. Two main reasons for fatigue monitoring are more frequent occurrence of some transients than that assumed in the fatigue design analysis and the discovery of stressors that were not included in the fatigue design analysis but may cause significant fatigue damage at some locations. One fatigue monitoring method involves use of plant operating data and procedures to update the fatigue usage. Another method involves monitoring of plant operating parameters using existing, or if needed, supplementary plant instrumentation for online computation of fatigue usage. Use of fatigue monitoring has better defined the operational transients. Most operational transients have been found less severe and fewer in numbers than anticipated in the design fatigue analysis. Use of fatigue monitoring has assisted in quantifying newly discovered stressors and has helped in detecting the presence of thermal stratification of unsuspected locations.

  5. MARS, 600 MWth NUCLEAR POWER PLANT

    SciTech Connect

    Cumo, M.; Naviglio, A.; Sorabella, L.

    2004-10-06

    MARS (Multipurpose Advanced Reactor, inherently Safe) is a 600 MWth, single loop, pressurized light water reactor (PWR), developed at the Dept. of Nuclear Engineering and Energy Conversion of the University of Rome ''La Sapienza''. The design was focused to a multipurpose reactor to be used in high population density areas also for industrial heat production and, in particular, for water desalting. Using the well-proven technology and the operation experience of PWRs, the project introduces a lot of innovative features hugely improving the safety performance while keeping the cost of KWh competitive with traditional large power plants. Extensive use of passive safety, in depth plant simplification and decommissioning oriented design were the guidelines along the design development. The latest development in the plant design, in the decommissioning aspects and in the experimental activities supporting the project are shown in this paper.

  6. THE NEXT GENERATION NUCLEAR PLANT GRAPHITE PROGRAM

    SciTech Connect

    William E. Windes; Timothy D. Burchell; Robert L. Bratton

    2008-09-01

    Developing new nuclear grades of graphite used in the core of a High Temperature Gas-cooled Reactor (HTGR) is one of the critical development activities being pursued within the Next Generation Nuclear Plant (NGNP) program. Graphite’s thermal stability (in an inert gas environment), high compressive strength, fabricability, and cost effective price make it an ideal core structural material for the HTGR reactor design. While the general characteristics necessary for producing nuclear grade graphite are understood, historical “nuclear” grades no longer exist. New grades must be fabricated, characterized, and irradiated to demonstrate that current grades of graphite exhibit acceptable non-irradiated and irradiated properties upon which the thermo-mechanical design of the structural graphite in NGNP is based. The NGNP graphite R&D program has selected a handful of commercially available types for research and development activities necessary to qualify this nuclear grade graphite for use within the NGNP reactor. These activities fall within five primary areas; 1) material property characterization, 2) irradiated material property characterization, 3) modeling, and 4) ASTM test development, and 5) ASME code development efforts. Individual research and development activities within each area are being pursued with the ultimate goal of obtaining a commercial operating license for the nuclear graphite from the US NRC.

  7. The look of into Desalination and Natural Hazard

    NASA Astrophysics Data System (ADS)

    Arregoitia Sarabia, C. A.

    2012-04-01

    Today due to climate change and population growth, cities and especially larger cities have become more water stressed. Thus the growing demand for drinkable water due to water scarcity in different World regions and its reliable supply, have persuaded humans to construct desalination plants. Today, the implementation of different large-scale desalination methods is increasing. Desalination is a separation process that consists on the removal of salts from water (seawater or brackish water) to make it suitable for other purposes. Some important environmental aspects for a desalination plant are the location of the plant, brine disposal and energy considerations. However these issues become affected when natural adversity happens. Desalination processes used are normally classified in thermal and membrane. The energy required by these processes could be of any form of heat, electrical or mechanical depending on the separation process. These types of energy derive from fossil fuels, which conditions the desalination sustainability -environmental and economical. To improve this reality, the desalination industry is making a great research effort related to novel technologies, the use of renewable energies, and brine management. Presently desalination membrane technologies are preferred over thermal ones (based on evaporation) since they allow for continuous operations close to ambient temperatures. Moreover, the offer for a wider selection of large equipment and modules is increasing. This makes it possible to design processes according to potable needs as well as ease the use of membranes and other separation technologies together. Traditionally the location of the plant is an obvious matter where selection of site should be determined by considerations of mainly energy supply available and distance in relation to feed water intake, disposal site and end-user. This means locating these plants in coastal areas or inland locations and look for a solution to then

  8. ORFIG-MSF. Desalination Flash Evaporator

    SciTech Connect

    Browell, R.W.; Burris, J.H.; Friedrich, R.O.; Parsley, I.R.

    1989-07-01

    ORFIG-MSF was developed to determine the flexibility of a fixed-geometry water desalination plant to operate under off-design point conditions. The program accepts the variation of all major parameters and the specification of a number of logically possible dependent-independent parameter combinations. Input is in the form of punched cards and includes plant geometry specifications, operating and fixed cost data, parameter control information and operating variables. Output is printed hard copy from the standard output channel and includes detailed stage-by-stage flow and thermodynamic operating characteristics, costs and differential costs referred to the first case processed.

  9. Nuclear power plants in China's coastal zone: risk and safety

    NASA Astrophysics Data System (ADS)

    Lu, Qingshui; Gao, Zhiqiang; Ning, Jicai; Bi, Xiaoli; Gao, Wei

    2014-10-01

    Nuclear power plants are used as an option to meet the demands for electricity due to the low emission of CO2 and other contaminants. The accident at the Fukushima nuclear power plant in 2011 has forced the Chinese government to adjust its original plans for nuclear power. The construction of inland nuclear power plants was stopped, and construction is currently only permitted in coastal zones. However, one obstacle of those plants is that the elevation of those plants is notably low, ranging from 2 to 9 meters and a number of the nuclear power plants are located in or near geological fault zones. In addition, the population density is very high in the coastal zones of China. To reduce those risks of nuclear power plants, central government should close the nuclear power plants within the fault zones, evaluate the combined effects of storm surges, inland floods and tidal waves on nuclear power plants and build closed dams around nuclear power plants to prevent damage from storm surges and tidal waves. The areas without fault zones and with low elevation should be considered to be possible sites for future nuclear power plants if the elevation can be increased using soil or civil materials.

  10. Analysis of nuclear power plant construction costs

    SciTech Connect

    Not Available

    1986-01-01

    The objective of this report is to present the results of a statistical analysis of nuclear power plant construction costs and lead-times (where lead-time is defined as the duration of the construction period), using a sample of units that entered construction during the 1966-1977 period. For more than a decade, analysts have been attempting to understand the reasons for the divergence between predicted and actual construction costs and lead-times. More importantly, it is rapidly being recognized that the future of the nuclear power industry rests precariously on an improvement in the cost and lead-time situation. Thus, it is important to study the historical information on completed plants, not only to understand what has occurred to also to improve the ability to evaluate the economics of future plants. This requires an examination of the factors that have affected both the realized costs and lead-times and the expectations about these factors that have been formed during the construction process. 5 figs., 22 tabs.

  11. Thermal and economic analysis of a solar multi-effect desalination system

    SciTech Connect

    Hamed, O.A.

    1996-10-01

    The performance of a solar multieffect desalination pilot plant has been studied over an extended period of one year. The impact of solar flux, ambient and sea water temperatures on the monthly average water production and plant performance ratios are investigated. The specific thermal and electric energy requirements of the system have been examined and compared with the requirements of conventional fossil fuel powered desalination plants. The economic viability of the solar desalination system has been assessed. It reveals that the capital and operating costs represent around 93 and 7 percent of the overall water production cost respectively. The capital cost critically depends on solar radiation and distiller performance ratio.

  12. Analysis of failed nuclear plant components

    NASA Astrophysics Data System (ADS)

    Diercks, D. R.

    1993-12-01

    Argonne National Laboratory has conducted analyses of failed components from nuclear power- gener-ating stations since 1974. The considerations involved in working with and analyzing radioactive compo-nents are reviewed here, and the decontamination of these components is discussed. Analyses of four failed components from nuclear plants are then described to illustrate the kinds of failures seen in serv-ice. The failures discussed are (1) intergranular stress- corrosion cracking of core spray injection piping in a boiling water reactor, (2) failure of canopy seal welds in adapter tube assemblies in the control rod drive head of a pressurized water reactor, (3) thermal fatigue of a recirculation pump shaft in a boiling water reactor, and (4) failure of pump seal wear rings by nickel leaching in a boiling water reactor.

  13. Cesium Removal at Fukushima Nuclear Plant - 13215

    SciTech Connect

    Braun, James L.; Barker, Tracy A.

    2013-07-01

    The Great East Japan Earthquake that took place on March 11, 2011 created a number of technical challenges at the Fukushima Daiichi Nuclear Plant. One of the primary challenges involved the treatment of highly contaminated radioactive wastewater. Avantech Inc. developed a unique patent pending treatment system that addressed the numerous technical issues in an efficient and safe manner. Our paper will address the development of the process from concept through detailed design, identify the lessons learned, and provide the updated results of the project. Specific design and operational parameters/benefits discussed in the paper include: - Selection of equipment to address radionuclide issues; - Unique method of solving the additional technical issues associated with Hydrogen Generation and Residual Heat; - Operational results, including chemistry, offsite discharges and waste generation. Results show that the customized process has enabled the utility to recycle the wastewater for cooling and reuse. This technology had a direct benefit to nuclear facilities worldwide. (authors)

  14. Direct seawater desalination by ion concentration polarization

    NASA Astrophysics Data System (ADS)

    Kim, Sung Jae; Ko, Sung Hee; Kang, Kwan Hyoung; Han, Jongyoon

    2010-04-01

    A shortage of fresh water is one of the acute challenges facing the world today. An energy-efficient approach to converting sea water into fresh water could be of substantial benefit, but current desalination methods require high power consumption and operating costs or large-scale infrastructures, which make them difficult to implement in resource-limited settings or in disaster scenarios. Here, we report a process for converting sea water (salinity ~500 mM or ~30,000 mg l-1) to fresh water (salinity <10 mM or <600 mg l-1) in which a continuous stream of sea water is divided into desalted and concentrated streams by ion concentration polarization, a phenomenon that occurs when an ion current is passed through ion-selective membranes. During operation, both salts and larger particles (cells, viruses and microorganisms) are pushed away from the membrane (a nanochannel or nanoporous membrane), which significantly reduces the possibility of membrane fouling and salt accumulation, thus avoiding two problems that plague other membrane filtration methods. To implement this approach, a simple microfluidic device was fabricated and shown to be capable of continuous desalination of sea water (~99% salt rejection at 50% recovery rate) at a power consumption of less than 3.5 Wh l-1, which is comparable to current state-of-the-art systems. Rather than competing with larger desalination plants, the method could be used to make small- or medium-scale systems, with the possibility of battery-powered operation.

  15. Nuclear power-plant safety functions

    SciTech Connect

    Corcoran, W.R.; Finnicum, D.J.; Hubbard, F.R. III; Musick, C.R.; Walzer, P.F.

    1981-03-01

    The concept of safety functions is discussed. Ten critical safety functions and the multiple success paths available for accomplishing them are described. Use of the safety function concept in the development of emergency procedures, operator training, and control-room displays provides a systematic approach and a hierarchy of protection that an operator can use to mitigate the consequences of an event. The safety function concept can also be applied to the design and analysis of nuclear plant systems and to the evaluation of past expierience.

  16. Affective imagery and acceptance of replacing nuclear power plants.

    PubMed

    Keller, Carmen; Visschers, Vivianne; Siegrist, Michael

    2012-03-01

    This study examined the relationship between the content of spontaneous associations with nuclear power plants and the acceptance of using new-generation nuclear power plants to replace old ones. The study also considered gender as a variable. A representative sample of the German- and French-speaking population of Switzerland (N= 1,221) was used. Log-linear models revealed significant two-way interactions between the association content and acceptance, association content and gender, and gender and acceptance. Correspondence analysis revealed that participants who were opposed to nuclear power plants mainly associated nuclear power plants with risk, negative feelings, accidents, radioactivity, waste disposal, military use, and negative consequences for health and environment; whereas participants favoring nuclear power plants mainly associated them with energy, appearance descriptions of nuclear power plants, and necessity. Thus, individuals opposing nuclear power plants had both more concrete and more diverse associations with them than people who were in favor of nuclear power plants. In addition, participants who were undecided often mentioned similar associations to those participants who were in favor. Males more often expressed associations with energy, waste disposal, and negative health effects. Females more often made associations with appearance descriptions, negative feelings, and negative environmental effects. The results further suggest that acceptance of replacing nuclear power plants was higher in the German-speaking part of the country, where all of the Swiss nuclear power plants are physically located. Practical implications for risk communication are discussed. PMID:21977961

  17. BN-800 advanced nuclear power plant with fast reactor

    SciTech Connect

    Shishkin, A.N.; Kuzavkov, N.G.; Sobolev, V.A.; Shestakov, G.V.; Bagdasarov, Yu.E.; Kochetkov, L.A.; Matveyev, V.I.; Poplavsky, V.M.

    1993-12-31

    Bn-800 reactor plant with fast reactor and sodium coolant in the primary and secondary circuits is designed for operation as part of the power units in the Yuzhno-Uralskaya nuclear power plant scheduled to be constructed in Chelyabinsk region and as part unit 4 in the Beloyarskaya nuclear power plant. Reactor operations are described.

  18. Condenser performance recovery in nuclear power plants

    SciTech Connect

    Saxon, G. Jr.; Putman, R.E.

    1996-12-31

    Fouling of the tubes in the main condenser can have a significant impact on nuclear plant performance. Recent experiences suggest that the effects of fouling have been underestimated and that the results of an effective tube cleaning can be measured in improved unit capacity. In particular two nuclear power plants have reported recovery of 20 and 25 MW respectively. While the types of deposition often vary as they did in these two cases, the deposit elements were accurately identified, the deposits` impact on heat transfer was evaluated and an effective cleaning methodology was developed for successful deposit removal. These experiences have prompted the development of a number of diagnostic monitoring and inspection methods which can be utilized in the field or in the laboratory; to detect, identify and quantify the presence of fouling and its impact on heat transfer, to determine the relative effectiveness of a cleaning method and to evaluate condenser performance as related to MW capacity for both single and multiple compartment condensers.

  19. Electromagnetic Compatibility in Nuclear Power Plants

    SciTech Connect

    Ewing, P.D.; Kercel, S.W.; Korsah, K.; Wood, R.T.

    1999-08-29

    Electromagnetic compatibility (EMC) has long been a key element of qualification for mission critical instrumentation and control (I&C) systems used by the U.S. military. The potential for disruption of safety-related I&C systems by electromagnetic interference (EMI), radio-frequency interference (RFI), or power surges is also an issue of concern for the nuclear industry. Experimental investigations of the potential vulnerability of advanced safety systems to EMI/RFI, coupled with studies of reported events at nuclear power plants (NPPs) that are attributed to EMI/RFI, confirm the safety significance of EMC for both analog and digital technology. As a result, Oak Ridge National Laboratory has been engaged in the development of the technical basis for guidance that addresses EMC for safety-related I&C systems in NPPs. This research has involved the identification of engineering practices to minimize the potential impact of EMI/RFI and power surges and an evaluation of the ambient electromagnetic environment at NPPs to tailor those practices for use by the nuclear industry. Recommendations for EMC guidance have been derived from these research findings and are summarized in this paper.

  20. A new method for water desalination using microbial desalination cells.

    PubMed

    Cao, Xiaoxin; Huang, Xia; Liang, Peng; Xiao, Kang; Zhou, Yingjun; Zhang, Xiaoyuan; Logan, Bruce E

    2009-09-15

    Current water desalination techniques are energy intensive and some use membranes operated at high pressures. It is shown here that water desalination can be accomplished without electrical energy input or high water pressure by using a source of organic matter as the fuel to desalinate water. A microbial fuel cell was modified by placing two membranes between the anode and cathode, creating a middle chamber for water desalination between the membranes. An anion exchange membrane was placed adjacent to the anode, and a cation exchange membrane was positioned next to the cathode. When current was produced by bacteria on the anode, ionic species in the middle chamber were transferred into the two electrode chambers, desalinating the water in the middle chamber. Proof-of-concept experiments for this approach, using what we call a microbial desalination cell (MDC), was demonstrated using water at different initial salt concentrations (5, 20, and 35 g/L) with acetate used as the substrate for the bacteria. The MDC produced a maximum of 2 W/m2 (31 W/m3) while at the same time removing about 90% of the salt in a single desalination cycle. As the salt was removed from the middle chamber the ohmic resistance of the MDC (measured using electrochemical impedance spectroscopy) increased from 25 Omega to 970 Omega at the end of the cycle. This increased resistance was reflected by a continuous decrease in the voltage produced over the cycle. These results demonstrate for the first time the possibility for a new method for water desalination and power production that uses only a source of biodegradable organic matter and bacteria. PMID:19806756

  1. Projected world market for seawater desalination equipment

    SciTech Connect

    Not Available

    1984-10-01

    A forecast is presented of the market for seawater desalination plants. The conclusions presented herein are based on a number of sources of information, of which the most important are: responses to questionnaires mailed to 300 cognizant water agencies in 61 countries; the published market growth trend over the period 1971 to 1983; and an analysis of the geography, rainfall, population, industrial growth, and energy availability in the respective countries. Analysis suggests the possibility that financing, although currently a major stumbling block to the purchase of desalting plants, may be effected by an exchange program in which the purchaser of plants will offer some exportable product(s) in exchange. The forecast suggests the likelihood that the seawater desalination market is becoming saturated. A plateau is expected to develop in new plant sales of additional capacity in the immediate future, followed by a downturn by the end of the century. This report, however, emphasizes the importance of the replacement market, which will involve substantial sales to replace worn-out and obsolescent equipment. The combined new-plus-replacement annual sales can be expected to reach 1.25 million m/sup 3//d (330 Mgd) by the year 2000. Seawater reverse osmosis (SWRO) is expected to represent 270,000 m/sup 3//d (70 Mgd) by the end of the century because of technological improvements in membrane systems and components.

  2. Nanostructured materials for water desalination.

    PubMed

    Humplik, T; Lee, J; O'Hern, S C; Fellman, B A; Baig, M A; Hassan, S F; Atieh, M A; Rahman, F; Laoui, T; Karnik, R; Wang, E N

    2011-07-22

    Desalination of seawater and brackish water is becoming an increasingly important means to address the scarcity of fresh water resources in the world. Decreasing the energy requirements and infrastructure costs of existing desalination technologies remains a challenge. By enabling the manipulation of matter and control of transport at nanometer length scales, the emergence of nanotechnology offers new opportunities to advance water desalination technologies. This review focuses on nanostructured materials that are directly involved in the separation of water from salt as opposed to mitigating issues such as fouling. We discuss separation mechanisms and novel transport phenomena in materials including zeolites, carbon nanotubes, and graphene with potential applications to reverse osmosis, capacitive deionization, and multi-stage flash, among others. Such nanostructured materials can potentially enable the development of next-generation desalination systems with increased efficiency and capacity. PMID:21680966

  3. Precipitation softening: a pretreatment process for seawater desalination.

    PubMed

    Ayoub, George M; Zayyat, Ramez M; Al-Hindi, Mahmoud

    2014-02-01

    Reduction of membrane fouling in reverse osmosis systems and elimination of scaling of heat transfer surfaces in thermal plants are a major challenge in the desalination of seawater. Precipitation softening has the potential of eliminating the major fouling and scaling species in seawater desalination plants, thus allowing thermal plants to operate at higher top brine temperatures and membrane plants to operate at a reduced risk of fouling, leading to lower desalinated water costs. This work evaluated the use of precipitation softening as a pretreatment step for seawater desalination. The effectiveness of the process in removing several scale-inducing materials such as calcium, magnesium, silica, and boron was investigated under variable conditions of temperature and pH. The treatment process was also applied to seawater spiked with other known fouling species such as iron and bacteria to determine the efficiency of removal. The results of this work show that precipitation softening at a pH of 11 leads to complete elimination of calcium, silica, and bacteria; to very high removal efficiencies of magnesium and iron (99.6 and 99.2 %, respectively); and to a reasonably good removal efficiency of boron (61 %). PMID:24151028

  4. Storage of mixed waste at nuclear plants

    SciTech Connect

    Bodine, D.

    1995-05-01

    The problems posed by waste that is both radioactive and classified as hazardous by 40CFR261 include storage, proper treatment and disposal. An Enforcement Action issued by the State of Tennessee required that Sequoyah Nuclear Plant (SQN) either find a means to remove its mixed waste from onsite storage or obtain Part B Hazardous Waste Treatment, Storage and Disposal Facility by March 1, 1994. Generators of hazardous waste cannot store the material for longer than 90 days without obtaining a Hazardous Waste Treatment, Storage, and Disposal Facility (TSDF) permit. To complicate this regulation, there are very few permitted TSDFs that can receive radioactive waste. Those facilities that can receive the waste have only one year to store it before treatment. Limited treatment is available for mixed waste that will meet the Land Ban requirements.

  5. Seismic analysis of nuclear power plant structures

    NASA Technical Reports Server (NTRS)

    Go, J. C.

    1973-01-01

    Primary structures for nuclear power plants are designed to resist expected earthquakes of the site. Two intensities are referred to as Operating Basis Earthquake and Design Basis Earthquake. These structures are required to accommodate these seismic loadings without loss of their functional integrity. Thus, no plastic yield is allowed. The application of NASTRAN in analyzing some of these seismic induced structural dynamic problems is described. NASTRAN, with some modifications, can be used to analyze most structures that are subjected to seismic loads. A brief review of the formulation of seismic-induced structural dynamics is also presented. Two typical structural problems were selected to illustrate the application of the various methods of seismic structural analysis by the NASTRAN system.

  6. Static Converter for High Energy Utilization, Modular, Small Nuclear Power Plants

    SciTech Connect

    El-Genk, Mohamed S.; Tournier, Jean-Michel P.

    2002-07-01

    This paper presents and analyzes the performance of high efficiency, high total energy utilization, static converters, which could be used in conjunction with small nuclear reactor plants in remote locations and in undersea applications, requiring little or no maintenance. The converters consist of a top cycle of Alkali Metal Thermal-to-Electric Conversion (AMTEC) units and PbTe thermoelectric (TE) bottom cycle. In addition to converting the reactor thermal power to electricity at 1150 K or less, at a thermodynamic efficiency in the low to mid thirties, the heat rejection from the TE bottom cycle could be used for space heating, industrial processing, or sea water desalination. The results indicated that for space heating applications, where the rejected thermal power from the TE bottom cycle is removed by natural convection of ambient air, a total utilization of the reactor thermal power of > 80% is possible. When operated at 1030 K, potassium AMTEC/TE converters are not only more efficient than the sodium AMTEC/TE converters but produce more electrical power. The present analysis showed that a single converter could be sized to produce up to 100 kWe and 70 kWe, for the Na-AMTEC/TE units when operating at 1150 K and the K-AMTEC/TE units when operating at 1030 K, respectively. Such modularity is an added advantage to the high-energy utilization of the present AMTEC/TE converters. (authors)

  7. Inspection of Nuclear Power Plant Containment Structures

    SciTech Connect

    Graves, H.L.; Naus, D.J.; Norris, W.E.

    1998-12-01

    Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number of low-probability external and interval events, such as earthquakes, tornadoes, and loss-of-coolant accidents. Loadings incurred during normal plant operation therefore generally are not significant enough to cause appreciable degradation. However, these structures are susceptible to aging by various processes depending on the operating environment and service conditions. The effects of these processes may accumulate within these structures over time to cause failure under design conditions, or lead to costly repair. In the late 1980s and early 1990s several occurrences of degradation of NPP structures were discovered at various facilities (e.g., corrosion of pressure boundary components, freeze- thaw damage of concrete, and larger than anticipated loss of prestressing force). Despite these degradation occurrences and a trend for an increasing rate of occurrence, in-service inspection of the safety-related structures continued to be performed in a somewhat cursory manner. Starting in 1991, the U.S. Nuclear Regulatory Commission (USNRC) published the first of several new requirements to help ensure that adequate in-service inspection of these structures is performed. Current regulatory in-service inspection requirements are reviewed and a summary of degradation experience presented. Nondestructive examination techniques commonly used to inspect the NPP steel and concrete structures to identify and quantify the amount of damage present are reviewed. Finally, areas where nondestructive evaluation techniques require development (i.e., inaccessible portions of the containment pressure boundary, and thick heavily reinforced concrete sections are discussed.

  8. Emotional consequences of nuclear power plant disasters.

    PubMed

    Bromet, Evelyn J

    2014-02-01

    The emotional consequences of nuclear power plant disasters include depression, anxiety, post-traumatic stress disorder, and medically unexplained somatic symptoms. These effects are often long term and associated with fears about developing cancer. Research on disasters involving radiation, particularly evidence from Chernobyl, indicates that mothers of young children and cleanup workers are the highest risk groups. The emotional consequences occur independently of the actual exposure received. In contrast, studies of children raised in the shadows of the Three Mile Island (TMI) and Chernobyl accidents suggest that although their self-rated health is less satisfactory than that of their peers, their emotional, academic, and psychosocial development is comparable. The importance of the psychological impact is underscored by its chronicity and by several studies showing that poor mental health is associated with physical health conditions, early mortality, disability, and overuse of medical services. Given the established increase in mental health problems following TMI and Chernobyl, it is likely that the same pattern will occur in residents and evacuees affected by the Fukushima meltdowns. Preliminary data from Fukushima indeed suggest that workers and mothers of young children are at risk of depression, anxiety, psychosomatic, and post-traumatic symptoms both as a direct result of their fears about radiation exposure and an indirect result of societal stigma. Thus, it is important that non-mental health providers learn to recognize and manage psychological symptoms and that medical programs be designed to reduce stigma and alleviate psychological suffering by integrating psychiatric and medical treatment within the walls of their clinics.Introduction of Emotional Consequences of Nuclear Power Plant Disasters (Video 2:15, http://links.lww.com/HP/A34). PMID:24378494

  9. Next Generation Nuclear Plant GAP Analysis Report

    SciTech Connect

    Ball, Sydney J; Burchell, Timothy D; Corwin, William R; Fisher, Stephen Eugene; Forsberg, Charles W.; Morris, Robert Noel; Moses, David Lewis

    2008-12-01

    As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

  10. [Chernobyl nuclear power plant accident and Tokaimura criticality accident].

    PubMed

    Takada, Jun

    2012-03-01

    It is clear from inspection of historical incidents that the scale of disasters in a nuclear power plant accident is quite low level overwhelmingly compared with a nuclear explosion in nuclear war. Two cities of Hiroshima and Nagasaki were destroyed by nuclear blast with about 20 kt TNT equivalent and then approximately 100,000 people have died respectively. On the other hand, the number of acute death is 30 in the Chernobyl nuclear reactor accident. In this chapter, we review health hazards and doses in two historical nuclear incidents of Chernobyl and Tokaimura criticality accident and then understand the feature of the radiation accident in peaceful utilization of nuclear power. PMID:22514916

  11. 75 FR 16520 - James A. Fitzpatrick Nuclear Power Plant; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-01

    ... have a significant effect on the quality of the human environment (75 FR 14637; dated March 26, 2010... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION James A. Fitzpatrick Nuclear Power Plant; Exemption 1.0 Background Entergy Nuclear Operations,...

  12. Some aspects of the decommissioning of nuclear power plants

    SciTech Connect

    Khvostova, M. S.

    2012-03-15

    The major factors influencing the choice of a national concept for the decommissioning of nuclear power plants are examined. The operating lifetimes of power generating units with nuclear reactors of various types (VVER-1000, VVER-440, RBMK-1000, EGP-6, and BN-600) are analyzed. The basic approaches to decommissioning Russian nuclear power plants and the treatment of radioactive waste and spent nuclear fuel are discussed. Major aspects of the ecological and radiation safety of personnel, surrounding populations, and the environment during decommissioning of nuclear installations are identified.

  13. Osmotically-assisted desalination method and system

    SciTech Connect

    Achilli, Andrea; Childress, Amy E.; Cath, Tzahi Y.

    2014-08-12

    Systems and methods for osmotically assisted desalination include using a pressurized concentrate from a pressure desalination process to pressurize a feed to the desalination process. The depressurized concentrate thereby produced is used as a draw solution for a pressure-retarded osmosis process. The pressure-retarded osmosis unit produces a pressurized draw solution stream that is used to pressurize another feed to the desalination process. In one example, the feed to the pressure-retarded osmosis process is impaired water.

  14. 76 FR 40403 - R.E. Ginna Nuclear Power Plant, LLC, R.E. Ginna Nuclear Power Plant, R.E. Ginna Independent Spent...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-08

    ... participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August... COMMISSION R.E. Ginna Nuclear Power Plant, LLC, R.E. Ginna Nuclear Power Plant, R.E. Ginna Independent Spent.... Ginna Nuclear Power Plant (Ginna), currently held by R.E. Ginna Nuclear Power Plant, LLC as owner...

  15. Fukushima nuclear power plant accident was preventable

    NASA Astrophysics Data System (ADS)

    Kanoglu, Utku; Synolakis, Costas

    2015-04-01

    On 11 March 2011, the fourth largest earthquake in recorded history triggered a large tsunami, which will probably be remembered from the dramatic live pictures in a country, which is possibly the most tsunami-prepared in the world. The earthquake and tsunami caused a major nuclear power plant (NPP) accident at the Fukushima Dai-ichi, owned by Tokyo Electric Power Company (TEPCO). The accident was likely more severe than the 1979 Three Mile Island and less severe than the Chernobyl 1986 accidents. Yet, after the 26 December 2004 Indian Ocean tsunami had hit the Madras Atomic Power Station there had been renewed interest in the resilience of NPPs to tsunamis. The 11 March 2011 tsunami hit the Onagawa, Fukushima Dai-ichi, Fukushima Dai-ni, and Tokai Dai-ni NPPs, all located approximately in a 230km stretch along the east coast of Honshu. The Onagawa NPP was the closest to the source and was hit by an approximately height of 13m tsunami, of the same height as the one that hit the Fukushima Dai-ichi. Even though the Onagawa site also subsided by 1m, the tsunami did not reach to the main critical facilities. As the International Atomic Energy Agency put it, the Onagawa NPP survived the event "remarkably undamaged." At Fukushima Dai-ichi, the three reactors in operation were shut down due to strong ground shaking. The earthquake damaged all offsite electric transmission facilities. Emergency diesel generators (EDGs) provided back up power and started cooling down the reactors. However, the tsunami flooded the facilities damaging 12 of its 13 EDGs and caused a blackout. Among the consequences were hydrogen explosions that released radioactive material in the environment. It is unfortunately clear that TEPCO and Japan's principal regulator Nuclear and Industrial Safety Agency (NISA) had failed in providing a professional hazard analysis for the plant, even though their last assessment had taken place only months before the accident. The main reasons are the following. One

  16. Use of neurals networks in nuclear power plant diagnostics

    SciTech Connect

    Uhrig, R.E. . Dept. of Nuclear Engineering Oak Ridge National Lab., TN )

    1989-01-01

    A technique using neural networks as a means of diagnosing transients or abnormal conditions in nuclear power plants is investigated and found to be feasible. The technique is based on the fact that each physical state of the plant can be represented by a unique pattern of sensor outputs or instrument readings that can be related to the condition of the plant. Neural networks are used to relate this pattern to the fault, problem, or transient condition of the plant. A demonstration of the ability of this technique to identify causes of perturbations in the steam generator of a nuclear plant is presented. 3 refs., 4 figs.

  17. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    SciTech Connect

    L.E. Demick

    2011-10-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  18. Desalination of water

    SciTech Connect

    Pasternak, M.; Morduchowitz, A.

    1991-08-06

    This patent describes the method of treating a charge aqueous solution containing a soluble salt. It comprises maintaining a non-porous separating membrane of thickness of 0.2-1 microns of polyimine polymer which has been cross-linked with a polyisocyanate - NCO or a poly(carbonyl chloride - COCl) cross-linking agent sufficient for providing properties for at least desalinating salt water; maintaining a pressure drop across the non-porous separating polyimine layer; passing a charge aqueous solution containing a soluble salt into contact with the high pressure side of the non-porous separating polyimine layer whereby at least a portion of the water in the charge aqueous solution and a lesser portion of salt pass through the non-porous separating layer of polyimine; recovering from the low pressure side of the polyimine separating layer the lean liquid containing a lesser concentration of salt than is present in the charge aqueous solution; and recovering from the high pressure side of the polyimine separating layer the rich liquid containing a lesser concentration of salt than is present in the charge aqueous solution.

  19. Nuclear thiol redox systems in plants.

    PubMed

    Delorme-Hinoux, Valérie; Bangash, Sajid A K; Meyer, Andreas J; Reichheld, Jean-Philippe

    2016-02-01

    Thiol-disulfide redox regulation is essential for many cellular functions in plants. It has major roles in defense mechanisms, maintains the redox status of the cell and plays structural, with regulatory roles for many proteins. Although thiol-based redox regulation has been extensively studied in subcellular organelles such as chloroplasts, it has been much less studied in the nucleus. Thiol-disulfide redox regulation is dependent on the conserved redox proteins, glutathione/glutaredoxin (GRX) and thioredoxin (TRX) systems. We first focus on the functions of glutathione in the nucleus and discuss recent data concerning accumulation of glutathione in the nucleus. We also provide evidence that glutathione reduction is potentially active in the nucleus. Recent data suggests that the nucleus is enriched in specific GRX and TRX isoforms. We discuss the biochemical and molecular characteristics of these isoforms and focus on genetic evidences for their potential nuclear functions. Finally, we make an overview of the different thiol-based redox regulated proteins in the nucleus. These proteins are involved in various pathways including transcriptional regulation, metabolism and signaling. PMID:26795153

  20. Macrofouling control in nuclear power plants

    SciTech Connect

    Ekis, E.W. Jr.; Keoplin-Gall, S.M.; McCarthy, R.E.

    1991-11-01

    Macrofouling of cooling-water systems is one of the more significant and costly problems encountered in the nuclear power industry. Both marine and freshwater macroinvertebrates can be responsible for losses in plant availability because of plugged intakes and heat transfer equipment. There is a greater diversity of macrofouling organisms in marine waters than in fresh waters. Marine macrofouling organisms include barnacles, mollusks, bryozoans, and hydroids. Barnacles are crustaceans with feathery appendages, which allow them to attach to a variety of surfaces. They are a major cause of severe macrofouling because they can remain attached even after death. The major freshwater macrofouling organisms include the Asiatic Clam (Corbicula fluminea) and the newest freshwater macrofouler, the Zebra Mussel (Dreissena polymorpha). The introduction of the Zebra Mussel into the Great Lakes has created economic and ecological problems that will not easily be solved. The threat of intercontinental dispersal of the Zebra Mussel in America is serious. Research programs have been initiated around the country to develop control methods for this macrofouling problem. The various control methodologies can be classified in the following categories: biological, chemical, physical, and mechanical. Laboratory experiments were performed to evaluate the efficacy of Actibrom against mature Zebra Mussels.

  1. Nuclear plant-aging research on reactor protection systems

    SciTech Connect

    Meyer, L.C.

    1988-01-01

    This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed.

  2. Efficient plant male fertility depends on vegetative nuclear movement mediated by two families of plant outer nuclear membrane proteins

    PubMed Central

    Zhou, Xiao; Meier, Iris

    2014-01-01

    Increasing evidence suggests that nuclear migration is important for eukaryotic development. Although nuclear migration is conserved in plants, its importance for plant development has not yet been established. The most extraordinary plant nuclear migration events involve plant fertilization, which is starkly different from that of animals. Instead of evolving self-propelled sperm cells (SCs), plants use pollen tubes to deliver SCs, in which the pollen vegetative nucleus (VN) and the SCs migrate as a unit toward the ovules, a fundamental but barely understood process. Here, we report that WPP domain-interacting proteins (WIPs) and their binding partners the WPP domain-interacting tail-anchored proteins (WITs) are essential for pollen nuclear migration. Loss-of-function mutations in WIT and/or WIP gene families resulted in impaired VN movement, inefficient SC delivery, and defects in pollen tube reception. WIPs are Klarsicht/ANC-1/Syne-1 Homology (KASH) analogs in plants. KASH proteins are key players in animal nuclear migration. Thus, this study not only reveals an important nuclear migration mechanism in plant fertilization but also, suggests that similar nuclear migration machinery is conserved between plants and animals. PMID:25074908

  3. Mesoscale to plant-scale models of nuclear waste reprocessing.

    SciTech Connect

    Noble, David Frederick; O'Hern, Timothy John; Moffat, Harry K.; Nemer, Martin B.; Domino, Stefan Paul; Rao, Rekha Ranjana; Cipiti, Benjamin B.; Brotherton, Christopher M.; Jove-Colon, Carlos F.; Pawlowski, Roger Patrick

    2010-09-01

    Imported oil exacerabates our trade deficit and funds anti-American regimes. Nuclear Energy (NE) is a demonstrated technology with high efficiency. NE's two biggest political detriments are possible accidents and nuclear waste disposal. For NE policy, proliferation is the biggest obstacle. Nuclear waste can be reduced through reprocessing, where fuel rods are separated into various streams, some of which can be reused in reactors. Current process developed in the 1950s is dirty and expensive, U/Pu separation is the most critical. Fuel rods are sheared and dissolved in acid to extract fissile material in a centrifugal contactor. Plants have many contacts in series with other separations. We have taken a science and simulation-based approach to develop a modern reprocessing plant. Models of reprocessing plants are needed to support nuclear materials accountancy, nonproliferation, plant design, and plant scale-up.

  4. A Novel, Safe, and Environmentally Friendly Technology for Water Production Through Recovery of Rejected Thermal Energy From Nuclear Power Plants

    SciTech Connect

    Khalil, Yehia F.; Elimelech, Menachem

    2006-07-01

    In this work, we describe a novel design that utilizes seawater and a portion of rejected heat from a nuclear plant's steam cycle to operate a water desalination system using forward osmosis technology. Water produced from this process is of sufficient quality to be readily used to supply plant demands for continuous makeup water. The proposed process minimizes the environmental concerns associated with thermal pollution of public waters and the resulting adverse impact on marine ecology. To demonstrate the technical feasibility of this conceptual design of a water treatment process, we discuss a case study as an example to describe how the proposed design can be implemented in a nuclear power station with a once--through cooling system that discharges rejected heat to an open sound seawater as its ultimate heat sink. In this case study, the station uses a leased (vendor owned and operated) onsite water treatment system that demineralizes and polishes up to 500-gpm of city water (at 100 ppm TDS) to supply high-quality makeup water (< 0.01 ppm TDS) to the plant steam system. The objectives of implementing the new design are three fold: 1) forego current practice of using city water as the source of plant makeup water, thereby reducing the nuclear station's impact on the region's potable water supply by roughly 100 million gallons/year, 2) minimize the adverse impact of discharging rejected heat into the open sound seawater and, hence, protect the marine ecology, and 3) eliminate the reliance on external vendor that owns and operates the onsite water treatment system, thereby saving an annual fixed cost of $600 K plus 6 cents per 1,000 gallons of pure water. The design will also eliminate the need for using two double-path reverse osmosis (RO) units that consume 425 kW/h of electric power to operate two RO pumps (480 V, 281.6 HP, and 317.4 amps). (authors)

  5. Localized hyper saline waters in Arabian Gulf from desalination activity--an example from South Kuwait.

    PubMed

    Uddin, Saif; Al Ghadban, Abdul Nabi; Khabbaz, Ahmed

    2011-10-01

    Desalination is the only means of reliable water supply in most of the Arabian Gulf States including Kuwait, Saudi Arabia, Bahrain, Qatar, and United Arab Emirates. Huge desalination capacities are installed on the western margin of the Arabian Gulf contributing to increased salinity off the coast. This paper presents long term salinity observation made near outfall of Az Zour Power and Desalination Plant in South Kuwait. The salinity values peak at around 50 ppt at observation station located in open gulf around 5 km from the outfall of the power and desalination plant. The observation highlights the stress on the local marine environment continued incremental salinity can impair the marine biodiversity in the area. The study suggests that a stringent post construction and operational offshore water quality assessment can help in early detection of potentially complex environmental issues. PMID:21213041

  6. Characterization of saline groundwater across the coastal aquifer of Israel as resource for desalination

    NASA Astrophysics Data System (ADS)

    Stein, Shaked; Russak, Amos; Sivan, Orit; Yechieli, Yospeh; Oren, Yoram; Kasher, Roni

    2015-04-01

    In arid countries with access to marine water seawater desalination is becoming an important water source in order to deal with the water scarcity and population growth. Seawater reverse osmosis (RO) facilities use open seawater intake, which requires pretreatment processes to remove particles in order to avoid fouling of the RO membrane. In small and medium size desalination facilities, an alternative water source can be saline groundwater in coastal aquifers. Using saline groundwater from boreholes near the shore as feed water may have the advantage of natural filtration and low organic content. It will also reduce operation costs of pretreatment. Another advantage of using groundwater is its availability in highly populated areas, where planning of large RO desalination plants is difficult and expensive due to real-estate prices. Pumping saline groundwater underneath the freshwater-seawater interface (FSI) might shift the interface towards the sea, thus rehabilitating the fresh water reservoirs in the aquifer. In this research, we tested the potential use of saline groundwater in the coastal aquifer of Israel as feed water for desalination using field work and desalination experiments. Specifically, we sampled the groundwater from a pumping well 100 m from the shore of Tel-Aviv and sea water from the desalination plant in Ashqelon, Israel. We used an RO cross flow system in a pilot plant in order to compare between the two water types in terms of permeate flux, permeate flux decline, salt rejection of the membrane and the fouling on the membrane. The feed, brine and fresh desalinated water from the outlet of the desalination system were chemically analyzed and compared. Field measurements of dissolved oxygen, temperature, pH and salinity were also conducted in situ. Additionally, SDI (silt density index), which is an important index for desalination, and total organic carbon that has a key role in organic fouling and development of biofouling, were measured and

  7. Purification of High Salinity Brine by Multi-Stage Ion Concentration Polarization Desalination

    PubMed Central

    Kim, Bumjoo; Kwak, Rhokyun; Kwon, Hyukjin J.; Pham, Van Sang; Kim, Minseok; Al-Anzi, Bader; Lim, Geunbae; Han, Jongyoon

    2016-01-01

    There is an increasing need for the desalination of high concentration brine (>TDS 35,000 ppm) efficiently and economically, either for the treatment of produced water from shale gas/oil development, or minimizing the environmental impact of brine from existing desalination plants. Yet, reverse osmosis (RO), which is the most widely used for desalination currently, is not practical for brine desalination. This paper demonstrates technical and economic feasibility of ICP (Ion Concentration Polarization) electrical desalination for the high saline water treatment, by adopting multi-stage operation with better energy efficiency. Optimized multi-staging configurations, dependent on the brine salinity values, can be designed based on experimental and numerical analysis. Such an optimization aims at achieving not just the energy efficiency but also (membrane) area efficiency, lowering the true cost of brine treatment. ICP electrical desalination is shown here to treat brine salinity up to 100,000 ppm of Total Dissolved Solids (TDS) with flexible salt rejection rate up to 70% which is promising in a various application treating brine waste. We also demonstrate that ICP desalination has advantage of removing both salts and diverse suspended solids simultaneously, and less susceptibility to membrane fouling/scaling, which is a significant challenge in the membrane processes. PMID:27545955

  8. Purification of High Salinity Brine by Multi-Stage Ion Concentration Polarization Desalination.

    PubMed

    Kim, Bumjoo; Kwak, Rhokyun; Kwon, Hyukjin J; Pham, Van Sang; Kim, Minseok; Al-Anzi, Bader; Lim, Geunbae; Han, Jongyoon

    2016-01-01

    There is an increasing need for the desalination of high concentration brine (>TDS 35,000 ppm) efficiently and economically, either for the treatment of produced water from shale gas/oil development, or minimizing the environmental impact of brine from existing desalination plants. Yet, reverse osmosis (RO), which is the most widely used for desalination currently, is not practical for brine desalination. This paper demonstrates technical and economic feasibility of ICP (Ion Concentration Polarization) electrical desalination for the high saline water treatment, by adopting multi-stage operation with better energy efficiency. Optimized multi-staging configurations, dependent on the brine salinity values, can be designed based on experimental and numerical analysis. Such an optimization aims at achieving not just the energy efficiency but also (membrane) area efficiency, lowering the true cost of brine treatment. ICP electrical desalination is shown here to treat brine salinity up to 100,000 ppm of Total Dissolved Solids (TDS) with flexible salt rejection rate up to 70% which is promising in a various application treating brine waste. We also demonstrate that ICP desalination has advantage of removing both salts and diverse suspended solids simultaneously, and less susceptibility to membrane fouling/scaling, which is a significant challenge in the membrane processes. PMID:27545955

  9. EMOTIONAL CONSEQUENCES OF NUCLEAR POWER PLANT DISASTERS

    PubMed Central

    Bromet, Evelyn J.

    2014-01-01

    The emotional consequences of nuclear power plant disasters include depression, anxiety, post-traumatic stress disorder, and medically unexplained somatic symptoms. These effects are often long term and associated with fears about developing cancer. Research on disasters involving radiation, particularly evidence from Chernobyl, indicates that mothers of young children and cleanup workers are the highest risk groups. The emotional consequences occur independently of the actual exposure received. In contrast, studies of children raised in the shadows of the Three Mile Island (TMI) and Chernobyl accidents suggest that although their self-rated health is less satisfactory than that of their peers, their emotional, academic, and psychosocial development is comparable. The importance of the psychological impact is underscored by its chronicity and by several studies showing that poor mental health is associated with physical health conditions, early mortality, disability, and over-utilization of medical services. Given the established increase in mental health problems following TMI and Chernobyl, it is likely that the same pattern will occur in residents and evacuees affected by the Fukushima meltdowns. Preliminary data from Fukushima indeed suggest that workers and mothers of young children are at risk of depression, anxiety, psychosomatic, and post-traumatic symptoms both as a direct result of their fears about radiation exposure and an indirect result of societal stigma. Thus, it is important that nonmental health providers learn to recognize and manage psychological symptoms and that medical programs be designed to reduce stigma and alleviate psychological suffering by integrating psychiatric and medical treatment within the walls of their clinics. PMID:24378494

  10. Fresh nuclear fuel measurements at Ukrainian nuclear power plants

    SciTech Connect

    Kuzminski, Jozef; Ewing, Tom; Dickman, Debbie; Gavrilyuk, Victor; Drapey, Sergey; Kirischuk, Vladimir; Strilchuk, Nikolay

    2009-01-01

    In 2005, the Provisions on Nuclear Material Measurement System was enacted in Ukraine as an important regulatory driver to support international obligations in nuclear safeguards and nonproliferation. It defines key provisions and requirements for material measurement and measurement control programs to ensure the quality and reliability of measurement data within the framework of the State MC&A System. Implementing the Provisions requires establishing a number of measurement techniques for both fresh and spent nuclear fuel for various types of Ukrainian reactors. Our first efforts focused on measurements of fresh nuclear fuel from a WWR-1000 power reactor.

  11. Reliability of emergency ac power systems at nuclear power plants

    SciTech Connect

    Battle, R E; Campbell, D J

    1983-07-01

    Reliability of emergency onsite ac power systems at nuclear power plants has been questioned within the Nuclear Regulatory Commission (NRC) because of the number of diesel generator failures reported by nuclear plant licensees and the reactor core damage that could result from diesel failure during an emergency. This report contains the results of a reliability analysis of the onsite ac power system, and it uses the results of a separate analysis of offsite power systems to calculate the expected frequency of station blackout. Included is a design and operating experience review. Eighteen plants representative of typical onsite ac power systems and ten generic designs were selected to be modeled by fault trees. Operating experience data were collected from the NRC files and from nuclear plant licensee responses to a questionnaire sent out for this project.

  12. Nuclear Technology Series. Nuclear Reactor (Plant) Operator Trainee. A Suggested Program Planning Guide. Revised June 80.

    ERIC Educational Resources Information Center

    Center for Occupational Research and Development, Inc., Waco, TX.

    This program planning guide for a two-year postsecondary nuclear reactor (plant) operator trainee program is designed for use with courses 1-16 of thirty-five in the Nuclear Technology Series. The purpose of the guide is to describe the nuclear power field and its job categories for specialists, technicians and operators; and to assist planners,…

  13. 77 FR 28407 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-14

    ... January 1998 (63 FR 2426; January 15, 1998), because the underlying basis standard, ANSI N15.8-1974... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants AGENCY:...

  14. 75 FR 16524 - FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-01

    ... have a significant effect on the quality of the human environment (75 FR 14638). This exemption is... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION FirstEnergy Nuclear Operating Company, Perry Nuclear Power Plant; Exemption 1.0 Background...

  15. 78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-27

    ... Information DG-5028, was published in the Federal Register on May 14, 2012 (77 FR 28407), for a 60-day public... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants AGENCY:...

  16. Prediction of Technological Failures in Nuclear Power Plant Operation

    SciTech Connect

    Salnykov, A. A.

    2015-01-15

    A method for predicting operating technological failures in nuclear power plants which makes it possible to reduce the unloading of the generator unit during the onset and development of an anomalous engineering state of the equipment by detecting a change in state earlier and taking suitable measures. With the circulating water supply loop of a nuclear power plant as an example, scenarios and algorithms for predicting technological failures in the operation of equipment long before their actual occurrence are discussed.

  17. Hierarchical structure for risk criteria applicable to nuclear power plants

    SciTech Connect

    Hall, R.E.; Mitra, S.P.

    1985-01-01

    This paper discusses the development of a hierarchical structure for risk criteria applicable to nuclear power plants. The structure provides a unified framework to systematically analyze the implications of different types of criteria, each focusing on a particular aspect of nuclear power plant risks. The framework allows investigation of the specific coverage of a particular criterion and comparison of different criteria with regard to areas to which they apply. 5 refs., 2 figs.

  18. Method for assigning sites to projected generic nuclear power plants

    SciTech Connect

    Holter, G.M.; Purcell, W.L.; Shutz, M.E.; Young, J.R.

    1986-07-01

    Pacific Northwest Laboratory developed a method for forecasting potential locations and startup sequences of nuclear power plants that will be required in the future but have not yet been specifically identified by electric utilities. Use of the method results in numerical ratings for potential nuclear power plant sites located in each of the 10 federal energy regions. The rating for each potential site is obtained from numerical factors assigned to each of 5 primary siting characteristics: (1) cooling water availability, (2) site land area, (3) power transmission land area, (4) proximity to metropolitan areas, and (5) utility plans for the site. The sequence of plant startups in each federal energy region is obtained by use of the numerical ratings and the forecasts of generic nuclear power plant startups obtained from the EIA Middle Case electricity forecast. Sites are assigned to generic plants in chronological order according to startup date.

  19. Radiological impact of power plants: coal vs nuclear

    SciTech Connect

    Styron, C.E.

    1981-12-23

    A definitive comparison of the radiological impact of coal power plants with that of (normally operating) nuclear power plants is quite difficult because of (1) insufficient data on both types of plants; (2) the diversity in design and performance of coal-fired plants and emission control systems; and (3) the relatively low concentrations of radionuclides to be measured. Radiation doses to the public estimated for coal and normally operating nuclear power plants are quite small when compared to natural background, and the level of uncertainty associated with estimates of radiological impact is so large that it is not possible at this time to demonstrate a significant difference between radiological risks of coal and nuclear power.

  20. Desalination. LC Science Tracer Bullet.

    ERIC Educational Resources Information Center

    Buydos, John F., Comp.

    This guide provides a review of the relevant literature on desalination within the collections of the Library of Congress. While not intended as a comprehensive bibliography, this guide is designed as a quick and ready reference source for the reader, and includes the following sections: (1) articles that provide introductions to the topic of…

  1. Performance evaluation of fiber optic components in nuclear plant environments

    SciTech Connect

    Hastings, M.C.; Miller, D.W.; James, R.W.

    1996-03-01

    Over the past several years, the Electric Power Research Institute (EPRI) has funded several projects to evaluate the performance of commercially available fiber optic cables, connective devices, light sources, and light detectors under environmental conditions representative of normal and abnormal nuclear power plant operating conditions. Future projects are planned to evaluate commercially available fiber optic sensors and to install and evaluate performance of instrument loops comprised of fiber optic components in operating nuclear power plant applications. The objective of this research is to assess the viability of fiber optic components for replacement and upgrade of nuclear power plant instrument systems. Fiber optic instrument channels offer many potential advantages: commercial availability of parts and technical support, small physical size and weight, immunity to electromagnetic interference, relatively low power requirements, and high bandwidth capabilities. As existing nuclear power plants continue to replace and upgrade I&C systems, fiber optics will offer a low-cost alternative technology which also provides additional information processing capabilities. Results to date indicate that fiber optics are a viable technology for many nuclear applications, both inside and outside of containments. This work is funded and manage& under the Operations & Maintenance Cost Control research target of EPRI`s Nuclear Power Group. The work is being performed by faculty and students in the Mechanical and Nuclear Engineering Departments and the staff of the Nuclear Reactor Laboratory of the Ohio State University.

  2. Major factors impacting costs of nuclear power plants

    SciTech Connect

    Tan, Z.A.; James, D.W.

    1985-11-01

    China is striving to complete construction of 10,000 MWe of nuclear power plants by the year 2000. The Chinese government is concerned about the costs and is interested in minimizing the economic risks. The paper discusses the problems of cost control in the US and the special problems expected as China begins its nuclear power development.

  3. Children's reactions to the threat of nuclear plant accidents.

    PubMed

    Schwebel, M; Schwebel, B

    1981-04-01

    In the wake of Three Mile Island nuclear plant accident, questionnaire and interview responses of children in elementary and secondary schools revealed their perceptions of the dangers entailed in the continued use of nuclear reactors. Results are compared with a parallel study conducted close to 20 years ago, and implications for mental health are examined. PMID:7223871

  4. Towards appropriate seismic margins in nuclear plant piping

    SciTech Connect

    Kennedy, R.P.; Chokshi, N.C.; Chen, W.P.

    1996-12-01

    Some results of ongoing research being conducted for the US Nuclear Regulatory Commission (NRC) at the Energy Technology Engineering Center (ETEC) are reported. These results include the development of a methodology for establishing and estimating appropriate seismic margins in nuclear plant piping.

  5. 76 FR 66089 - Access Authorization Program for Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-25

    ...The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision to Regulatory Guide 5.66, ``Access Authorization Program for Nuclear Power Plants.'' This guide describes a method that NRC staff considers acceptable to implement the requirements related to an access authorization...

  6. Boron control system for a nuclear power plant

    SciTech Connect

    Brown, W.W.; Van der Schoot, M.R.

    1980-09-30

    Ion exchangers which reversibly store borate ions in a temperature dependent process are combined with evaporative boric acid recovery apparatus to provide a boron control system for controlling the reactivity of nuclear power plants. A plurality of ion exchangers are operated sequentially to provide varying amounts of boric acid to a nuclear reactor for load follow operations. Evaporative boric acid recovery apparatus is utilized for major changes in the boron concentration within the nuclear reactor.

  7. Conceptual design study. Standard Floating Nuclear Power Plant on inshore site and Modified Floating Nuclear Power plant on upriver site

    NASA Astrophysics Data System (ADS)

    1982-02-01

    Both plants/designs are technically feasible. Both compare favorably with conventional nuclear plants with respect to licensability, quality of construction, reliability of operation, and safety. Both offer considerable reductions in construction schedule over conventional nuclear plants. It was estimated that if project durations were reduced by three years the cost of a 1100 MWe nuclear unit could be decreased by $260 million to $450 million. The allowance for funds during construction (AFDC) was estimated to be $929 million for a 1260 MWe nuclear plant with a commercial operation date in 1992. Reducing the schedule from 12 to 9 years, a reduction of 25%, implies a savings in AFDC alone of approximately $230 million. .DLN : Killed, superseded by N85-21597 NASA patent

  8. Early warning indicators for monitoring nuclear plant performance

    SciTech Connect

    Acosta, R.J.

    1997-12-01

    Florida Power & Light Company`s (FP&L`s) Nuclear Division has developed a set of early warning indicators that are used to provide precursor indications of future plant performance. These indicators are monitored by management and safety committees to enable early detection of negative performance so that corrective actions may be taken prior to experiencing a significant decline in plant performance.

  9. Development of an Integrity Evaluation System for Nuclear Power Plants

    NASA Astrophysics Data System (ADS)

    Kim, Young-Jin; Choi, Jae-Boong; Lee, Joon-Seong; Jun, Hyun-Kyu; Park, Youn-Won

    This paper describes the structure and development strategy for integrity evaluation system for nuclear power plants called NPP-KINS/SAFE. NPP-KINS/SAFE consists of three different programs covering the integrity assessment of reactor pressure vessel, pipings, and pressure tubes, respectively. The system has been developed based on currently available codes and standards, and includes a number of databases, expert systems, and numerical analysis schemes. NPP-KINS/SAFE is applicable for various types of nuclear power plants constructed in Korea with the aid of attached database systems including plant specific data. Case studies for the developed system are also provided.

  10. Instrumentation and control upgrade plan for Browns Ferry nuclear plant

    SciTech Connect

    Belew, M.R.; Langley, D.T. ); Torok, R.C.; Wilkinson, C.D. ); Stanley, L. )

    1992-01-01

    A comprehensive upgrade of the instrumentation and control (I C) systems at a power plant represents a formidable project for any utility. For a nuclear plant, the extra safety and reliability requirements along with regulatory constraints add further complications and cost. The need for the upgrade must, therefore, be very compelling, and the process must be well planned from the start. This paper describes the steps taken to initiate the I C upgrade process for Tennessee Valley Authority's (TVA's) Browns Ferry 2 nuclear plant. It explains the impetus for the upgrade, the expected benefits, and the process by which system upgrades will be selected and implemented.

  11. Analysis of valve failure data for LWR nuclear power plants

    SciTech Connect

    Schmidt, W. H.

    1980-01-01

    A computer analysis of the Nuclear Regulatory Commission (NRC) data file, compiled from Licensee Event Report (LER) data sheets, has been performed to characterize and highlight valve failures in light water reactor (LWR) nuclear power plants and provide guidance for valve improvement programs. The analysis is based on data from 1975 through 1978. Over this period, 889 valve citations were reported for pressurized water reactor (PWR) plants and 891 for boiling water reactor (BWR) plants. This report presents the pertinent LER data in a manner which indicates valve performance areas toward which improvement efforts may be directed.

  12. Forward Osmosis in India: Status and Comparison with Other Desalination Technologies

    PubMed Central

    2014-01-01

    With an increase in demand of freshwater and depleting water sources, it is imperative to switch to seawater as a regular source of water supply. However, due to the high total dissolved solid content, it has to be desalinated to make it drinkable. While desalination technologies have been used for many years, mass deployment of such technologies poses a number of challenges like high energy requirements as well as high negative environmental impact through side products and CO2 emissions. The purpose of this paper is to present a sustainable technology for desalination. Forward osmosis, an emerging technology, is compared with the other commonly used technologies worldwide, namely, multieffect distillation, multistage flash distillation, and reverse osmosis as well as other emerging technologies like vapour compression, solar humidification dehumidification, nanofiltration, and freezing desalination. As energy consumption and associated greenhouse gas emissions are one of the major concerns of desalination, this paper concludes that forward osmosis is an emerging sustainable technology for seawater desalination. This paper then presents the challenges involved in the application of forward osmosis in India and presents a plant setup. In the end, the cost comparison of a forward osmosis and reverse osmosis plant has been done and it was concluded that forward osmosis is economically better as well. PMID:27350984

  13. Forward Osmosis in India: Status and Comparison with Other Desalination Technologies.

    PubMed

    Mehta, Dhruv; Gupta, Lovleen; Dhingra, Rijul

    2014-01-01

    With an increase in demand of freshwater and depleting water sources, it is imperative to switch to seawater as a regular source of water supply. However, due to the high total dissolved solid content, it has to be desalinated to make it drinkable. While desalination technologies have been used for many years, mass deployment of such technologies poses a number of challenges like high energy requirements as well as high negative environmental impact through side products and CO2 emissions. The purpose of this paper is to present a sustainable technology for desalination. Forward osmosis, an emerging technology, is compared with the other commonly used technologies worldwide, namely, multieffect distillation, multistage flash distillation, and reverse osmosis as well as other emerging technologies like vapour compression, solar humidification dehumidification, nanofiltration, and freezing desalination. As energy consumption and associated greenhouse gas emissions are one of the major concerns of desalination, this paper concludes that forward osmosis is an emerging sustainable technology for seawater desalination. This paper then presents the challenges involved in the application of forward osmosis in India and presents a plant setup. In the end, the cost comparison of a forward osmosis and reverse osmosis plant has been done and it was concluded that forward osmosis is economically better as well. PMID:27350984

  14. Analysis of nuclear power plant component failures

    SciTech Connect

    Not Available

    1984-01-01

    Items are shown that have caused 90% of the nuclear unit outages and/or deratings between 1971 and 1980 and the magnitude of the problem indicated by an estimate of power replacement cost when the units are out of service or derated. The funding EPRI has provided on these specific items for R and D and technology transfer in the past and the funding planned in the future (1982 to 1986) are shown. EPRI's R and D may help the utilities on only a small part of their nuclear unit outage problems. For example, refueling is the major cause for nuclear unit outages or deratings and the steam turbine is the second major cause for nuclear unit outages; however, these two items have been ranked fairly low on the EPRI priority list for R and D funding. Other items such as nuclear safety (NRC requirements), reactor general, reactor and safety valves and piping, and reactor fuel appear to be receiving more priority than is necessary as determined by analysis of nuclear unit outage causes.

  15. The Next Generation Nuclear Plant (NGNP) Project

    SciTech Connect

    F. H. Southworth; P. E. MacDonald

    2003-11-01

    The Next Generation Nuclear Power (NGNP) Project will demonstrate emissions-free nuclearassisted electricity and hydrogen production by 2015. The NGNP reactor will be a helium-cooled, graphite moderated, thermal neutron spectrum reactor with a design goal outlet temperature of 1000 C or higher. The reactor thermal power and core configuration will be designed to assure passive decay heat removal without fuel damage during hypothetical accidents. The fuel cycle will be a once-through very high burnup low-enriched uranium fuel cycle. This paper provides a description of the project to build the NGNP at the Idaho National Engineering and Environmental Laboratory (INEEL). The NGNP Project includes an overall reactor design activity and four major supporting activities: materials selection and qualification, NRC licensing and regulatory support, fuel development and qualification, and the hydrogen production plant. Each of these activities is discussed in the paper. All the reactor design and construction activities will be managed under the DOE’s project management system as outlined in DOE Order 413.3. The key elements of the overall project management system discussed in this paper include the client and project management organization relationship, critical decisions (CDs), acquisition strategy, and the project logic and timeline. The major activities associated with the materials program include development of a plan for managing the selection and qualification of all component materials required for the NGNP; identification of specific materials alternatives for each system component; evaluation of the needed testing, code work, and analysis required to qualify each identified material; preliminary selection of component materials; irradiation of needed sample materials; physical, mechanical, and chemical testing of unirradiated and irradiated materials; and documentation of final materials selections. The NGNP will be licensed by the NRC under 10 CFR 50 or 10

  16. 78 FR 45573 - Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-29

    ... COMMISSION Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN-FIRE) AGENCY: Nuclear Regulatory Commission. ACTION: Notice of availability; request for public comment.../CR-7135, ``Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire...

  17. Intelligent Component Monitoring for Nuclear Power Plants

    SciTech Connect

    Lefteri Tsoukalas

    2010-07-30

    Reliability and economy are two major concerns for a nuclear power generation system. Next generation nuclear power reactors are being developed to be more reliable and economic. An effective and efficient surveillance system can generously contribute toward this goal. Recent progress in computer systems and computational tools has made it necessary and possible to upgrade current surveillance/monitoring strategy for better performance. For example, intelligent computing techniques can be applied to develop algorithm that help people better understand the information collected from sensors and thus reduce human error to a new low level. Incidents incurred from human error in nuclear industry are not rare and have been proven costly. The goal of this project is to develop and test an intelligent prognostics methodology for predicting aging effects impacting long-term performance of nuclear components and systems. The approach is particularly suitable for predicting the performance of nuclear reactor systems which have low failure probabilities (e.g., less than 10-6 year-). Such components and systems are often perceived as peripheral to the reactor and are left somewhat unattended. That is, even when inspected, if they are not perceived to be causing some immediate problem, they may not be paid due attention. Attention to such systems normally involves long term monitoring and possibly reasoning with multiple features and evidence, requirements that are not best suited for humans.

  18. US nuclear power plant operating cost and experience summaries

    SciTech Connect

    Kohn, W.E.; Reid, R.L.; White, V.S.

    1998-02-01

    NUREG/CR-6577, U.S. Nuclear Power Plant Operating Cost and Experience Summaries, has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants. Cost incurred after initial construction are characterized as annual production costs, representing fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operating summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from annual operating reports submitted by the licensees, plant histories contained in Nuclear Power Experience, trade press articles, and the Nuclear Regulatory Commission (NRC) web site (www.nrc.gov).

  19. Perspectives and Challenges for Water Desalination - A Socio-Economic Multi-Regional Analysis and a Case Study for Texas

    NASA Astrophysics Data System (ADS)

    Ziolkowska, J. R.; Scanlon, B. R.; Young, M.

    2013-12-01

    Water desalination is anticipated to become a prospective solution for mitigating future water shortages in Texas. As of 2010, 46 municipal brackish water desalination plants were operating in Texas with an estimated total desalination capacity of about 120 million gallons per day (2.3% of state water use) (TWDB 2010; TWDB 2013). In 2011, 99% of the State of Texas suffered extreme drought, with large portions suffering through exceptional drought. This event was classified as the one-year drought of record. Moreover, the growing population of Texas and the subsequent growing water demand create an immediate need for long-term planning for a reliable and efficient water supply. Desalination, even though acknowledged as a reliable option in many countries in the world, requires high investment costs and energy inputs. Current costs of desalinated water can range between US1.09/1,000 gallons and US3.7/1,000 gallons (Arroyo and Shirazi 2012), which are about two to three times higher than water costs from conventional sources (San Antonio Water System 2012; AustinTexas.gov 2013). Economic efficiency is still the main factor determining future developments of desalination investments in Texas, and the technology is still emerging. While currently only investment, maintenance and total capital costs per unit water are considered as factors determining viability of a desalination plant, this study aims at depicting a broader picture of socio-economic impacts related to the construction project itself, both in the immediate region and adjacent communities and interlinked sectors. This study presents an Input-Output model for the brackish water desalination plant in San Antonio, with the first stage expected to be completed in 2016. By using multi-regional and sectoral multipliers, the analysis shows that constructing the desalination plant can create 2,050 jobs in the San Antonio region, while it will add 316 more jobs in other regions in Texas by 2016. Construction will

  20. Numerical simulation of electrochemical desalination.

    PubMed

    Hlushkou, D; Knust, K N; Crooks, R M; Tallarek, U

    2016-05-18

    We present an effective numerical approach to simulate electrochemically mediated desalination of seawater. This new membraneless, energy efficient desalination method relies on the oxidation of chloride ions, which generates an ion depletion zone and local electric field gradient near the junction of a microchannel branch to redirect sea salt into the brine stream, consequently producing desalted water. The proposed numerical model is based on resolution of the 3D coupled Navier-Stokes, Nernst-Planck, and Poisson equations at non-uniform spatial grids. The model is implemented as a parallel code and can be employed to simulate mass-charge transport coupled with surface or volume reactions in 3D systems showing an arbitrarily complex geometrical configuration. PMID:27089841

  1. Solar desalination system and method

    SciTech Connect

    Kruse, C.L.

    1985-03-12

    A solar desalination system in which fresh water is derived from sea water by focussing solar ray energy from a collecting reflector onto an evaporator tube located at substantially the focal apex of the reflector. The reflector/evaporator tube assembly is mounted on a horizontal open grid platform which may support a plurality of parallel reflector/evaporator tube assemblies. The reflectors may serve as pontoons to support the desalination system unit on a body of sea water. The solar heat generated vapor is condensed in condenser tubes immersed in the sea water. Intermittently sea water concentrate is withdrawn from the evaporator tubes. Velocity of the vapor passing from the evaporator tubes to the condensers may be utilized for generating power.

  2. Numerical simulation of electrochemical desalination

    NASA Astrophysics Data System (ADS)

    Hlushkou, D.; Knust, K. N.; Crooks, R. M.; Tallarek, U.

    2016-05-01

    We present an effective numerical approach to simulate electrochemically mediated desalination of seawater. This new membraneless, energy efficient desalination method relies on the oxidation of chloride ions, which generates an ion depletion zone and local electric field gradient near the junction of a microchannel branch to redirect sea salt into the brine stream, consequently producing desalted water. The proposed numerical model is based on resolution of the 3D coupled Navier–Stokes, Nernst–Planck, and Poisson equations at non-uniform spatial grids. The model is implemented as a parallel code and can be employed to simulate mass–charge transport coupled with surface or volume reactions in 3D systems showing an arbitrarily complex geometrical configuration.

  3. Nuclear Power Plant NDE Challenges - Past, Present, and Future

    SciTech Connect

    Doctor, S. R.

    2007-03-21

    The operating fleet of U.S. nuclear power plants was built to fossil plant standards (of workmanship, not fitness for service) and with good engineering judgment. Fortuitously, those nuclear power plants were designed using defense-in-depth concepts, with nondestructive examination (NDE) an important layer, so they can tolerate almost any component failure and still continue to operate safely. In the 30+ years of reactor operation, many material failures have occurred. Unfortunately, NDE has not provided the reliability to detect degradation prior to initial failure (breaching the pressure boundary). However, NDE programs have been improved by moving from prescriptive procedures to performance demonstrations that quantify inspection effectiveness for flaw detection probability and sizing accuracy. Other improvements include the use of risk-informed strategies to ensure that reactor components contributing the most risk receive the best and most frequent inspections. Another challenge is the recent surge of interest in building new nuclear power plants in the United States to meet increasing domestic energy demand. New construction will increase the demand for NDE but also offers the opportunity for more proactive inspections. This paper reviews the inception and evolution of NDE for nuclear power plants over the past 40 years, recounts lessons learned, and describes the needs remaining as existing plants continue operation and new construction is contemplated.

  4. Electromagnetic compatibility in nuclear power plants

    SciTech Connect

    Cirillo, J.; Prussel, M.

    1986-02-01

    EMC (electromagnetic compatibility) is being largely ignored in the design of nuclear power instrumentation and control systems. As a result, EMI (electromagnetic interference) is causing costly startup delays and spurious reactor trips. This paper describes existing problems, basic causes, and approaches to their solutions.

  5. Nuclear Power Plant Containment Pressure Boundary Research

    SciTech Connect

    Cherry, J.L.; Chokshi, N.C.; Costello, J.F.; Ellingwood, B.R.; Naus, D.J.

    1999-09-15

    Research to address aging of the containment pressure boundary in light-water reactor plants is summarized. This research is aimed at understanding the significant factors relating occurrence of corrosion, efficacy of inspection, and structural capacity reduction of steel containment and liners of concrete containment. This understanding will lead to improvements in risk-informed regulatory decision making. Containment pressure boundary components are described and potential aging factors identified. Quantitative tools for condition assessments of aging structures to maintain an acceptable level of reliability over the service life of the plant are discussed. Finally, the impact of aging (i.e., loss of shell thickness due to corrosion) on steel containment fragility for a pressurized water reactor ice-condenser plant is presented.

  6. 75 FR 61779 - R.E. Ginna Nuclear Power Plant, LLC; R.E. Ginna Nuclear Power Plant Environmental Assessment and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-06

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION R.E. Ginna Nuclear Power Plant, LLC; R.E. Ginna Nuclear Power Plant Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC) is considering changes to the Emergency Plan, pursuant to 10 CFR 50.54,...

  7. Dynamic testing of nuclear power plant structures: an evaluation

    SciTech Connect

    Weaver, H.J.

    1980-02-01

    Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes work in three main areas: (1) analytical qualification of a set of computer programs developed at LLL to extract model parameters from the time histories; (2) examination of the feasibility of safely exciting nuclear power plant structures and accurately recording the resulting time-history motions; (3) study of how the model parameters that are extracted from the data be used best to evaluate structural integrity and analyze nuclear power plants.

  8. Occupational exposures and practices in nuclear power plants

    SciTech Connect

    Baum, J.W.

    1989-01-01

    As the first generation of commercial nuclear power comes to a close, it is timely to consider the status of occupational exposure in the power generation industry, that is, the collective occupational radiation doses received by workers in nuclear power plants. The picture is surprising. One might have thought that as newer, larger, and more modern plants came on line, there would be a significant decrease in exposure per unit of electricity generated. There is some indication that this is now happening. One might also have thought that the United States, being a leader in the development of nuclear power, and in the knowledge, experience and technology of nuclear radiation protection, would have the greatest success in controlling exposure. This expectation has not been fulfilled. 32 refs., 4 figs., 5 tabs.

  9. A dynamical systems model for nuclear power plant risk

    NASA Astrophysics Data System (ADS)

    Hess, Stephen Michael

    The recent transition to an open access generation marketplace has forced nuclear plant operators to become much more cost conscious and focused on plant performance. Coincidentally, the regulatory perspective also is in a state of transition from a command and control framework to one that is risk-informed and performance-based. Due to these structural changes in the economics and regulatory system associated with commercial nuclear power plant operation, there is an increased need for plant management to explicitly manage nuclear safety risk. Application of probabilistic risk assessment techniques to model plant hardware has provided a significant contribution to understanding the potential initiating events and equipment failures that can lead to core damage accidents. Application of the lessons learned from these analyses has supported improved plant operation and safety over the previous decade. However, this analytical approach has not been nearly as successful in addressing the impact of plant processes and management effectiveness on the risks of plant operation. Thus, the research described in this dissertation presents a different approach to address this issue. Here we propose a dynamical model that describes the interaction of important plant processes among themselves and their overall impact on nuclear safety risk. We first provide a review of the techniques that are applied in a conventional probabilistic risk assessment of commercially operating nuclear power plants and summarize the typical results obtained. The limitations of the conventional approach and the status of research previously performed to address these limitations also are presented. Next, we present the case for the application of an alternative approach using dynamical systems theory. This includes a discussion of previous applications of dynamical models to study other important socio-economic issues. Next, we review the analytical techniques that are applicable to analysis of

  10. Safety system augmentation at Russian nuclear power plants

    SciTech Connect

    Scerbo, J.A.; Satpute, S.N.; Donkin, J.Y.; Reister, R.A. |

    1996-12-31

    This paper describes the design and procurement of a Class IE DC power supply system to upgrade plant safety at the Kola Nuclear Power Plant (NPP). Kola NPP is located above the Arctic circle at Polyarnie Zorie, Murmansk, Russia. Kola NPP consists of four units. Units 1 and 2 have VVER-440/230 type reactors: Units 3 and 4 have VVER-440/213 type reactors. The VVER-440 reactor design is similar to the pressurized water reactor design used in the US. This project provided redundant, Class 1E DC station batteries and DC switchboards for Kola NPP, Units 1 and 2. The new DC power supply system was designed and procured in compliance with current nuclear design practices and requirements. Technical issues that needed to be addressed included reconciling the requirements in both US and Russian codes and satisfying the requirements of the Russian nuclear regulatory authority. Close interface with ATOMENERGOPROEKT (AEP), the Russian design organization, KOLA NPP plant personnel, and GOSATOMNADZOR (GAN), the Russian version of US Nuclear Regulatory Commission, was necessary to develop a design that would assure compliance with current Russian design requirements. Hence, this project was expected to serve as an example for plant upgrades at other similar VVER-440 nuclear plants. In addition to technical issues, the project needed to address language barriers and the logistics of shipping equipment to a remote section of the Former Soviet Union (FSU). This project was executed by Burns and Roe under the sponsorship of the US DOE as part of the International Safety Program (INSP). The INSP is a comprehensive effort, in cooperation with partners in other countries, to improve nuclear safety worldwide. A major element within the INSP is the improvement of the safety of Soviet-designed nuclear reactors.

  11. DOE`s nuclear energy plant optimization program

    SciTech Connect

    Harrison, D.; Savage, C.D.; Singh, B.P.

    1999-09-01

    In December 1997, the United States agreed to the Kyoto Protocol on Climate Change that outlines specific greenhouse gas emissions reduction requirements. A key element of this protocol is binding emissions targets and timetables. The Protocol calls for the United States to reach emissions targets 7% below 1990 emissions levels over the 5-yr period from 2008 to 2012. A key element to achieving this goal will be the continued safe and economic operation of the Nation`s 104 nuclear power plants. These plants provide >20% of the Nation`s electricity, and nearly one-half of the 50 states receive >25% of their electricity from nuclear power. DOE`s current Strategic Plan specifies that the United States maintain its nuclear energy option and improve the efficiency of existing plants as part of its energy portfolio, in the interest of national security. As a result, DOE proposed two new nuclear energy R and D programs for fiscal year (FY) 1999: the Nuclear Energy Research Initiative (NERI), a peer-reviewed, competitively selected R and D program in advanced concepts, and the Nuclear Energy Plant Optimization Program (NEPO). NERI was authorized and received initial funding of $19 million for its first year. NEPO was not funded in 1999 but has been reintroduced in the FY 2000 budget request. NEPO will be a jointly funded R and D program with industry through the Electric Power Research Institute (EPRI) and will address those issues that could hinder continued safe operation of the Nation`s operating nuclear power plants. The FY 2000 funding request to Congress for NEPO is $5 million.

  12. Evaluation of site characteristics for Guangdong nuclear power plant

    SciTech Connect

    Ruming, Z.; Dizhong, W.; Zhongmin, Y.

    1988-01-01

    This paper gives an account of the features of the site of Guangdong Nuclear Power Plant in general and in particular evaluates the outstanding site characteristics related to nuclear safety and public health. It is composed of two parts: the first part describes the seismo-geologic conditions of the site and the other treats the atmospheric dispersion conditions. It also contains the discussion why the possibility of inhabitancy within 5km from the exclusion area boundary would not be affected.

  13. Liquid metal cooled nuclear reactor plant system

    DOEpatents

    Hunsbedt, Anstein; Boardman, Charles E.

    1993-01-01

    A liquid metal cooled nuclear reactor having a passive cooling system for removing residual heat resulting for fuel decay during reactor shutdown, or heat produced during a mishap. The reactor system is enhanced with sealing means for excluding external air from contact with the liquid metal coolant leaking from the reactor vessel during an accident. The invention also includes a silo structure which resists attack by leaking liquid metal coolant, and an added unique cooling means.

  14. Desalination of backish water of brine from hydrocarbon wells

    SciTech Connect

    Fenton, D.M.

    1992-07-07

    This patent describes an apparatus for producing non-brackish water from water containing at least 500 ppm total dissolved solids found in an active hydrocarbon product well. It comprises at least one active hydrocarbon product well located on an offshore oil platform; a means for separating the hydrocarbon product from the water; a desalination plant located on the offshore platform for receiving water containing at least 500 ppm total dissolved solids from the means for separating and for producing non-brackish water; and means for transporting non-brackish water produced by the desalination plant. This paper also describes a method of using an inactivated gas well. It comprises ceasing all gas production in an inactive gas well; recovering water containing at least 500 ppm total dissolved solids from the inactive gas well from a geological formation containing flowable water containing at least 500 ppm total dissolved solids; and desalinating the water to produce liquid water having less than 500 ppmw total dissolved solids.

  15. Heterogonous Nanofluids for Nuclear Power Plants

    NASA Astrophysics Data System (ADS)

    Alammar, Khalid

    2014-09-01

    Nuclear reactions can be associated with high heat energy release. Extracting such energy efficiently requires the use of high-rate heat exchangers. Conventional heat transfer fluids, such as water and oils are limited in their thermal conductivity, and hence nanofluids have been introduced lately to overcome such limitation. By suspending metal nanoparticles with high thermal conductivity in conventional heat transfer fluids, thermal conductivity of the resulting homogeneous nanofluid is increased. Heterogeneous nanofluids offer yet more potential for heat transfer enhancement. By stratifying nanoparticles within the boundary layer, thermal conductivity is increased where temperature gradients are highest, thereby increasing overall heat transfer of a flowing fluid. In order to test the merit of this novel technique, a numerical study of a laminar pipe flow of a heterogeneous nanofluid was conducted. Effect of Iron-Oxide distribution on flow and heat transfer characteristics was investigated. With Iron-Oxide volume concentration of 0.009 in water, up to 50% local heat transfer enhancement was predicted for the heterogeneous compared to homogeneous nanofluids. Increasing the Reynolds number is shown to increase enhancement while having negligible effect on pressure drop. Using permanent magnets attached externally to the pipe, an experimental investigation conducted at MIT nuclear reactor laboratory for similar flow characteristics of a heterogeneous nanofluid have shown upto 160% enhancement in heat transfer. Such results show that heterogeneous nanofluids are promising for augmenting heat transfer rates in nuclear power heat exchanger systems.

  16. Radiation protection performance indicators at the Nuclear Power Plant Krsko.

    PubMed

    Janzekovic, Helena

    2006-06-01

    Nuclear power plant safety performance indicators are developed "by nuclear operating organisations to monitor their own performance and progress, to set their own challenging goals for improvement, and to gain additional perspective on performance relative to that of other plants". In addition, performance indicators are widely used by regulatory authorities although the use is not harmonised. Two basic performance indicators related to good radiation protection practice are collective radiation exposure and volume of low-level radioactive waste. In 2000, Nuclear Power Plant Krsko, a Westinghouse pressurised water reactor with electrical output 700 MW, finished an extensive modernisation including the replacement of both steam generators. While the annual volume of low-level radioactive waste does not show a specific trend related to modernisation, the annual collective dose reached maximum, i.e. 2.60 man Sv, and dropped to 1.13 man Sv in 2001. During the replacement of the steam generators in 2000, the dose associated with this activity was 1.48 man Sv. The annual doses in 2002 and 2003 were 0.53 and 0.80 man Sv, respectively, nearing thus the goal set by the US Institute of Nuclear Power Operators, which is 0.65 man Sv. Therefore, inasmuch as collective dose as the radiation protection performance indicator are concerned, the modernisation of the Krsko nuclear power plant was a success. PMID:16832974

  17. Report on aging of nuclear power plant reinforced concrete structures

    SciTech Connect

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.

    1996-03-01

    The Structural Aging Program provides the US Nuclear Regulatory Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures. The program was organized under four task areas: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technology, and Quantitative Methodology for Continued Service Determinations. Under these tasks, over 90 papers and reports were prepared addressing pertinent aspects associated with aging management of nuclear power plant reinforced concrete structures. Contained in this report is a summary of program results in the form of information related to longevity of nuclear power plant reinforced concrete structures, a Structural Materials Information Center presenting data and information on the time variation of concrete materials under the influence of environmental stressors and aging factors, in-service inspection and condition assessments techniques, repair materials and methods, evaluation of nuclear power plant reinforced concrete structures, and a reliability-based methodology for current and future condition assessments. Recommendations for future activities are also provided. 308 refs., 61 figs., 50 tabs.

  18. A methodology for evaluating ``new`` technologies in nuclear power plants

    SciTech Connect

    Korsah, K.; Clark, R.L.; Holcomb, D.E.

    1994-06-01

    As obsolescence and spare parts issues drive nuclear power plants to upgrade with new technology (such as optical fiber communication systems), the ability of the new technology to withstand stressors present where it is installed needs to be determined. In particular, new standards may be required to address qualification criteria and their application to the nuclear power plants of tomorrow. This paper discusses the failure modes and age-related degradation mechanisms of fiber optic communication systems, and suggests a methodology for identifying when accelerated aging should be performed during qualification testing.

  19. St. Lucie nuclear plant's instrument setpoint control program

    SciTech Connect

    Woodruff, B.A. )

    1991-01-01

    In the past several years, instrument setpoint control has become an issue of significant utility focus and concern. Various nuclear industry initiatives have contributed to shaping the current environment. Florida Power and Light Company's St. Lucie nuclear plant maintains a proactive approach to implementing an instrument setpoint control program. St. Lucie's timely response to prevailing setpoint issues ensures that an effective setpoint program is the end result. Florida Power and Light (FP and L) initiated a setpoint control program at St. Lucie, a two-unit Combustion Engineering plant, in 1985. The plan's development was the result of obsolete equipment modifications, setpoint changes, and regulatory inquiries.

  20. Nuclear power plant fire protection: philosophy and analysis. [PWR; BWR

    SciTech Connect

    Berry, D. L.

    1980-05-01

    This report combines a fire severity analysis technique with a fault tree methodology for assessing the importance to nuclear power plant safety of certain combinations of components and systems. Characteristics unique to fire, such as propagation induced by the failure of barriers, have been incorporated into the methodology. By applying the resulting fire analysis technique to actual conditions found in a representative nuclear power plant, it is found that some safety and nonsafety areas are both highly vulnerable to fire spread and impotant to overall safety, while other areas prove to be of marginal importance. Suggestions are made for further experimental and analytical work to supplement the fire analysis method.

  1. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect

    G. O. Hayner; E.L. Shaber

    2004-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  2. Nuclear power plant alarm systems: Problems and issues

    SciTech Connect

    O'Hara, J.M.; Brown, W.S.

    1991-01-01

    Despite the incorporation of advanced technology into nuclear power plant alarm systems, human factors problems remain. This paper identifies to be addressed in order to allow advanced technology to be used effectively in the design of nuclear power plant alarm systems. The operator's use and processing of alarm system information will be considered. Based upon a review of alarm system research, issues related to general system design, alarm processing, display and control are discussed. It is concluded that the design of effective alarm systems depends on an understanding of the information processing capabilities and limitations of the operator. 39 refs.

  3. Neural networks and their application to nuclear power plant diagnosis

    SciTech Connect

    Reifman, J.

    1997-10-01

    The authors present a survey of artificial neural network-based computer systems that have been proposed over the last decade for the detection and identification of component faults in thermal-hydraulic systems of nuclear power plants. The capabilities and advantages of applying neural networks as decision support systems for nuclear power plant operators and their inherent characteristics are discussed along with their limitations and drawbacks. The types of neural network structures used and their applications are described and the issues of process diagnosis and neural network-based diagnostic systems are identified. A total of thirty-four publications are reviewed.

  4. Protective clothing laundering and monitoring at nuclear power plants

    SciTech Connect

    Hylko, J.M. . Dept. of Nuclear Engineering); Miller, M.L. , Inc., Albuquerque, NM ); Brehm, L.E.; Peterson, S.K. )

    1988-02-01

    This paper reports that a small but significant number of skin contamination incidents at Northern States Power Company's Monticello Nuclear Generating Plant were believed to have been caused by residual contamination in laundered, clean protective clothing. Since very little information was available on this mode of skin contamination, a two-part study was undertaken to evaluate it more fully. The first part of this study consisted of a survey of protective clothing laundering and monitoring practices at 24 nuclear power plants. The second part of the study was a simple experiment to evaluate the effect of perspiration on the transfer of residual contamination from laundered clothing.

  5. Solar Energy Water Desalination in the United States and Saudi Arabia

    SciTech Connect

    Luft, W.

    1981-04-01

    Five solar energy water desalination systems are described. The systems will each deliver 6000 m3/day of desalted water from either seawater or brackish water. After the system definition study is completed in August 1981, two systems will be selected for pilot plant construction. The pilot plants will have capacities in the range of 1 00 to 400 m3/day.

  6. Ground-based testing of space nuclear power plants

    SciTech Connect

    McDonald, T.G.

    1990-10-22

    Small nuclear power plants for space applications are evaluated according to their testability in this two part report. The first part introduces the issues involved in testing these power plants. Some of the concerns include oxygen embrittlement of critical components, the test environment, the effects of a vacuum environment on materials, the practically of racing an activated test chamber, and possible testing alternative the SEHPTR, king develop at the Idaho National Engineering Laboratory. 10 refs., 6 figs., 1 tab.

  7. Energy portfolio of Iran: A case study of solar desalination

    NASA Astrophysics Data System (ADS)

    Besharati, Adib

    Energy plays a very important role in the economic development of a country such as Iran where industrial progress and higher living standards increase demand for energy. Iran is one of the countries in the world that simultaneously produces and consumes large amounts of energy. Because of its geographic latitude and weather conditions, Iran has the potential to develop and use of both fossil and renewable energy sources. In South Iran, there are huge oil and gas resources, and at the same time high potential of solar radiation. However, at the present large-scale utilization, solar energy is prohibitively expensive for Iran. Therefore, this study investigates an economical way to utilize solar energy in a meaningful way for Iran. One of the possible uses of solar energy that is both economical and technically feasible is desalination of water using solar energy. People in South Iran live in different areas with relatively low population density. One of the critical problems in those areas is a lack of clean drinking water. As a result, there is an urgent need to investigate ways to produce clean water from the saltwater. Therefore, the present study conducts a case study of solar desalination in south Iran using solar. Different desalination methods, such as humidification dehumidification by using a solar collector, and reverse osmosis, are discussed. In the case study, a prototype desalination plant was considered and both technical and economic aspects of the plant were investigated in details. The results showed higher productivity of drinking water in reverse osmosis method for south Iran.

  8. 76 FR 55137 - Monitoring the Effectiveness of Maintenance at Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-06

    ... COMMISSION Monitoring the Effectiveness of Maintenance at Nuclear Power Plants AGENCY: Nuclear Regulatory..., ``Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.'' This guide endorses Revision 4A to... Effectiveness of Maintenance at Nuclear Power Plants,'' which provides methods that are acceptable to the...

  9. 78 FR 35330 - Initial Test Programs for Water-Cooled Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-12

    ... COMMISSION Initial Test Programs for Water-Cooled Nuclear Power Plants AGENCY: Nuclear Regulatory Commission... revision to Regulatory Guide (RG), 1.68, ``Initial Test Programs for Water-Cooled Nuclear Power Plants... Initial Test Programs (ITPs) for light water cooled nuclear power plants. ADDRESSES: Please refer...

  10. 77 FR 34093 - License Renewal for Calvert Cliffs Nuclear Power Plant, LLC's

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-08

    ... COMMISSION License Renewal for Calvert Cliffs Nuclear Power Plant, LLC's AGENCY: Nuclear Regulatory... Cliffs Nuclear Power Plant site near Lusby, Maryland. The NRC has prepared an Environmental Assessment... dated September 17, 2010, Calvert Cliffs Nuclear Power Plant, LLC (CCNPP) submitted an application...

  11. Aging assessment of large electric motors in nuclear power plants

    SciTech Connect

    Villaran, M.; Subudhi, M.

    1996-03-01

    Large electric motors serve as the prime movers to drive high capacity pumps, fans, compressors, and generators in a variety of nuclear plant systems. This study examined the stressors that cause degradation and aging in large electric motors operating in various plant locations and environments. The operating history of these machines in nuclear plant service was studied by review and analysis of failure reports in the NPRDS and LER databases. This was supplemented by a review of motor designs, and their nuclear and balance of plant applications, in order to characterize the failure mechanisms that cause degradation, aging, and failure in large electric motors. A generic failure modes and effects analysis for large squirrel cage induction motors was performed to identify the degradation and aging mechanisms affecting various components of these large motors, the failure modes that result, and their effects upon the function of the motor. The effects of large motor failures upon the systems in which they are operating, and on the plant as a whole, were analyzed from failure reports in the databases. The effectiveness of the industry`s large motor maintenance programs was assessed based upon the failure reports in the databases and reviews of plant maintenance procedures and programs.

  12. Seismic risk management solution for nuclear power plants

    DOE PAGESBeta

    Coleman, Justin; Sabharwall, Piyush

    2014-12-01

    Nuclear power plants should safely operate during normal operations and maintain core-cooling capabilities during off-normal events, including external hazards (such as flooding and earthquakes). Management of external hazards to expectable levels of risk is critical to maintaining nuclear facility and nuclear power plant safety. Seismic risk is determined by convolving the seismic hazard with seismic fragilities (capacity of systems, structures, and components). Seismic isolation (SI) is one protective measure showing promise to minimize seismic risk. Current SI designs (used in commercial industry) reduce horizontal earthquake loads and protect critical infrastructure from the potentially destructive effects of large earthquakes. The benefitmore » of SI application in the nuclear industry is being recognized and SI systems have been proposed in American Society of Civil Engineer Standard 4, ASCE-4, to be released in the winter of 2014, for light water reactors facilities using commercially available technology. The intent of ASCE-4 is to provide criteria for seismic analysis of safety related nuclear structures such that the responses to design basis seismic events, computed in accordance with this standard, will have a small likelihood of being exceeded. The U.S. nuclear industry has not implemented SI to date; a seismic isolation gap analysis meeting was convened on August 19, 2014, to determine progress on implementing SI in the U.S. nuclear industry. The meeting focused on the systems and components that could benefit from SI. As a result, this article highlights the gaps identified at this meeting.« less

  13. Seismic risk management solution for nuclear power plants

    SciTech Connect

    Coleman, Justin; Sabharwall, Piyush

    2014-12-01

    Nuclear power plants should safely operate during normal operations and maintain core-cooling capabilities during off-normal events, including external hazards (such as flooding and earthquakes). Management of external hazards to expectable levels of risk is critical to maintaining nuclear facility and nuclear power plant safety. Seismic risk is determined by convolving the seismic hazard with seismic fragilities (capacity of systems, structures, and components). Seismic isolation (SI) is one protective measure showing promise to minimize seismic risk. Current SI designs (used in commercial industry) reduce horizontal earthquake loads and protect critical infrastructure from the potentially destructive effects of large earthquakes. The benefit of SI application in the nuclear industry is being recognized and SI systems have been proposed in American Society of Civil Engineer Standard 4, ASCE-4, to be released in the winter of 2014, for light water reactors facilities using commercially available technology. The intent of ASCE-4 is to provide criteria for seismic analysis of safety related nuclear structures such that the responses to design basis seismic events, computed in accordance with this standard, will have a small likelihood of being exceeded. The U.S. nuclear industry has not implemented SI to date; a seismic isolation gap analysis meeting was convened on August 19, 2014, to determine progress on implementing SI in the U.S. nuclear industry. The meeting focused on the systems and components that could benefit from SI. As a result, this article highlights the gaps identified at this meeting.

  14. 40 CFR 35.1605-7 - Desalinization.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Desalinization. 35.1605-7 Section 35.1605-7 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY GRANTS AND OTHER FEDERAL ASSISTANCE... Lakes § 35.1605-7 Desalinization. Any mechanical procedure or process where some or all of the salt...

  15. 40 CFR 35.1605-7 - Desalinization.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 1 2013-07-01 2013-07-01 false Desalinization. 35.1605-7 Section 35.1605-7 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY GRANTS AND OTHER FEDERAL ASSISTANCE... Lakes § 35.1605-7 Desalinization. Any mechanical procedure or process where some or all of the salt...

  16. 40 CFR 35.1605-7 - Desalinization.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 1 2011-07-01 2011-07-01 false Desalinization. 35.1605-7 Section 35.1605-7 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY GRANTS AND OTHER FEDERAL ASSISTANCE... Lakes § 35.1605-7 Desalinization. Any mechanical procedure or process where some or all of the salt...

  17. 40 CFR 35.1605-7 - Desalinization.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 40 Protection of Environment 1 2012-07-01 2012-07-01 false Desalinization. 35.1605-7 Section 35.1605-7 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY GRANTS AND OTHER FEDERAL ASSISTANCE... Lakes § 35.1605-7 Desalinization. Any mechanical procedure or process where some or all of the salt...

  18. 40 CFR 35.1605-7 - Desalinization.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 1 2014-07-01 2014-07-01 false Desalinization. 35.1605-7 Section 35.1605-7 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY GRANTS AND OTHER FEDERAL ASSISTANCE... Lakes § 35.1605-7 Desalinization. Any mechanical procedure or process where some or all of the salt...

  19. Using Solar Energy to Desalinate Water.

    ERIC Educational Resources Information Center

    Tabor, Harry Z.

    1978-01-01

    Material presented is adapted from Desalination with Solar Energy, a paper presented before the International Symposium on Energy Sources and Development, held in Spain in 1977. Desalination systems energized by the sun, conditions governing their efficiency, and their costs are discussed. (HM)

  20. Peach Bottom and Vermont Yankee Nuclear Power Plants

    SciTech Connect

    1992-12-31

    A dramatic and extraordinary instance of state and local government control of nuclear power, the purchase by New York of the Shoreham plant is nonetheless indicative of the political demands that some states confront for additional involvement in the regulation of the radiological hazards associated with commercial nuclear power plants. Although the Supreme Court has appeared to expand, in the eight years since PG&E and Silkwood, the acceptable extent of state regulation, some states, in addition to New York, have acquired, with the acquiescence of the NRC, a degree of involvement that exceeds the role for state and local governments provided by the Court. For example, the Commonwealth of Pennsylvania concluded with the Philadelphia Electric Company (PECO) in June 1989 an agreement that commits PECO to various initiatives, not otherwise required under NRC regulations, for the safe operation of the Peach Bottom nuclear power plant in Pennsylvania. In July 1991 the State of Vermont and Vermont Yankee Nuclear Power Corporation (Vermont Yankee) concluded an agreement similar to that concluded between Pennsylvania and PECO. The agreement also commits Vermont Yankee to certain initiatives, not otherwise required under NRC regulations, related to its operation of the Vermont Yankee nuclear power plant in Vermont. The agreement was precipitated by a challenge to an application, submitted to the NRC by Vermont Yankee in April 1989, to amend the Vermont Yankee plant license to extend its expiration date from December 11, 2007 to March 21, 2012. The amendment would allow the Vermont Yankee plant to operate for forty full years.

  1. Safety/security interface assessments at commercial nuclear power plants

    SciTech Connect

    Byers, K.R.; Brown, P.J.; Norderhaug, L.R.

    1985-07-01

    The findings of the Haynes Task Force Committee (NUREG-0992) are used as the basis for defining safety/security assessment team activities at commercial nuclear power plants in NRC Region V. A safety/security interface assessment outline and the approach used for making the assessments are presented along with the composition of team members. As a result of observing simulated plant emergency conditions during scheduled emergency preparedness exercises, examining security and operational response procedures, and interviewing plant personnel, the team has identified instances where safety/security conflicts can occur. 2 refs.

  2. Aging management guideline for commercial nuclear power plants - heat exchangers

    SciTech Connect

    Booker, S.; Lehnert, D.; Daavettila, N.; Palop, E.

    1994-06-01

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in commercial nuclear power plant heat exchangers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  3. 76 FR 81994 - UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-29

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION UniStar Nuclear Energy; Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit 3; Exemption 1.0 Background: UniStar Nuclear Energy (UNE) submitted to the U.S. Nuclear...

  4. Is natural background or radiation from nuclear power plants leukemogenic

    SciTech Connect

    Cronkite, E.P.

    1989-01-01

    The objective in this review is to provide some facts about normal hemopoietic cell proliferation relevant to leukemogenesis, physical, chemical, and biological facts about radiation effects with the hope that each person will be able to decide for themselves whether background radiation or emissions from nuclear power plants and facilities significantly add to the spontaneous leukemia incidence. 23 refs., 1 tab.

  5. New Generation Nuclear Plant -- High Level Functions and Requirements

    SciTech Connect

    J. M. Ryskamp; E. J. Gorski; E. A. Harvego; S. T. Khericha; G. A. Beitel

    2003-09-01

    This functions and requirements (F&R) document was prepared for the Next Generation Nuclear Plant (NGNP) Project. The highest-level functions and requirements for the NGNP preconceptual design are identified in this document, which establishes performance definitions for what the NGNP will achieve. NGNP designs will be developed based on these requirements by commercial vendor(s).

  6. Assessment of control rooms of nuclear power plants

    NASA Astrophysics Data System (ADS)

    Norros, L.; Ranta, J.; Wahlstroem, B.

    1983-05-01

    The NUREG 0700 recommendations were assessed for implementation in the control rooms of Finnish nuclear power plants. Direct conclusions drawn from the American situation are misleading, because of differences in, for example, procurement of instruments or personnel training. If the review is limited to control room details, the NRC program (checklist) is successful. It can also be used during planning to observe small discrepancies.

  7. Radioactive Effluents from Nuclear Power Plants Annual Report 2008

    SciTech Connect

    U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

    2010-12-10

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  8. Radioactive Effluents from Nuclear Power Plants Annual Report 2007

    SciTech Connect

    U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

    2010-12-10

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  9. Nuclear physics detector technology applied to plant biology research

    SciTech Connect

    Weisenberger, Andrew G.; Kross, Brian J.; Lee, Seung Joo; McKisson, John E.; Xi, Wenze; Zorn, Carl J.; Howell, Calvin; Crowell, A.S.; Reid, C.D.; Smith, Mark

    2013-08-01

    The ability to detect the emissions of radioactive isotopes through radioactive decay (e.g. beta particles, x-rays and gamma-rays) has been used for over 80 years as a tracer method for studying natural phenomena. More recently a positron emitting radioisotope of carbon: {sup 11}C has been utilized as a {sup 11}CO{sub 2} tracer for plant ecophysiology research. Because of its ease of incorporation into the plant via photosynthesis, the {sup 11}CO{sub 2} radiotracer is a powerful tool for use in plant biology research. Positron emission tomography (PET) imaging has been used to study carbon transport in live plants using {sup 11}CO{sub 2}. Presently there are several groups developing and using new PET instrumentation for plant based studies. Thomas Jefferson National Accelerator Facility (Jefferson Lab) in collaboration with the Duke University Phytotron and the Triangle Universities Nuclear Laboratory (TUNL) is involved in PET detector development for plant imaging utilizing technologies developed for nuclear physics research. The latest developments of the use of a LYSO scintillator based PET detector system for {sup 11}CO{sub 2} tracer studies in plants will be briefly outlined.

  10. Aging of nuclear power plant safety cables

    SciTech Connect

    Gillen, K.T.; Salazar, E.A.

    1986-01-01

    Results from an extensive aging program on polymeric materials stripped from unused nuclear reactor safety cables are described. Mechanical damage was monitored after room temperature aging in a Co-60 gamma radiation source at various humidities and radiation dose rates ranging from 1.2 Mrad/h to 2 krad/h. For chloroprene, chlorosulfonated polyethylene, and silicone materials, the mechanical degradation was found to depend only on the total integrated radiation dose, implying that radiation dose rate effects are small. On the other hand, strong evidence for radiation dose rate effects were found for an ethylene propylene rubber material and a cross-linked polyolefin material. Humidity effects were determined to be insignificant for all the materials studied.

  11. The Acceptance Strategy for Nuclear Power Plant In Indonesia

    NASA Astrophysics Data System (ADS)

    Suhaemi, Tjipta; Syaukat, Achmad

    2010-06-01

    THE ACCEPTANCE STRATEGY FOR NUCLEAR POWER PLANT IN INDONESIA. Indonesia has planned to build nuclear power plants. Some feasibility studies have been conducted intensively. However, the processes of NPP introduction are still uncertain. National Energy Plan in Indonesia, which has been made by some governmental agencies, does not yet give positive impact to the government decision to construct the nuclear power plant (NPP). This paper discusses the process of NPP introduction in Indonesia, which has been colored with debate of stakeholder and has delayed decision for go-nuclear. The technology paradigm is used to promote NPP as an alternative of reliable energy resources. This paradigm should be complemented with international politic-economic point of view. The international politic-economic point of view shows that structural powers, consisting of security, production, finance, and knowledge structures, within which the NPP is introduced, have dynamic characteristics. The process of NPP introduction in Indonesia contains some infrastructure development (R&D, legislation, regulation, energy planning, site study, public acceptance efforts, etc), but they need a better coherent NPP implementation program and NPP Acceptance Program. Strategic patterns for NPP acceptance described in this paper are made by considering nuclear regulation development and the interest of basic domestic participation. The first NPP program in Indonesia having proven technology and basic domestic participation is and important milestone toward and optimal national energy-mix.

  12. European standards and approaches to EMC in nuclear power plants

    SciTech Connect

    Bardsley, D.J.; Dillingham, S.R.; McMinn, K.

    1995-04-01

    Electromagnetic Interference (EMI) arising from a wide range of sources can threaten nuclear power plant operation. The need for measures to mitigate its effects have long been recognised although there are difference in approaches worldwide. The US industry approaches the problem by comprehensive site surveys defining an envelope of emissions for the environmental whilst the UK nuclear industry defined many years ago generic levels which cover power station environments. Moves to standardisation within the European community have led to slight changes in UK approach, in particular how large systems can be tested. The tests undertaken on UK nuclear plant include tests for immunity to conducted as well as radiated interference. Similar tests are also performed elsewhere in Europe but are not, to the authors` knowledge, commonly undertaken in the USA. Currently work is proceeding on draft international standards under the auspices of the IEC.

  13. Nuclear power plant safety related pump issues

    SciTech Connect

    Colaccino, J.

    1996-12-01

    This paper summarizes of a number of pump issues raised since the Third NRC/ASME Symposium on Valve and Pump Testing in 1994. General issues discussed include revision of NRC Inspection Procedure 73756, issuance of NRC Information Notice 95-08 on ultrasonic flow meter uncertainties, relief requests for tests that are determined by the licensee to be impractical, and items in the ASME OM-1995 Code, Subsection ISTB, for pumps. The paper also discusses current pump vibration issues encountered in relief requests and plant inspections - which include smooth running pumps, absolute vibration limits, and vertical centrifugal pump vibration measurement requirements. Two pump scope issues involving boiling water reactor waterlog and reactor core isolation cooling pumps are also discussed. Where appropriate, NRC guidance is discussed.

  14. Reprocessing of nuclear fuels at the Savannah River Plant

    SciTech Connect

    Gray, L.W.

    1986-10-04

    For more than 30 years, the Savannah River Plant (SRP) has been a major supplier of nuclear materials such as plutonium-239 and tritium-3 for nuclear and thermonuclear weapons, plutonium-238 for space exploration, and isotopes of americium, curium, and californium for use in the nuclear research community. SRP is a complete nuclear park, providing most of the processes in the nuclear fuel cycle. Key processes involve fabrication and cladding of the nuclear fuel, target, and control assemblies; rework of heavy water for use as reactor moderator; reactor loading, operation, and unloading; chemical recovery of the reactor transmutation products and spent fuels; and management of the gaseous, liquid, and solid nuclear and chemical wastes; plus a host of support operations. The site's history and the key processes from fabrication of reactor fuels and targets to finishing of virgin plutonium for use in the nuclear weapons complex are reviewed. Emphasis has been given to the chemistry of the recovery and purification of weapons grade plutonium from irradiated reactor targets.

  15. Online Monitoring of Plant Assets in the Nuclear Industry

    SciTech Connect

    Nancy Lybeck; Vivek Agarwal; Binh Pham; Richard Rusaw; Randy Bickford

    2013-10-01

    Today’s online monitoring technologies provide opportunities to perform predictive and proactive health management of assets within many different industries, in particular the defense and aerospace industries. The nuclear industry can leverage these technologies to enhance safety, productivity, and reliability of the aging fleet of existing nuclear power plants. The U.S. Department of Energy’s Light Water Reactor Sustainability Program is collaborating with the Electric Power Research Institute’s (EPRI’s) Long-Term Operations program to implement online monitoring in existing nuclear power plants. Proactive online monitoring in the nuclear industry is being explored using EPRI’s Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software, a set of web-based diagnostic and prognostic tools and databases that serves as an integrated health monitoring architecture. This paper focuses on development of asset fault signatures used to assess the health status of generator step-up transformers and emergency diesel generators in nuclear power plants. Asset fault signatures describe the distinctive features based on technical examinations that can be used to detect a specific fault type. Fault signatures are developed based on the results of detailed technical research and on the knowledge and experience of technical experts. The Diagnostic Advisor of the FW-PHM Suite software matches developed fault signatures with operational data to provide early identification of critical faults and troubleshooting advice that could be used to distinguish between faults with similar symptoms. This research is important as it will support the automation of predictive online monitoring techniques in nuclear power plants to diagnose incipient faults, perform proactive maintenance, and estimate the remaining useful life of assets.

  16. Enhancement of NRC station blackout requirements for nuclear power plants

    SciTech Connect

    McConnell, M. W.

    2012-07-01

    The U.S. Nuclear Regulatory Commission (NRC) established a Near-Term Task Force (NTTF) in response to Commission direction to conduct a systematic and methodical review of NRC processes and regulations to determine whether the agency should make additional improvements to its regulatory system and to make recommendations to the Commission for its policy direction, in light of the accident at the Fukushima Dai-ichi Nuclear Power Plant. The NTTF's review resulted in a set of recommendations that took a balanced approach to defense-in-depth as applied to low-likelihood, high-consequence events such as prolonged station blackout (SBO) resulting from severe natural phenomena. Part 50, Section 63, of Title 10 of the Code of Federal Regulations (CFR), 'Loss of All Alternating Current Power,' currently requires that each nuclear power plant must be able to cool the reactor core and maintain containment integrity for a specified duration of an SBO. The SBO duration and mitigation strategy for each nuclear power plant is site specific and is based on the robustness of the local transmission system and the transmission system operator's capability to restore offsite power to the nuclear power plant. With regard to SBO, the NTTF recommended that the NRC strengthen SBO mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events. The NTTF also recommended strengthening emergency preparedness for prolonged SBO and multi-unit events. These recommendations, taken together, are intended to clarify and strengthen US nuclear reactor safety regarding protection against and mitigation of the consequences of natural disasters and emergency preparedness during SBO. The focus of this paper is on the existing SBO requirements and NRC initiatives to strengthen SBO capability at all operating and new reactors to address prolonged SBO stemming from design-basis and beyond-design-basis external events. The NRC initiatives are intended to

  17. Calibration of radiation monitors at nuclear power plants. Final report

    SciTech Connect

    Boudreau, L.; Miller, A.D.; Naughton, M.D.

    1994-03-01

    This work was performed to provide guidance to the utilities in the primary and secondary calibration of the radiation monitoring systems (RMS) installed in nuclear power plants. These systems are installed in nuclear power plants to monitor ongoing processes, identify changing radiation fields, predict and limit personnel radiation exposures and measure and control discharge of radioactive materials to the environment. RMS are checked and calibrated on a continuing basis to ensure their precision and accuracy. This report discusses various approaches towards primary and secondary calibrations of the RMS equipment in light of accepted practices at typical power plants and recent interpretations of regulatory guidance. Detailed calibration techniques and overall system responses, trends, and practices are discussed. Industry, utility, and regulatory sources were contacted to create an overall consensus of the most reasonable approaches to optimizing the performance of this equipment.

  18. Nuclear driven water decomposition plant for hydrogen production

    NASA Technical Reports Server (NTRS)

    Parker, G. H.; Brecher, L. E.; Farbman, G. H.

    1976-01-01

    The conceptual design of a hydrogen production plant using a very-high-temperature nuclear reactor (VHTR) to energize a hybrid electrolytic-thermochemical system for water decomposition has been prepared. A graphite-moderated helium-cooled VHTR is used to produce 1850 F gas for electric power generation and 1600 F process heat for the water-decomposition process which uses sulfur compounds and promises performance superior to normal water electrolysis or other published thermochemical processes. The combined cycle operates at an overall thermal efficiency in excess of 45%, and the overall economics of hydrogen production by this plant have been evaluated predicated on a consistent set of economic ground rules. The conceptual design and evaluation efforts have indicated that development of this type of nuclear-driven water-decomposition plant will permit large-scale economic generation of hydrogen in the 1990s.

  19. Nuclear Plant Analyzer: an interactive TRAC/RELAP Power-Plant Simulation Program

    SciTech Connect

    Steinke, R.; Booker, C.; Giguere, P.; Liles, D.; Mahaffy, J.; Turner, M.; Wiley, R.

    1984-01-01

    The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis.

  20. Los Alamos Nuclear Plant Analyzer: an interactive power-plant simulation program

    SciTech Connect

    Steinke, R.; Booker, C.; Giguere, P.; Liles, D.R.; Mahaffy, J.H.; Turner, M.R.

    1984-01-01

    The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware-adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis.

  1. Operating nuclear plant feedback to ASME and French codes

    SciTech Connect

    Journet, J.; O`Donnell, W.J.

    1996-12-01

    The French have an advantage in nuclear plant operating experience feedback due to the highly centralized nature of their nuclear industry. There is only one utility in charge of design as well as operations (EDF) and only one reactor vendor (Framatome). The ASME Code has played a key role in resolving technical issues in the design and operation of nuclear plants since the inception of nuclear power. The committee structure of the Code brings an ideal combination of senior technical people with both broad and specialized experience to bear on complex how safe is safe enough technical issues. The authors now see an even greater role for the ASME Code in a proposed new regulatory era for the US nuclear industry. The current legalistic confrontational regulatory era has been quite destructive. There now appears to be a real opportunity to begin a new era of technical consensus as the primary means for resolving safety issues. This change can quickly be brought about by having the industry take operating plant problems and regulatory technical issues directly to the ASME Code for timely resolution. Surprisingly, there is no institution in the US nuclear industry with such a mandate. In fact, the industry is organized to feedback through the Nuclear Regulatory Commission issues which could be far better resolved through the ASME Code. Major regulatory benefits can be achieved by closing this loop and providing systematic interaction with the ASME Code. The essential elements of a new regulatory era and ideas for organizing US institutional industry responsibilities, taken from the French experience, are described in this paper.

  2. Potential drawbacks associated with agricultural irrigation with treated wastewaters from desalinated water origin and possible remedies.

    PubMed

    Lahav, Ori; Kochva, Malka; Tarchitzky, Jorge

    2010-01-01

    Over 90% of the water supplied in the coastal region in Israel in 2013 (600 Mm(3) y(-1)) will be from desalination plants. The wastewater generated from this water (>400 Mm(3) y(-1)) is planned, after proper treatment, to be reused for agricultural irrigation, making this low-salinity water the main agricultural-sector future water source. In this respect both the Mg(2 + ) concentration and the Sodium Adsorption Ratio value of the water are of concern. We show that the typical Na(+) concentration addition to wastewater (between approximately 100 and approximately 165 mg L(-1)) is much higher than the combined addition of Ca(2 + ) and Mg(2 + ) (between 0 and several mg L(-1)). Since desalinated water is typically supplied with low Ca(2 + ) and Mg(2 + ) concentrations ( approximately 35 and 0 mg L(-1) respectively), the treated wastewater is characterized by very low Mg(2 + ) concentrations, low salinity and very high SAR values, typically >6 and up to 10 (meq L(-1))(0.5). SAR values can be lowered by adding either Ca(2 + ) or Mg(2 + ) to desalinated water. Adding Mg(2 + ) is preferable from both health (minimizing cardiovascular disease hazards) and agriculture (inexpensive Mg fertilization) aspects. The low cost of Mg(2 + ) addition at the post-treatment stage of desalination plants corroborates the request for Mg(2 + ) addition in regions where treated wastewater from desalinated water origin is planned to be reused for irrigation. PMID:20453317

  3. Licensing retrofit incinerators at commercial nuclear power plants

    SciTech Connect

    Dodge, R.L.; Edwards, C.W.; Wilson, B.

    1983-01-01

    In order to determine whether or not a backfit incinerator could be licensed under the provisions of 10 CFR Part 50.59, Gilbert Associates, Inc., with support from the Department of Energy, prepared, on a generic basis, typical engineering design information, accident analysis data and other documentation necessary to apply to the Nuclear Regulatory Commission for a license to backfit a low-level radioactive waste incinerator in an operating nuclear power plant. The Department of Energy, serving in the role of a typical utility organization, submitted this generic report to the Nuclear Regulatory Commission for review and comment in a mock demonstration of the licensing process. The ultimate goal of this effort is to identify and resolve any safety issues associated with backfit incinerators so that a sufficient level of confidence in the licensability of backfit incinerators can be installed in nuclear utility management, and to encourage the industry to actually proceed with plans to install incinerators on a retrofit basis.

  4. Ecological aspects of the chernobyl nuclear plant disaster.

    PubMed

    Medvedev, Z A

    1986-07-01

    The partial meltdown of the 1000MW reactor in Chernobyl and the massive release of radionuclides into the environment is the first large-scale contamination of a geographically significant area by a power-generating civilian nuclear plant. It will have a long term effect on the human population, agriculture and the environment. Previous cases of accidental contamination of the environment on such a scale were connected with the disposal of reprocessed nuclear waste or the release of radioactivity from atmospheric and underground tests of nuclear weapons. One such contamination, which provides important lessons in the wake of the Chernobyl disaster, was linked with the explosion of the nuclear waste storage facility near Kyshtym in the Cheliabinsk region of the Soviet Union in 1958. It resulted in the creation of a special 'exclusion zone', resettlement of local populations and special construction projects designed to prevent the distribution of radioactivity over even larger areas. PMID:21227774

  5. In situ monitoring with Tradescantia around nuclear power plants.

    PubMed Central

    Ichikawa, S

    1981-01-01

    Highly sensitive mutational responses of the stamen-hair system of some Tradescantia clones heterozygous for flower color (blue/pink, the blue being dominant) to low-level radiation and chemical mutagens, as demonstrated in the last decade, seem to endorse this system to be the most promising biological tester for detecting the genetic effects of mutagens at low levels. Two triploid (thus sterile) clones, KU 7 and KU 9, have been established as those suitable for in situ monitoring of environmental mutagens. In situ monitoring with such Tradescantia clones was first tried in 1974 around a nuclear power plant in Japan, then has been repeated until 1979 around more nuclear plants. About 260,000 to 1,570,000 stamen hairs were observed per year per nuclear plant (about 12-million hairs in total), and the data of pink mutation frequency were analyzed statistically. Significantly increased mutation frequencies were observed and were correlated to the operation periods of the nuclear facilities and to predominant wind direction, but not to other environmental factors. Considering physical monitoring data of radiation dose in the air, internal exposure due to incorporation and concentration of man-made radioactive nuclides seems to be of a greater importance in increasing mutation incidence. PMID:7460878

  6. Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.

    SciTech Connect

    Palmiotti, G.; Cahalan, J.; Pfeiffer, P.; Sofu, T.; Taiwo, T.; Wei,T.; Yacout, A.; Yang, W.; Siegel, A.; Insepov, Z.; Anitescu, M.; Hovland,P.; Pereira, C.; Regalbuto, M.; Copple, J.; Willamson, M.

    2006-12-11

    This report presents requirements for advanced simulation of nuclear reactor and chemical processing plants that are of interest to the Global Nuclear Energy Partnership (GNEP) initiative. Justification for advanced simulation and some examples of grand challenges that will benefit from it are provided. An integrated software tool that has its main components, whenever possible based on first principles, is proposed as possible future approach for dealing with the complex problems linked to the simulation of nuclear reactor and chemical processing plants. The main benefits that are associated with a better integrated simulation have been identified as: a reduction of design margins, a decrease of the number of experiments in support of the design process, a shortening of the developmental design cycle, and a better understanding of the physical phenomena and the related underlying fundamental processes. For each component of the proposed integrated software tool, background information, functional requirements, current tools and approach, and proposed future approaches have been provided. Whenever possible, current uncertainties have been quoted and existing limitations have been presented. Desired target accuracies with associated benefits to the different aspects of the nuclear reactor and chemical processing plants were also given. In many cases the possible gains associated with a better simulation have been identified, quantified, and translated into economical benefits.

  7. New desalination concept: the solar evaporator and condenser system (SEACS)

    SciTech Connect

    ElDifrawi, A.; Yudow, B.; Grotheer, R.H.

    1981-01-01

    A new concept for a solar-powered, modular desalination plant has been developed. Plants will utilize a Solar Evaporator and Condenser System which provides a simple, reliable, and low-cost method for desalination. The system is an augmented solar still. Air drawn at low velocity over glazed solar ponds picks up moisture and transports it to a condenser where it picks up the latent heat of condensation. The warm seawater then flows by gravity through the ponds and is pumped over an evaporator pad at the air stream inlet. Most of the latent heat of condensation recovered at the condenser will provide additional moisture to the air stream. The cold brine will flow by gravity back to the sea. Product water from the condenser is stored for subsequent use by the community. The level of technology is low. Major components are low speed pumps and fans, heat exchangers, battery storage systems, and photovoltaic power panels. Plant capacity is determined by the number of modules in the plant. Total electric power requirements are anticipated to be as low as 1.2 to 1.5 kWhr/m/sup 3/ of product water. Cost of water production over the 20-year plant life is estimated to be $2.40/m/sup 3/. System is attractive in its simplicity, both from a construction and operation standpoint.

  8. Revised seismic and geologic siting regulations for nuclear power plants

    SciTech Connect

    Murphy, A.J.; Chokshi, N.C.

    1997-02-01

    The primary regulatory basis governing the seismic design of nuclear power plants is contained in Appendix A to Part 50, General Design Criteria for Nuclear Power Plants, of Title 10 of the Code of Federal Regulations (CFR). General Design Criteria (GDC) 2 defines requirements for design bases for protection against natural phenomena. GDC 2 states the performance criterion that {open_quotes}Structures, systems, and components important to safety shall be designed to withstand the effects of natural phenomena such as earthquakes, . . . without loss of capability to perform their safety functions. . .{close_quotes}. Appendix A to Part 100, Seismic and Geologic Siting Criteria for Nuclear Power Plants, has been the principal document which provided detailed criteria to evaluate the suitability of proposed sites and suitability of the plant design basis established in consideration of the seismic and geologic characteristics of the proposed sites. Appendix A defines required seismological and geological investigations and requirements for other design conditions such as soil stability, slope stability, and seismically induced floods and water waves, and requirements for seismic instrumentation. The NRC staff is in the process of revising Appendix A. The NRC has recently revised seismic siting and design regulations for future applications. These revisions are discussed in detail in this paper.

  9. Indicator system for advanced nuclear plant control complex

    DOEpatents

    Scarola, Kenneth; Jamison, David S.; Manazir, Richard M.; Rescorl, Robert L.; Harmon, Daryl L.

    1993-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

  10. Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

    SciTech Connect

    Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

    1983-02-01

    This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants.

  11. Desalination with carbon aerogel electrodes

    SciTech Connect

    Farmer, J.C.; Richardson, J.H.; Fix, D.V.

    1996-10-21

    An electrically regenerated electrosorption process known as carbon aerogel CDI was developed for continuously removing ionic impurities from aqueous streams. A salt solution flows in a channel formed by pairs of parallel carbon aerogel electrodes. Each electrode has a very high BET surface area and very low resistivity. After polarization, anions and cations are removed from electrolyte by the electric field and electrosorbed onto the carbon aerogel. The solution is thus separated into two streams, brine and water. Based on this, carbon aerogel CDI appears to be an energy-efficient alternative to evaporation, electrodialysis, and reverse osmosis. The energy required by this process is about QV/2, plus losses. Estimated energy requirement for sea water desalination is 18-27 Wh gal{sup -1}, depending on cell voltage and flow rate. The requirement for brackish water desalination is less, 1.2-2.5 Wh gal{sup -1} at 1600 ppM. This is assuming that stored electrical energy is reclaimed during regeneration.

  12. Educators benefit from energy information centers at nuclear plant sites

    SciTech Connect

    Krcma-Olson, L.

    1994-12-31

    While issues like dry storage, low-level waste storage, radiation, and license extension are projects with a technical perspective that need to be planned and executed at nuclear power plants, more difficult is the political perspective-gaining public acceptance to allow these projects to proceed. And public perception is predicated on the way plant neighbors and community members understand, accept, and trust the plants. Community educators are a key audience. Annually, U.S. information centers host about one million visitors; roughly half of them are school children who will soon join the ranks of voters, taxpayers, utility customers, and employees. Programs for educators and their classes vary from tours of centers that include computer games and video programs on energy-related topics to audio-visual presentations by center personnel. Some facilities have environmental activities such as hatcheries or nature trails, while others offer plant tours to specific age groups.

  13. Structures and construction of nuclear power plants on lunar surface

    NASA Astrophysics Data System (ADS)

    Shimizu, Katsunori; Kobatake, Masuhiko; Ogawa, Sachio; Kanamori, Hiroshi; Okada, Yasuhiko; Mano, Hideyuki; Takagi, Kenji

    1991-07-01

    The best structure and construction techniques of nuclear power plants in the severe environments on the lunar surface are studied. Facility construction types (functional conditions such as stable structure, shield thickness, maintainability, safety distances, and service life), construction conditions (such as construction methods, construction equipment, number of personnel, time required for construction, external power supply, and required transportation) and construction feasibility (construction method, reactor transportation between the moon and the earth, ground excavation for installation, loading and unloading, transportation, and installation, filling up the ground, electric power supply of plant S (300 kW class) and plant L (3000 kW class)) are outlined. Items to pay attention to in construction are (1) automation and robotization of construction; (2) cost reduction by multi functional robots; and (3) methods of supplying power to robots. A precast concrete block manufacturing plant is also outlined.

  14. Review of maintenance personnel practices at nuclear power plants

    SciTech Connect

    Chockie, A.D.; Badalamente, R.V.; Hostick, C.J.; Vickroy, S.C.; Bryant, J.L.; Imhoff, C.H.

    1984-05-01

    As part of the Nuclear Regulatory Commission (NRC) sponsored Maintenance Qualifications and Staffing Project, the Pacific Northwest Laboratory (PNL) has conducted a preliminary assessment of nuclear power plant (NPP) maintenance practices. As requested by the NRC, the following areas within the maintenance function were examined: personnel qualifications, maintenance training, overtime, shiftwork and staffing levels. The purpose of the assessment was to identify the primary safety-related problems that required further analysis before specific recommendations can be made on the regulations affecting NPP maintenance operations.

  15. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    SciTech Connect

    R. Doug Hamelin; G. O. Hayner

    2004-11-01

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  16. Scale inhibition in desalination applications: An overview

    SciTech Connect

    Amjad, Z.

    1996-12-01

    Desalination is a process in which dissolved impurities are removed from water. Three processes commonly employed include: distillation, electrodialysis, and reverse osmosis. This paper provides a general discussion of various desalination processes including advantages and disadvantages of each, performance comparisons, and problems encountered in the operation of the process. An in-depth discussion of fouling by mineral scales, colloidal matter, and metal hydroxides is also included. The role of the foulant control agent in treating a desalination system is also presented. Basic chemistry and efficacy of the individual scale inhibitors is summarized.

  17. Infrastructure development assistance modeling for nuclear power plant

    SciTech Connect

    Park, J. H.; Hwang, K.; Park, K. M.; Kim, S. W.; Lee, S. M.

    2012-07-01

    The purpose of this paper is to develop a model, a general frame to be utilized in assisting newcomer countries to start a nuclear power program. A nuclear power plant project involves technical complexity and high level of investment with long duration. Considering newcomers are mostly developing countries that lack the national infrastructure, key infrastructure issues may constitute the principal constraints to the development of a nuclear power program. In this regard, it is important to provide guidance and support to set up an appropriate infrastructure when we help them with the first launch of nuclear power plant project. To date, as a sole nuclear power generation company, KHNP has been invited many times to mentor or assist newcomer countries for their successful start of a nuclear power program since Republic of Korea is an exemplary case of a developing country which began nuclear power program from scratch and became a major world nuclear energy country in a short period of time. Through hosting events organized to aid newcomer countries' initiation of nuclear power projects, difficulties have been recognized. Each event had different contents according to circumstances because they were held as an unstructured and one-off thing. By developing a general model, we can give more adequate and effective aid in an efficient way. In this paper, we created a model to identify necessary infrastructures at the right stage, which was mainly based on a case of Korea. Taking into account the assistance we received from foreign companies and our own efforts for technological self-reliance, we have developed a general time table and specified activities required to do at each stage. From a donor's perspective, we explored various ways to help nuclear infrastructure development including technical support programs, training courses, and participating in IAEA technical cooperation programs on a regular basis. If we further develop the model, the next task would be to

  18. Optimization of membrane stack configuration in enlarged microbial desalination cells for efficient water desalination

    NASA Astrophysics Data System (ADS)

    Chen, Xi; Sun, Haotian; Liang, Peng; Zhang, Xiaoyuan; Huang, Xia

    2016-08-01

    Microbial desalination cells are considered a low-energy-consumption, clean technology to simultaneously purify wastewater and desalinate saline water by utilizing the in situ energy source contained in wastewater. To enhance desalination performance and achieve an optimal membrane stack configuration, an enlarged stacked microbial desalination cell (SMDC) has been developed and tested with 6-14 desalination cells. The cross-membrane area of the enlarged SMDC is 100 cm2. The anode and cathode volumes are both 200 mL. To reduce internal resistance, the width of desalination cells is kept as <0.5 mm. The optimal configuration with 10 desalination cells achieves the highest total desalination rate (TDR) of 423 mg/h and the highest charge transfer efficiency (CTE) of 836% when treating the 20 g/L NaCl solution. During this process, the junction potential across membranes increases from 0 to 374 mV, and occupies up to 74% of the total potential loss inside the SMDC. This shows that the SMDC used in this work achieves the highest TDR and CTE among the reported studies, and the junction potential should be effectively controlled to achieve the desired desalination performance in future practical applications.

  19. Nuclear power plant control room operators' performance research

    SciTech Connect

    Gray, L.H.; Haas, P.M.

    1984-01-01

    A research program is being conducted to provide information on the performance of nuclear power plant control room operators when responding to abnormal/emergency events in the plants and in full-scope training simulators. The initial impetus for this program was the need for data to assess proposed design criteria for the choice of manual versus automatic action for accomplishing safety-related functions during design basis accidents. The program also included studies of training simulator capabilities, of procedures and data for specifying and verifying simulator performance, and of methods and applications of task analysis.

  20. Application of AI technology to nuclear plant operations

    SciTech Connect

    Sackett, J.I.

    1988-01-01

    In this paper, applications of Artificial Intelligence (AI) Technology to nuclear-power plant operation are reviewed. AI Technology is advancing rapidly and in the next five years is expected to enjoy widespread application to operation, maintenance, management and safety. Near term emphasis on a sensor validation, scheduling, alarm handling, and expert systems for procedural assistance. Ultimate applications are envisioned to culminate in autonomous control such as would be necessary for a power system in space, where automatic control actions are taken based upon reasoned conclusions regarding plant conditions, capability and control objectives.

  1. Advanced maintenance, inspection & repair technology for nuclear power plants

    SciTech Connect

    Hinton, B.M.

    1994-12-31

    Maintenance, inspection, and repair technology for nuclear power plants is outlined. The following topics are discussed: technology for reactor systems, reactor refueling bridge, fuel inspection system, fuel shuffling software, fuel reconstitution, CEA/RCCA/CRA inspection, vessel inspection capabilities, CRDM inspection and repair, reactor internals inspection and repair, stud tensioning system, stud/nut cleaning system, EDM machining technology, MI Cable systems, core exit T/C nozzle assemblies, technology for steam generators, genesis manipulator systems, ECT, UT penetrant inspections, steam generator repair and cleaning systems, technology for balance of plant, heat exchangers, piping and weld inspections, and turbogenerators.

  2. Microbial-induced corrosion in nuclear power plant materials

    NASA Astrophysics Data System (ADS)

    Licina, George J.; Cubicciotti, Daniel

    1989-12-01

    The long construction times associated with nuclear plants and the large number of redundant or standby systems where water is allowed to remain stagnant for long periods of time produce conditions under which microbial-induced corrosion (MIC) can occur. Carbon and low-alloy steels, stainless steels and copper alloys are all susceptible to MIC in raw-water applications. Visual examination is particularly useful in performing preliminary assessments of MIC. If properly diagnosed, MIC can be effectively treated during plant construction, operation and temporary shutdowns.

  3. Recommendations for managing equipment aging in nuclear power plants

    SciTech Connect

    Gunther, W.E.; Subudhi, M.; Aggarwal, S.K.

    1992-12-01

    Research conducted under the auspices of the US NRC`s Nuclear Plant Aging Research (NPAR) Program has resulted in a large database of component and system operating, maintenance, and testing information. This database has been used to determine the susceptibility to aging of selected components, and the potential for equipment aging to impact plant safety and availability. it has also identified methods for detecting and mitigating component and system aging. This paper describes the research recommendations on electrical components which could be applied to maintenance, testing, and inspection activities to detect and mitigate the effects of aging prior to equipment failures.

  4. Recommendations for managing equipment aging in nuclear power plants

    SciTech Connect

    Gunther, W.E.; Subudhi, M. ); Aggarwal, S.K. )

    1992-01-01

    Research conducted under the auspices of the US NRC's Nuclear Plant Aging Research (NPAR) Program has resulted in a large database of component and system operating, maintenance, and testing information. This database has been used to determine the susceptibility to aging of selected components, and the potential for equipment aging to impact plant safety and availability. it has also identified methods for detecting and mitigating component and system aging. This paper describes the research recommendations on electrical components which could be applied to maintenance, testing, and inspection activities to detect and mitigate the effects of aging prior to equipment failures.

  5. 33 CFR 165.1155 - Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach, California.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... Nuclear Power Plant, Avila Beach, California. 165.1155 Section 165.1155 Navigation and Navigable Waters... Coast Guard District § 165.1155 Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach... surface to bottom, within a 2,000 yard radius of Diablo Canyon Nuclear Power Plant centered at position...

  6. 33 CFR 165.1155 - Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach, California.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Nuclear Power Plant, Avila Beach, California. 165.1155 Section 165.1155 Navigation and Navigable Waters... Coast Guard District § 165.1155 Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach... surface to bottom, within a 2,000 yard radius of Diablo Canyon Nuclear Power Plant centered at position...

  7. 76 FR 63541 - Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-13

    ... COMMISSION 10 CFR Parts 50 and 52 Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants... Hurricane and Hurricane Missiles for Nuclear Power Plants.'' This regulatory guide provides licensees and...- basis hurricane and design-basis hurricane-generated missiles that a nuclear power plant should...

  8. 78 FR 46255 - Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-31

    ... COMMISSION 10 CFR Part 51 RIN 3150-AI42 Revisions to Environmental Review for Renewal of Nuclear Power Plant... environmental effect of renewing the operating license of a nuclear power plant. Compliance with the provisions... nuclear power plant. This document is necessary to clarify and correct the revisions made to the...

  9. 78 FR 4477 - Review of Safety Analysis Reports for Nuclear Power Plants, Introduction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-22

    ... COMMISSION Review of Safety Analysis Reports for Nuclear Power Plants, Introduction AGENCY: Nuclear... subsection to NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power..., Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants:...

  10. 75 FR 11575 - James A. Fitzpatrick Nuclear Power Plant Environmental Assessment and Finding of No Significant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-11

    ... COMMISSION James A. Fitzpatrick Nuclear Power Plant Environmental Assessment and Finding of No Significant... Program for Nuclear Power Facilities Operating Prior to January 1, 1979,'' issued to Entergy Nuclear Operations, Inc. (the licensee), for the operation of the James A. FitzPatrick Nuclear Power Plant...

  11. 77 FR 24228 - Condition Monitoring Techniques for Electric Cables Used in Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-23

    ... COMMISSION Condition Monitoring Techniques for Electric Cables Used in Nuclear Power Plants AGENCY: Nuclear... Techniques for Electric Cables Used in Nuclear Power Plants.'' This guide describes techniques that the staff of the NRC considers acceptable for condition monitoring of electric cables for nuclear power...

  12. Expert systems and their use in nuclear power plants

    SciTech Connect

    Uhrig, R.E. |

    1990-12-31

    In the operation of a nuclear power plant, great quantities of numeric, symbolic, and quantitative information are handled by the reactor operators even during routine operation. The sheer magnitude of the number of process parameters and systems interactions poses difficulties for the operators, particularly during abnormal or emergency situations. Recovery from an upset situation depends upon the facility with which available raw data can be converted into, and assimilated as, meaningful knowledge. In operating a nuclear power plant, people are sometimes affected by fatigue, stress, emotion, and environmental factors that may have varying degrees of influence on their performance. Expert systems provide a method of removing some of the uncertainty from operator decisions by providing expert advice and rapid access to a large information base. 74 refs., 2 tabs.

  13. Deployment of the Topaz-II space nuclear power plant

    SciTech Connect

    Standley, V.H.; Wyant, F.J.; Polansky, G.F. )

    1993-01-01

    The Topaz-II is a 5-kW(electric) Russian space nuclear power plant. The power plant resembles a shuttlecock standing 3.9 m high and is 1.4 m in diameter at the base. The reactor is at the top, the radiation shield is in the middle, and the radiator is at the bottom. The whole system weighs 1 tonne. The reactor core is 37.5 cm long and 26 cm in diameter. It contains 37 core-length, single-cell thermionic fuel elements embedded in a ZrH moderator. Each thermionic fuel cell is a cylindrical emitter inside a cylindrical collector. Nuclear fuel inside the emitter raises the emitter's temperature.

  14. 78 FR 28245 - In the Matter of Southern Nuclear Operating Company, Farley Nuclear Plant, Units 1 and 2...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION [NRC-2013-0093; Docket No.: 50-348, 50-364; License No.: NPF-2, NPF-8; EA-12-145] In the Matter of Southern Nuclear Operating Company, Farley Nuclear Plant, Units 1 and 2; Confirmatory Order I Southern Nuclear Operating Company (SNC or Licensee)...

  15. Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.

    SciTech Connect

    OHara,J.; Higgins, J.; Brown, W.; Fink, R.

    2008-02-14

    This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and Training, Normal Operations Management, Disturbance and Emergency Management, Maintenance and Change Management, Plant Design and Construction, and HFE Methods and Tools. The issues where then prioritized into four categories using a 'Phenomena Identification and Ranking Table' methodology based on evaluations provided by 14 independent subject matter experts. The subject matter experts were knowledgeable in a variety of disciplines. Vendors, utilities, research organizations and regulators all participated. Twenty issues were categorized into the top priority category. This Brookhaven National Laboratory (BNL) technical report provides the detailed methodology, issue analysis, and results. A summary of the results of this study can be found in NUREG/CR-6947. The research performed for this project has identified a large number of human-performance issues for new control stations and new nuclear power plant designs. The information gathered in this project can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas through regulatory research. Addressing human-performance issues will provide the technical basis from which regulatory review guidance can be developed to meet these challenges. The availability of this review guidance will help set clear expectations for how the NRC staff will evaluate new designs, reduce regulatory uncertainty, and provide a well-defined path to new nuclear power plant licensing.

  16. New Generation Nuclear Plant (NGNP) Project, Preliminary Point Design

    SciTech Connect

    F. H. Southworth; P. E. MacDonald; A. M. Baxter; P. D. Bayless; J. M. Bolin; H. D. Gougar; R. L. Moore; A. M. Ougouag; M. B. Richards; R. L. Sant; J. W. Sterbentz; W. K. Terry

    2004-03-01

    This paper provides a preliminary assessment of two possible versions of the Next Generation Nuclear Plant (NGNP), a prismatic fuel type helium gas-cooled reactor and a pebblebed fuel helium gas reactor. Both designs will meet the three basic requirements that have been set for the NGNP: a coolant outlet temperature of 1000 C, passive safety, and a total power output consistent with that expected for commercial high-temperature gas-cooled reactors.

  17. Incidents at nuclear power plants caused by the human factor

    SciTech Connect

    Mashin, V. A.

    2012-09-15

    Psychological analysis of the causes of incorrect actions by personnel is discussed as presented in the report 'Methodological guidelines for analyzing the causes of incidents in the operation of nuclear power plants.' The types of incorrect actions and classification of the root causes of errors by personnel are analyzed. Recommendations are made for improvements in the psychological analysis of causes of incorrect actions by personnel.

  18. Decommissioning nuclear power plants - the wave of the future

    SciTech Connect

    Griggs, F.S. Jr.

    1994-12-31

    The paper discusses the project controls developed in the decommissioning of a nuclear power plant. Considerations are given to the contaminated piping and equipment that have to be removed and the spent and used fuel that has to be disposed of. The storage issue is of primary concern here. The cost control aspects and the dynamics of decommissioning are discussed. The effects of decommissioning laws on the construction and engineering firms are mentioned. 5 refs.

  19. Regression analysis of technical parameters affecting nuclear power plant performances

    SciTech Connect

    Ghazy, R.; Ricotti, M. E.; Trueco, P.

    2012-07-01

    Since the 80's many studies have been conducted in order to explicate good and bad performances of commercial nuclear power plants (NPPs), but yet no defined correlation has been found out to be totally representative of plant operational experience. In early works, data availability and the number of operating power stations were both limited; therefore, results showed that specific technical characteristics of NPPs were supposed to be the main causal factors for successful plant operation. Although these aspects keep on assuming a significant role, later studies and observations showed that other factors concerning management and organization of the plant could instead be predominant comparing utilities operational and economic results. Utility quality, in a word, can be used to summarize all the managerial and operational aspects that seem to be effective in determining plant performance. In this paper operational data of a consistent sample of commercial nuclear power stations, out of the total 433 operating NPPs, are analyzed, mainly focusing on the last decade operational experience. The sample consists of PWR and BWR technology, operated by utilities located in different countries, including U.S. (Japan)) (France)) (Germany)) and Finland. Multivariate regression is performed using Unit Capability Factor (UCF) as the dependent variable; this factor reflects indeed the effectiveness of plant programs and practices in maximizing the available electrical generation and consequently provides an overall indication of how well plants are operated and maintained. Aspects that may not be real causal factors but which can have a consistent impact on the UCF, as technology design, supplier, size and age, are included in the analysis as independent variables. (authors)

  20. Plant maintenance and advanced reactors, 2007

    SciTech Connect

    Agnihotri, Newal

    2007-09-15

    The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: A new day for energy in America; Committed to success more than ever, by Andy White, GE--Hitachi Nuclear Energy; Competitive technology for decades, by Steve Tritch, Westinghouse Electric Company; Pioneers of positive community relationship, by Exelon Nuclear; A robust design for 60-years, by Ray Ganthner, Areva; Aiming at no evacuation plants, by Kumiaki Moriya, Hitachi-GE Nuclear Energy, Ltd.; and, Desalination and hydrogen economy, by Dr. I. Khamis, International Atomic Energy Agency. Industry innovation articles in this issue are: Reactor vessel closure head project, by Jeff LeClair, Prairie Island Nuclear Generating Plant; and Submersible remote-operated vehicle, by Michael S. Rose, Entergy's Fitzpatrick Nuclear Station.

  1. Understanding the nature of nuclear power plant risk

    SciTech Connect

    Denning, R. S.

    2012-07-01

    This paper describes the evolution of understanding of severe accident consequences from the non-mechanistic assumptions of WASH-740 to WASH-1400, NUREG-1150, SOARCA and today in the interpretation of the consequences of the accident at Fukushima. As opposed to the general perception, the radiological human health consequences to members of the Japanese public from the Fukushima accident will be small despite meltdowns at three reactors and loss of containment integrity. In contrast, the radiation-related societal impacts present a substantial additional economic burden on top of the monumental task of economic recovery from the nonnuclear aspects of the earthquake and tsunami damage. The Fukushima accident provides additional evidence that we have mis-characterized the risk of nuclear power plant accidents to ourselves and to the public. The human health risks are extremely small even to people living next door to a nuclear power plant. The principal risk associated with a nuclear power plant accident involves societal impacts: relocation of people, loss of land use, loss of contaminated products, decontamination costs and the need for replacement power. Although two of the three probabilistic safety goals of the NRC address societal risk, the associated quantitative health objectives in reality only address individual human health risk. This paper describes the types of analysis that would address compliance with the societal goals. (authors)

  2. Epidemiological Evidence of Childhood Leukaemia Around Nuclear Power Plants

    PubMed Central

    Janiak, Marek K.

    2014-01-01

    A few reports of increased numbers of leukaemia cases (clusters) in children living in the vicinity of nuclear power plants (NPP) and other nuclear installations have triggered a heated debate over the possible causes of the disease. In this review the most important cases of childhood leukaemia clusters around NPPs are described and analyzed with special emphasis on the relationship between the environmental exposure to ionizing radiation and the risk of leukaemia. Since, as indicated, a lifetime residency in the proximity of an NPP does not pose any specific health risk to people and the emitted ionizing radiation is too small to cause cancer, a number of hypotheses have been proposed to explain the childhood leukaemia clusters. The most likely explanation for the clusters is ‘population mixing’, i.e., the influx of outside workers to rural regions where nuclear installations are being set up and where local people are not immune to pathogens brought along with the incomers. PMID:25249830

  3. Hydrogen Production from the Next Generation Nuclear Plant

    SciTech Connect

    M. Patterson; C. Park

    2008-03-01

    The Next Generation Nuclear Plant (NGNP) is a high temperature gas-cooled reactor that will be capable of producing hydrogen, electricity and/or high temperature process heat for industrial use. The project has initiated the conceptual design phase and when completed will demonstrate the viability of hydrogen generation using nuclear produced process heat. This paper explains how industry and the U.S. Government are cooperating to advance nuclear hydrogen technology. It also describes the issues being explored and the results of recent R&D including materials development and testing, thermal-fluids research, and systems analysis. The paper also describes the hydrogen production technologies being considered (including various thermochemical processes and high-temperature electrolysis).

  4. Understanding seismic design criteria for Japanese Nuclear Power Plants

    SciTech Connect

    Park, Y.J.; Hofmayer, C.H.; Costello, J.F.

    1995-04-01

    This paper summarizes the results of recent survey studies on the seismic design practice for nuclear power plants in Japan. The seismic design codes and standards for both nuclear as well as non-nuclear structures have been reviewed and summarized. Some key documents for understanding Japanese seismic design criteria are also listed with brief descriptions. The paper highlights the design criteria to determine the seismic demand and component capacity in comparison with U.S. criteria, the background studies which have led to the current Japanese design criteria, and a survey of current research activities. More detailed technical descriptions are presented on the development of Japanese shear wall equations, design requirements for containment structures, and ductility requirements.

  5. Regulation of nuclear shape and size in plants.

    PubMed

    Meier, Iris; Griffis, Anna Hn; Groves, Norman R; Wagner, Alecia

    2016-06-01

    Nuclear shape and size changes have long been used by cytopathologists to diagnose, stage, and prognose cancer. However, the underlying causalities and molecular mechanisms are largely unknown. The current eukaryotic tree of life groups eukaryotes into five supergroups, with all organisms between humans and yeast falling into the supergroup Opisthokonta. The emergence of model organisms with strong molecular genetic methodology in the other supergroups has recently facilitated a broader evolutionary approach to pressing biological questions. Here, we review what is known about the control of nuclear shape and size in the Archaeplastidae, the supergroup containing the higher plants. We discuss common themes as well as differences toward a more generalized model of how eukaryotic organisms regulate nuclear morphology. PMID:27030912

  6. Safety Second: the NRC and America's nuclear power plants

    SciTech Connect

    Adato, M.; MacKenzie, J.; Pollard, R.; Weiss, E.

    1987-01-01

    In 1975, Congress created the Nuclear Regulatory Commission (NRC). Its primary responsibility was to be the regulation of the nuclear power industry in order to maintain public health and safety. On March 28, 1979, in the worst commercial nuclear accident in US history, the plant at Three Mile Island began to leak radioactive material. How was Three Mile Island possible. Where was the NRC. This analysis by the Union of Concerned Scientists (UCS) of the NRC's first decade, points specifically to the factors that contributed to the accident at Three Mile Island. The NRC, created as a watchdog of the nuclear power industry, suffers from problems of mindset, says the UCS. The commission's problems are political, not technical; it repeatedly ranks special interests above the interest of public safety. This book critiques the NRC's performance in four specific areas. It charges that the agency has avoided tackling the most pervasive safety issues; has limited public participation in decision making and power plant licensing; has failed to enforce safety standards or conduct adequate regulation investigations; and, finally, has maintained a fraternal relationship with the industry it was created to regulate, serving as its advocate rather than it adversary. The final chapter offers recommendations for agency improvement that must be met if the NRC is to fulfill its responsibility for safety first.

  7. Multilayer Nanoporous Graphene Membranes for Water Desalination.

    PubMed

    Cohen-Tanugi, David; Lin, Li-Chiang; Grossman, Jeffrey C

    2016-02-10

    While single-layer nanoporous graphene (NPG) has shown promise as a reverse osmosis (RO) desalination membrane, multilayer graphene membranes can be synthesized more economically than the single-layer material. In this work, we build upon the knowledge gained to date toward single-layer graphene to explore how multilayer NPG might serve as a RO membrane in water desalination using classical molecular dynamic simulations. We show that, while multilayer NPG exhibits similarly promising desalination properties to single-layer membranes, their separation performance can be designed by manipulating various configurational variables in the multilayer case. This work establishes an atomic-level understanding of the effects of additional NPG layers, layer separation, and pore alignment on desalination performance, providing useful guidelines for the design of multilayer NPG membranes. PMID:26806020

  8. INTEGRATING DESALINATION AND AGRICULTURAL SALINITY CONTROL ALTERNATIVES

    EPA Science Inventory

    The cost-effectiveness relationships for various agricultural and desalination alternatives for controlling salinity in irrigation return flows are developed. Selection of optimal salinity management strategies on a river basin scale is described as a problem of integrating optim...

  9. The end of scarcity? Water desalination as the new cornucopia for Mediterranean Spain

    NASA Astrophysics Data System (ADS)

    March, Hug; Saurí, David; Rico-Amorós, Antonio M.

    2014-11-01

    In this paper we explore the new orientation taken by Spanish water policy since the beginning of the 21st century and very specifically the shift towards desalination as an alternative to other water supply options such as river regulation or inter-basin water transfers. Desalination has been seen as the cure for everything that dams and inter-basin water transfers were unable to solve, including droughts, scarcities, social conflicts, environmental impacts, and political rivalries among the different Spanish regions. Desalination also means a new and powerful element in water planning and management that could provide water for the continuous expansion of the urban and tourist growth machine in Mediterranean Spain and thus relax possible water constraints on this growth. However, by 2012 most new desalination plants along the Mediterranean coast remained almost idle. Focusing on the case of the Mancomunidad de los Canales del Taibillla in South-eastern Spain, our aim is to develop a critical, integrated and reflexive perspective on the use of desalination as a source of water for urban and regional growth.

  10. Validation of seismic probabilistic risk assessments of nuclear power plants

    SciTech Connect

    Ellingwood, B.

    1994-01-01

    A seismic probabilistic risk assessment (PRA) of a nuclear plant requires identification and information regarding the seismic hazard at the plant site, dominant accident sequences leading to core damage, and structure and equipment fragilities. Uncertainties are associated with each of these ingredients of a PRA. Sources of uncertainty due to seismic hazard and assumptions underlying the component fragility modeling may be significant contributors to uncertainty in estimates of core damage probability. Design and construction errors also may be important in some instances. When these uncertainties are propagated through the PRA, the frequency distribution of core damage probability may span three orders of magnitude or more. This large variability brings into question the credibility of PRA methods and the usefulness of insights to be gained from a PRA. The sensitivity of accident sequence probabilities and high-confidence, low probability of failure (HCLPF) plant fragilities to seismic hazard and fragility modeling assumptions was examined for three nuclear power plants. Mean accident sequence probabilities were found to be relatively insensitive (by a factor of two or less) to: uncertainty in the coefficient of variation (logarithmic standard deviation) describing inherent randomness in component fragility; truncation of lower tail of fragility; uncertainty in random (non-seismic) equipment failures (e.g., diesel generators); correlation between component capacities; and functional form of fragility family. On the other hand, the accident sequence probabilities, expressed in the form of a frequency distribution, are affected significantly by the seismic hazard modeling, including slopes of seismic hazard curves and likelihoods assigned to those curves.

  11. Proactive Management of Materials Degradation for Nuclear Power Plant Systems

    SciTech Connect

    Bond, Leonard J.; Taylor, Theodore T.; Doctor, Steven R.; Hull, Amy; Malik, Shah

    2008-09-01

    There are approximately 440 operating reactors in the global nuclear power plant (NPP) fleet, and these have an average age greater than 20 years. These NPPs had design lives of 30 or 40 years. The United States is currently implementing license extensions of 20 years on many plants and consideration is now being given to the concept of “life-beyond-60,” a further period of license extension from 60 to 80 years, and potentially longer. In almost all countries with NPPs, authorities are looking at some form of license renewal program. There is a growing urgency as a number of plants face either approvals for license extension or shut down, which will require deployment of new power plants. In support of NPP license extension over the past decade, various national and international programs have been initiated. This paper reports part of the work performed in support of the U.S. Nuclear Regulatory Commission’s (NRC’s) Proactive Management of Materials Degradation (PMMD) program. The paper concisely explains the basic principles of PMMD, its relationship to advanced diagnostics and prognostics and provides an assessment of some the technical gaps in PMMD and prognostics that need to be addressed.

  12. Consider zig-zag impeller for desalination projects

    SciTech Connect

    O'Keefe, W.

    1993-10-01

    This article describes the application of a novel pump with a zig-zag impeller that is suited for vapor condensation. The pump is proposed to be used as the vapor condensation portion of a vapor desalination plant. Small scale testing is currently under way. No additional heat needs to be added to the seawater which boils by application of a vacuum to the desalting tank. The zig-zag pump then condenses the resulting pure water vapor and pumps it to a holding tank.

  13. CSP cogeneration of electricity and desalinated water at the Pentakomo field facility

    NASA Astrophysics Data System (ADS)

    Papanicolas, C. N.; Bonanos, A. M.; Georgiou, M. C.; Guillen, E.; Jarraud, N.; Marakkos, C.; Montenon, A.; Stiliaris, E.; Tsioli, E.; Tzamtzis, G.; Votyakov, E. V.

    2016-05-01

    The Cyprus Institute's Pentakomo Field Facility (PFF) is a major infrastructure for research, development and testing of technologies relating to concentrated solar power (CSP) and solar seawater desalination. It is located at the south coast of Cyprus near the sea and its environmental conditions are fully monitored. It provides a test facility specializing in the development of CSP systems suitable for island and coastal environments with particular emphasis on small units (<25 MWth) endowed with substantial storage, suitable for use in isolation or distributed in small power grids. The first major experiment to take place at the PFF concerns the development of a pilot/experimental facility for the co-generation of electricity and desalinated seawater from CSP. Specifically, the experimental plant consists of a heliostat-central receiver system for solar harvesting, thermal energy storage in molten salts followed by a Rankine cycle for electricity production and a multiple-effect distillation (MED) unit for desalination.

  14. NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER

    SciTech Connect

    Mark Holbrook

    2010-09-01

    The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) plant capable of producing the electricity and high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) application process, as recommended in the Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy. NRC licensing of the NGNP plant utilizing this process will demonstrate the efficacy of licensing future HTGRs for commercial industrial applications. This white paper is one in a series of submittals that will address key generic issues of the COL priority licensing topics as part of the process for establishing HTGR regulatory requirements.

  15. The Meteorological Monitoring program at a former nuclear weapons plant

    SciTech Connect

    Maxwell, D.R.; Bowen, B.M.

    1994-02-01

    The purpose of the Meteorological Monitoring program at Rocky Flats Plant (RFP) is to provide meteorological information for use in assessing the transport, and diffusion, and deposition of effluent actually or potentially released into the atmosphere by plant operations. Achievement of this objective aids in protecting health and safety of the public, employees, and environment, and directly supports Emergency Response programs at RFP. Meteorological information supports the design of environmental monitoring networks for impact assessments, environmental surveillance activities, remediation activities, and emergency responses. As the mission of the plant changes from production of nuclear weapons parts to environmental cleanup and economic development, smaller releases resulting from remediation activities become more likely. These possible releases could result from airborne fugitive dust, evaporation from collection ponds, or grass fires.

  16. Aging management guideline for commercial nuclear power plants-pumps

    SciTech Connect

    Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D.

    1994-03-01

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  17. Work practices, fatigue, and nuclear power plant safety performance.

    PubMed

    Baker, K; Olson, J; Morisseau, D

    1994-06-01

    This paper focuses on work practices that may contribute to fatigue-induced performance decrements in the commercial nuclear power industry. Specifically, the amount of overtime worked by operations, technical, and maintenance personnel and the 12-h operator shift schedule are studied. Although overtime for all three job categories was fairly high at a number of plants, the analyses detected a clear statistical relationship only between operations overtime and plant safety performance. The results for the 12-h operator shift schedule were ambiguous. Although the 12-h operator shift schedule was correlated with operator error, it was not significantly related to the other five safety indicators. This research suggests that at least one of the existing work practices--the amount of operator overtime worked at some plants--represents a safety concern in this industry; however, further research is required before any definitive conclusions can be drawn. PMID:8070790

  18. Desalination apparatus with power generation

    SciTech Connect

    Humiston, G.F.

    1981-11-24

    An apparatus for desalinating ocean waters by distillation and furnishing electrical power, utilizes an evaporator, barometric leg conduits, a closed condenser, ocean water circulating circuits for circulating warm surface water to the evaporator and cool ocean water to the condenser and using the mass flow of vapors evolved from the evaporator to drive a prime mover which in turn drives an electrical generator. A portion of the electrical power so-generated is used to control the operation of respective pumps and valves in the apparatus. The liquid level of the condensate water is controlled in a barometric leg condensate outlet conduit. The system is also provided with a vacuum pump at least for initiating a reduced pressure and particle separator channel means is provided to prevent liquid entrainment in the condenser.

  19. Nuclear power plant control room operator control and monitoring tasks

    SciTech Connect

    Bovell, C.R.; Beck, M.G.; Carter, R.J.

    1998-07-01

    Oak Ridge National Laboratory is conducting a research project the purpose of which is to develop the technical bases for regulatory review criteria for use in evaluating the safety implications of human factors associated with the use of artificial intelligence and expert systems, and with advanced instrumentation and control (I and C) systems in nuclear power plants (NPP). This report documents the results from Task 8 of that project. The primary objectives of the task was to identify the scope and type of control and monitoring tasks now performed by control-room operators. Another purpose was to address the types of controls and safety systems needed to operate the nuclear plant. The final objective of Task 8 was to identify and categorize the type of information and displays/indicators required to monitor the performance of the control and safety systems. This report also discusses state-of-the-art controls and advanced display devices which will be available for use in control-room retrofits and in control room of future plants. The fundamental types of control and monitoring tasks currently conducted by operators can be divided into four classifications: function monitoring tasks, control manipulation tasks, fault diagnostic tasks, and administrative tasks. There are three general types of controls used in today`s NPPs, switches, pushbuttons, and analog controllers. Plant I and C systems include components to achieve a number of safety-related functions: measuring critical plant parameters, controlling critical plant parameters within safety limits, and automatically actuating protective devices if safe limits are exceeded. The types of information monitored by the control-room operators consist of the following parameters: pressure, fluid flow and level, neutron flux, temperature, component status, water chemistry, electrical, and process and area radiation. The basic types of monitoring devices common to nearly all NPP control rooms include: analog meters

  20. Environmental concerns of desalinating seawater using reverse osmosis.

    PubMed

    Tularam, Gurudeo Anand; Ilahee, Mahbub

    2007-08-01

    This Critical Review on environmental concerns of desalination plants suggests that planning and monitoring stages are critical aspects of successful management and operation of plants. The site for the desalination plants should be selected carefully and should be away from residential areas particularly for forward planning for possible future expansions. The concerning issues identified are noise pollution, visual pollution, reduction in recreational fishing and swimming areas, emission of materials into the atmosphere, the brine discharge and types of disposal methods used are the main cause of pollution. The reverse osmosis (RO) method is the preferred option in modern times especially when fossil fuels are becoming expensive. The RO has other positives such as better efficiency (30-50%) when compared with distillation type plants (10-30%). However, the RO membranes are susceptible to fouling and scaling and as such they need to be cleaned with chemicals regularly that may be toxic to receiving waters. The input and output water in desalination plants have to be pre and post treated, respectively. This involves treating for pH, coagulants, Cl, Cu, organics, CO(2), H(2)S and hypoxia. The by-product of the plant is mainly brine with concentration at times twice that of seawater. This discharge also includes traces of various chemicals used in cleaning including any anticorrosion products used in the plant and has to be treated to acceptable levels of each chemical before discharge but acceptable levels vary depending on receiving waters and state regulations. The discharge of the brine is usually done by a long pipe far into the sea or at the coastline. Either way the high density of the discharge reaches the bottom layers of receiving waters and may affect marine life particularly at the bottom layers or boundaries. The longer term effects of such discharge concentrate has not been documented but it is possible that small traces of toxic substances used in the

  1. From the first nuclear power plant to fourth-generation nuclear power installations [on the 60th anniversary of the World's First nuclear power plant

    NASA Astrophysics Data System (ADS)

    Rachkov, V. I.; Kalyakin, S. G.; Kukharchuk, O. F.; Orlov, Yu. I.; Sorokin, A. P.

    2014-05-01

    Successful commissioning in the 1954 of the World's First nuclear power plant constructed at the Institute for Physics and Power Engineering (IPPE) in Obninsk signaled a turn from military programs to peaceful utilization of atomic energy. Up to the decommissioning of this plant, the AM reactor served as one of the main reactor bases on which neutron-physical investigations and investigations in solid state physics were carried out, fuel rods and electricity generating channels were tested, and isotope products were bred. The plant served as a center for training Soviet and foreign specialists on nuclear power plants, the personnel of the Lenin nuclear-powered icebreaker, and others. The IPPE development history is linked with the names of I.V. Kurchatov, A.I. Leipunskii, D.I. Blokhintsev, A.P. Aleksandrov, and E.P. Slavskii. More than 120 projects of various nuclear power installations were developed under the scientific leadership of the IPPE for submarine, terrestrial, and space applications, including two water-cooled power units at the Beloyarsk NPP in Ural, the Bilibino nuclear cogeneration station in Chukotka, crawler-mounted transportable TES-3 power station, the BN-350 reactor in Kazakhstan, and the BN-600 power unit at the Beloyarsk NPP. Owing to efforts taken on implementing the program for developing fast-neutron reactors, Russia occupied leading positions around the world in this field. All this time, IPPE specialists worked on elaborating the principles of energy supertechnologies of the 21st century. New large experimental installations have been put in operation, including the nuclear-laser setup B, the EGP-15 accelerator, the large physical setup BFS, the high-pressure setup SVD-2; scientific, engineering, and technological schools have been established in the field of high- and intermediate-energy nuclear physics, electrostatic accelerators of multicharge ions, plasma processes in thermionic converters and nuclear-pumped lasers, physics of compact

  2. Microbial desalination cells for improved performance in wastewater treatment, electricity production, and desalination.

    PubMed

    Luo, Haiping; Xu, Pei; Roane, Timberley M; Jenkins, Peter E; Ren, Zhiyong

    2012-02-01

    The low conductivity and alkalinity in municipal wastewater significantly limit power production from microbial fuel cells (MFCs). This study integrated desalination with wastewater treatment and electricity production in a microbial desalination cell (MDC) by utilizing the mutual benefits among the above functions. When using wastewater as the sole substrate, the power output from the MDC (8.01 W/m(3)) was four times higher than a control MFC without desalination function. In addition, the MDC removed 66% of the salts and improved COD removal by 52% and Coulombic efficiency by 131%. Desalination in MDCs improved wastewater characteristics by increasing the conductivity by 2.5 times and stabilizing anolyte pH, which therefore reduced system resistance and maintained microbial activity. Microbial community analysis revealed a more diverse anode microbial structure in the MDC than in the MFC. The results demonstrated that MDC can serve as a viable option for integrated wastewater treatment, energy production, and desalination. PMID:22178493

  3. Paradigm for expert display systems in nuclear plant and elsewhere

    SciTech Connect

    Gabriel, J.R.

    1986-02-01

    Display of relevant data concerning plant operation has been a concern of the nuclear industry from its beginnings. Since the incident at Three Mile Island, this matter has had much careful scrutiny. L. Beltracchi, in particular, has originated a sequence of important steps to improve the operator's ability to recognize plant states and their changes. In the early 1980's, Beltracchi (1983, 1984) proposed a display based on the Rankine cycle for light water reactors. More recently, in an unpublished work (1986b), he described an extension that includes a small, rule-based system in the display program, drawing inferences about plant operation from sensor readings, and displaying those inferences on the Rankine display. Our paper examines Beltracchi's rule-based display from the perspective of knowledge bases. Earlier (Gabriel, 1983) we noted that analytical models of system behavior are just as much a knowledge base as are the rules of a conventional expert system. The problem of finding useful displays for a complex plant is discussed from this perspective. We then present a paradigm for developing designs with properties similar to those in Beltracchi's Rankine cycle display. Finally, to clarify the issue, we give a small example from an imaginary plant.

  4. Simplified tornado depressurization design methods for nuclear power plants

    SciTech Connect

    Howard, N.M.; Krasnopoler, M.I.

    1983-05-01

    A simplified approach for the calculation of tornado depressurization effects on nuclear power plant structures and components is based on a generic computer depressurization analysis for an arbitrary single volume V connected to the atmosphere by an effective vent area A. For a given tornado depressurization transient, the maximum depressurization ..delta..P of the volume was found to depend on the parameter V/A. The relation between ..delta..P and V/A can be represented by a single monotonically increasing curve for each of the three design-basis tornadoes described in the U.S. Nuclear Regulatory Commission's Regulatory Guide 1.76. These curves can be applied to most multiple-volume nuclear power plant structures by considering each volume and its controlling vent area. Where several possible flow areas could be controlling, the maximum value of V/A can be used to estimate a conservative value for ..delta..P. This simplified approach was shown to yield reasonably conservative results when compared to detailed computer calculations of moderately complex geometries. Treatment of severely complicated geometries, heating and ventilation systems, and multiple blowout panel arrangements were found to be beyond the limitations of the simplified analysis.

  5. Tracing airborne particles after Japan's nuclear plant explosion

    NASA Astrophysics Data System (ADS)

    Takemura, Toshihiko; Nakamura, Hisashi; Nakajima, Teruyuki

    2011-11-01

    The powerful Tohoku earthquake and consequent tsunami that occurred off the east coast of Japan on 11 March 2011 devastated dozens of coastal cities and towns, causing the loss of more than 15,000 lives and leaving close to 4000 people still missing. Although nuclear reactors at the Fukushima Daiichi Nuclear Power Plant, located on the Pacific coast, stopped their operation automatically upon the occurrence of the Mw 9.0 quake [Showstack, 2011], the cooling system for nuclear fuel broke down. From 12 to 16 March, vapor and hydrogen blasts destroyed the buildings that had contained the reactors, resulting in the release into the atmosphere of radioactive materials such as sulfur-35, iodine-131, cesium-134, and cesium-137, which collectively can cause harmful health effects such as tissue damage and increased risk of cancer (particularly in children), depending on dose. Most of those materials emitted from the power plant rained out onto the grounds within its vicinity and forced tens of thousands within a 20-kilometer radius to evacuate (residents to the northwest of the site within about 40 kilometers also were moved from their homes). Some of the radioactive materials were transported and then detected at such distant locations as North America and Europe, although the level of radiation dose was sufficiently low not to affect human health in any significant manner.

  6. Remote monitoring of nuclear power plants in Baden-Wuerttemberg.

    PubMed

    Neff, U; Müller, U; Mandel, C; Coutinho, P; Aures, R; Grimm, C; Hagmann, M; Wilbois, T; Ren, Y

    2014-08-01

    As part of its responsibilities as nuclear supervisory authority, the Ministry of the Environment, Climate Protection and the Energy Sector Baden-Wuerttemberg (UM) operates a computer-based system for remote monitoring of nuclear power plants (NPPs) (KFUe, Kernreaktor-Fernüberwachung). In addition to the Baden-Wuerttemberg NPPs located at Philippsburg, Neckarwestheim and the disused Obrigheim, those in foreign locations close to the border area, i.e. Fessenheim in France, and Leibstadt and Beznau in Switzerland, are monitored. The KFUe system provides several methods to evaluate and present the measured data as well as to ensure compliance of threshold limits and safety objectives. For the UM, it serves as an instrument of the nuclear supervision. In case of a radioactive release, the authorities responsible for civil protection can use dispersion calculations in order to identify potentially affected areas and to initiate protective measures for the population. Beyond the data collected at the plant sites, various international radiation and meteorological measuring networks are integrated in the KFUe. The State Institute for Environment, Measurements and Nature Protection (LUBW), the technical operator of the KFUe, runs its own special monitoring network for ambient gamma dose rate and nuclide specific activity concentration measurements in the vicinity of each NPP. This article gives an overview of the solution to combine data of different sources on a single screen: dose rate networks, dose rate traces measured by car, airborne gamma spectra of helicopters, mobile dose rate probes, grid data of weather forecasts, dispersion calculations, etc. PMID:24525946

  7. Consequences of the nuclear power plant accident at Chernobyl

    SciTech Connect

    Ginzburg, H.M.; Reis, E. )

    1991-01-01

    The Chernobyl Nuclear Power Plant accident, in the Ukrainian Soviet Socialist Republic (SSR), on April 26, 1986, was the first major nuclear power plant accident that resulted in a large-scale fire and subsequent explosions, immediate and delayed deaths of plant operators and emergency service workers, and the radioactive contamination of a significant land area. The release of radioactive material, over a 10-day period, resulted in millions of Soviets, and other Europeans, being exposed to measurable levels of radioactive fallout. Because of the effects of wind and rain, the radioactive nuclide fallout distribution patterns are not well defined, though they appear to be focused in three contiguous Soviet Republics: the Ukrainian SSR, the Byelorussian SSR, and the Russian Soviet Federated Socialist Republic. Further, because of the many radioactive nuclides (krypton, xenon, cesium, iodine, strontium, plutonium) released by the prolonged fires at Chernobyl, the long-term medical, psychological, social, and economic effects will require careful and prolonged study. Specifically, studies on the medical (leukemia, cancers, thyroid disease) and psychological (reactive depressions, post-traumatic stress disorders, family disorganization) consequences of continued low dose radiation exposure in the affected villages and towns need to be conducted so that a coherent, comprehensive, community-oriented plan may evolve that will not cause those already affected any additional harm and confusion.

  8. Just In-Time Maintenance of Nuclear Power Plants

    SciTech Connect

    DR. Alexander G. Parlos

    2002-01-22

    The goal of this project has been to develop and demonstrate the feasibility of a new technology for maintenance engineering: a Just-In-Time Maintenance (JITM) system for rotating machines. The JITM system is based on several key developments at Texas A and M over the past ten years in emerging intelligent information technologies, which if integrated into a single system could provide a revolutionary approach in the way maintenance is performed. Rotating machines, such as induction motors, range from a few horse power (hp) to several thousand hp in size, and they are widely used in nuclear power plants and in other industries. Forced outages caused by induction motor failures are the reason for as much as 15% - 40% of production costs to be attributable to maintenance, whereas plant shutdowns caused by induction motor failures result in daily financial losses to the utility and process industries of $1 M or more. The basic components of the JITM system are the available machine sensors, that is electric current sensors and accelerometers, and the computational algorithms used in the analysis and interpretation of the occurring incipient failures. The JITM system can reduce the costs attributable to maintenance by about 40% and it can lower the maintenance budgets of power and process plants by about 35%, while requiring no additional sensor installation. As a result, the JITM system can improve the competitiveness of US nuclear utilities at minimal additional cost.

  9. Recent Trends in the Adequacy of Nuclear Plant Decommissioning Funding

    SciTech Connect

    Williams, D. G.

    2002-02-26

    Concerned about the potential cost and sufficiency of funds to decommission the nation's nuclear power plants, the Congress asked the U.S. General Accounting Office (GAO) to assess the adequacy, as of December 31, 1997, of electric utilities'; funds to eventually decommission their plants. GAO's report (GAO/RCED-99-75) on this issue addressed three alternative assumption scenarios--baseline (most likely), optimistic, and pessimistic; and was issued in May 1999. This paper updates GAO's baseline assessment of fund adequacy in 1997, and extends the analysis through 2000. In 2000, we estimate that the present value cost to decommission the nation's nuclear plants is about $35 billion; utility fund balances are about $29 billion. Both our two measures of funding adequacy for utilities are on average not only much above ideal levels, but also overall have greatly improved since 1997. However, certain utilities still show less than ideal fund balances and annual contributions. We suggest that the range of these results among the individual utilities is a more important policy measure to assess the adequacy of decommissioning funding than is the funding adequacy for the industry as a whole.

  10. Consequences of the nuclear power plant accident at Chernobyl.

    PubMed Central

    Ginzburg, H M; Reis, E

    1991-01-01

    The Chernobyl Nuclear Power Plant accident, in the Ukrainian Soviet Socialist Republic (SSR), on April 26, 1986, was the first major nuclear power plant accident that resulted in a large-scale fire and subsequent explosions, immediate and delayed deaths of plant operators and emergency service workers, and the radioactive contamination of a significant land area. The release of radioactive material, over a 10-day period, resulted in millions of Soviets, and other Europeans, being exposed to measurable levels of radioactive fallout. Because of the effects of wind and rain, the radioactive nuclide fallout distribution patterns are not well defined, though they appear to be focused in three contiguous Soviet Republics: the Ukrainian SSR, the Byelorussian SSR, and the Russian Soviet Federated Socialist Republic. Further, because of the many radioactive nuclides (krypton, xenon, cesium, iodine, strontium, plutonium) released by the prolonged fires at Chernobyl, the long-term medical, psychological, social, and economic effects will require careful and prolonged study. Specifically, studies on the medical (leukemia, cancers, thyroid disease) and psychological (reactive depressions, post-traumatic stress disorders, family disorganization) consequences of continued low dose radiation exposure in the affected villages and towns need to be conducted so that a coherent, comprehensive, community-oriented plan may evolve that will not cause those already affected any additional harm and confusion. Images p38-a p38-b PMID:1899937

  11. Guidelines for inservice testing at nuclear power plants

    SciTech Connect

    Campbell, P.

    1995-04-01

    The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code.

  12. Reducing Risk for the Next Generation Nuclear Plant

    SciTech Connect

    John M. Beck II; Harold J. Heydt; Emmanuel O. Opare; Kyle B. Oswald

    2010-07-01

    The Next Generation Nuclear Plant (NGNP) Project, managed by the Idaho National Laboratory (INL), is directed by the Energy Policy Act of 2005, to research, develop, design, construct, and operate a prototype forth generation nuclear reactor to meet the needs of the 21st Century. As with all large projects developing and deploying new technologies, the NGNP has numerous risks that need to be identified, tracked, mitigated, and reduced in order for successful project completion. A Risk Management Plan (RMP) was created to outline the process the INL is using to manage the risks and reduction strategies for the NGNP Project. Integral to the RMP is the development and use of a Risk Management System (RMS). The RMS is a tool that supports management and monitoring of the project risks. The RMS does not only contain a risk register, but other functionality that allows decision makers, engineering staff, and technology researchers to review and monitor the risks as the project matures.

  13. [Accidents of the Fukushima Daiichi Nuclear Power Plants and future].

    PubMed

    Hoshi, Masaharu

    2012-01-01

    A massive earthquake of magnitude 9 terribly happened far out at sea of Tohoku area on 11 March, 2011. After this earthquake the hugest tsunami in the history came to the hundreds km of the seashore of Tohoku area. Due to this tsunami all of the four nuclear power plants of Fukushima Daiichi lost every electric power and, soon after this, loss nuclear fuels from number 1 to 3 reactors melt through their power containers. According to this phenomena, large amount of the radio-activities have been released in the air. There were some releases but major contaminations happened at the time of the two releases in the morning of 15 March, 2011. Due to this, to the direction of the northwest until the Iitate Village over 30km zone was contaminated. In this paper I explain the time course of the accidents and that how contaminated. PMID:24568025

  14. COMMERCIAL UTILITY PERSPECTIVES ON NUCLEAR POWER PLANT CONTROL ROOM MODERNIZATION

    SciTech Connect

    Jeffrey C. Joe; Ronald L. Boring; Julius J. Persensky

    2012-07-01

    Commercial nuclear power plants (NPPs) in the United States need to modernize their main control rooms (MCR). Many NPPs have done partial upgrades with some success and with some challenges. The Department of Energy’s (DOE) Light Water Reactor Sustainability (LWRS) Program, and in particular the Advanced Instrumentation and Controls (I&C) and Information Systems Technologies Research and Development (R&D) Pathway within LWRS, is designed to assist commercial nuclear power industry with their MCR modernization efforts. As part of this framework, a survey was issued to utility representatives of the LWRS Program Advanced Instrumentation, Information, and Control Systems/Technologies (II&C) Utility Working Group to obtain their views on a range of issues related to MCR modernization, including: drivers, barriers, and technology options, and the effects these aspects will have on concepts of operations, modernization strategies, and staffing. This paper summarizes the key survey results and discusses their implications.

  15. Improved tritium monitoring at the Pantex Nuclear Weapons Plant

    SciTech Connect

    Brain, W.F.; Click, C.N.; Griffis, D.W.

    1995-12-31

    This paper describes the development of a system capable of sampling ambient levels of both elemental and oxidized tritium in ambient air at the US Department of Energy`s Pantex Nuclear Weapons Plant. The system of monitors uses a combination of commercial laboratory equipment and custom fabricated components. Problems inherent in tritium sampling, and those specific to weather extremes in Texas, were identified and researched. Experience with the sampling network is still limited, but concentrations of oxidized tritium are presently comparable to the original sampling network.

  16. Radiation fields and dose assessments in Korean nuclear power plants.

    PubMed

    Kim, Hee Geun; Kong, Tae Young; Jeong, Woo Tae; Kim, Seok Tae

    2011-07-01

    In the primary systems of nuclear power plants (NPPs), various radionuclides including fission products and corrosion products are generated due to the complex water chemistry conditions. In particular, (3)H, (14)C, (58)Co, (60)Co, (137)Cs, and (131)I are important or potential radionuclides with respect to dose assessment for workers and the management of radioactive effluents or dose assessment for the public. In this paper, the dominant contributors to the dose for workers and the public were reviewed and the process of dose assessment attributable to those contributors was investigated. Furthermore, an analysis was carried out on some examples of dose to workers during NPP operation. PMID:21498858

  17. Fiber optic sensors for nuclear power plant applications

    SciTech Connect

    Kasinathan, Murugesan; Sosamma, Samuel; BabuRao, Chelamchala; Murali, Nagarajan; Jayakumar, Tammana

    2012-05-17

    Studies have been carried out for application of Raman Distributed Temperature Sensor (RDTS) in Nuclear Power Plants (NPP). The high temperature monitoring in sodium circuits of Fast Breeder Reactor (FBR) is important. It is demonstrated that RDTS can be usefully employed in monitoring sodium circuits and in tracking the percolating sodium in the surrounding insulation in case of any leak. Aluminum Conductor Steel Reinforced (ACSR) cable is commonly used as overhead power transmission cable in power grid. The suitability of RDTS for detecting defects in ACSR overhead power cable, is also demonstrated.

  18. Early Site Permit Demonstration Program: Nuclear Power Plant Siting Database

    Energy Science and Technology Software Center (ESTSC)

    1994-01-28

    This database is a repository of comprehensive licensing and technical reviews of siting regulatory processes and acceptance criteria for advanced light water reactor (ALWR) nuclear power plants. The program is designed to be used by applicants for an early site permit or combined construction permit/operating license (10CFRR522, Subparts A and C) as input for the development of the application. The database is a complete, menu-driven, self-contained package that can search and sort the supplied datamore » by topic, keyword, or other input. The software is designed for operation on IBM compatible computers with DOS.« less

  19. Qualification of active mechanical components for nuclear power plants

    SciTech Connect

    Allen, R.D.; Mollerus, F.J.

    1983-11-01

    The Electric Power Research Institute has undertaken a study of active safety related mechanical components in domestic nuclear plants to determine what qualification information exists and to establish a plan for qualification of those components. Active safety related mechanical components are those which undergo mechanical motion to perform a safety function. The overall objective of the study is to recommend appropriate methods and realistic criteria for the environmental, seismic and dynamic qualification of active mechanical components. This paper presents the results of progress in this project through May 1983.

  20. Perry Nuclear Plant's Plans for on-site storage

    SciTech Connect

    Ratchen, J.T. )

    1993-01-01

    Because of current radwaste disposal legislation and the eventual denial of access to the Barnwell, Richland, and Beatty burial sites, it was imperative for the Perry nuclear power plant to develop alternative means for handling its generated radioactive waste. The previous radwaste facilities at Perry were developed for processing, packaging, short-term storage, and shipment for burial. In order to meet the changing needs, new facilities have been constructed to handle the processing, packaging, and 5-yr interim storage of both dry active waste (DAW) and dewatered or solidified resin, filter media, etc.

  1. Automated separation process for radioanalytical purposes at nuclear power plants.

    PubMed

    Nagy, L G; Vajda, N; Vodicska, M; Zagyvai, P; Solymosi, J

    1987-10-01

    Chemical separation processes have been developed to remove the matrix components and thus to determine fission products, especially radioiodine nuclides, in the primary coolant of WWER-type nuclear reactors. Special procedures have been elaborated to enrich long-lived nuclides in waste waters to be released and to separate and enrich caesium isotopes in the environment. All processes are based mainly on ion-exchange separations using amorphous zirconium phosphate. Automated equipment was constructed to meet the demands of the plant personnel for serial analysis. PMID:3680447

  2. Float level switch for a nuclear power plant containment vessel

    DOEpatents

    Powell, James G.

    1993-01-01

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel.

  3. Float level switch for a nuclear power plant containment vessel

    DOEpatents

    Powell, J.G.

    1993-11-16

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel. 1 figures.

  4. Impact of the Bohunice Nuclear Power Plant on atmospheric radiocarbon.

    PubMed

    Povinec, P P; Sivo, A; Simon, J; Holý, K; Chudý, M; Richtáriková, M; Morávek, J

    2008-11-01

    Radiocarbon variations in the atmospheric CO(2) have been observed at two localities in Slovakia (Bratislava and Zlkovce). Zlkovce is situated about 60 km NE from Bratislava, and only 5 km from the Bohunice Nuclear Power Plant (NPP). The observed Delta(14)C levels provide a unique evidence of the long-term impact of the Bohunice NPP on the Bratislava region, as well as on the decreased fossil fuel CO(2) emissions. The radiation doses estimated to the local public have been around 3 microSv/year, 20% of the dose from global fallout (14)C present in the environment. PMID:18534859

  5. Qualification of Safety-Related Software in Nuclear Power Plants

    SciTech Connect

    Johnson, G L

    2000-06-13

    Digital instrumentation and control systems have the potential of offering significant benefits over traditional analog systems in Nuclear Power Plant safety systems, but there are also significant difficulties in qualifying digital systems to the satisfaction of regulators. Digital systems differ in fundamental ways from analog systems. New methods for safety qualification, which take these differences into account, would ease the regulatory cost and promote use of digital systems. This paper offers a possible method for assisting in the analysis of digital system software, as one step in an improved qualification process.

  6. Stochastic modeling of deterioration in nuclear power plant components

    NASA Astrophysics Data System (ADS)

    Yuan, Xianxun

    2007-12-01

    The risk-based life-cycle management of engineering systems in a nuclear power plant is intended to ensure safe and economically efficient operation of energy generation infrastructure over its entire service life. An important element of life-cycle management is to understand, model and forecast the effect of various degradation mechanisms affecting the performance of engineering systems, structures and components. The modeling of degradation in nuclear plant components is confounded by large sampling and temporal uncertainties. The reason is that nuclear systems are not readily accessible for inspections due to high level of radiation and large costs associated with remote data collection methods. The models of degradation used by industry are largely derived from ordinary linear regression methods. The main objective of this thesis is to develop more advanced techniques based on stochastic process theory to model deterioration in engineering components with the purpose of providing more scientific basis to life-cycle management of aging nuclear power plants. This thesis proposes a stochastic gamma process (GP) model for deterioration and develops a suite of statistical techniques for calibrating the model parameters. The gamma process is a versatile and mathematically tractable stochastic model for a wide variety of degradation phenomena, and another desirable property is its nonnegative, monotonically increasing sample paths. In the thesis, the GP model is extended by including additional covariates and also modeling for random effects. The optimization of age-based replacement and condition-based maintenance strategies is also presented. The thesis also investigates improved regression techniques for modeling deterioration. A linear mixed-effects (LME) regression model is presented to resolve an inconsistency of the traditional regression models. The proposed LME model assumes that the randomness in deterioration is decomposed into two parts: the unobserved

  7. 76 FR 29279 - Prairie Island Nuclear Generating Plant, Units 1 and 2; Notice of Availability of the Final...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-20

    ... COMMISSION NORTHERN STATES POWER COMPANY Prairie Island Nuclear Generating Plant, Units 1 and 2; Notice of... Nuclear Plants Regarding the License Renewal of Prairie Island Nuclear Generating Plants, Units 1 and 2... years of operation for Prairie Island Nuclear Generating Plant, Units 1 and Unit 2 (PINGP 1 and 2)....

  8. Vitrification of Polyvinyl Chloride Waste from Korean Nuclear Power Plants

    SciTech Connect

    Sheng, Jiawei; Choi, Kwansik; Yang, Kyung-Hwa; Lee, Myung-Chan; Song, Myung-Jae

    2000-02-15

    Vitrification is considered as an economical and safe treatment technology for low-level radioactive waste (LLW) generated from nuclear power plants (NPPs). Korea is in the process of preparing for its first ever vitrification plant to handle LLW from its NPPs. Polyvinyl chloride (PVC) has the largest volume of dry active wastes and is the main waste stream to treat. Glass formulation development for PVC waste is the focus of study. The minimum additive waste stabilization approach has been utilized in vitrification. It was found that glasses can incorporate a high content of PVC ash (up to 50 wt%), which results in a large volume reduction. A glass frit, KEP-A, was developed to vitrify PVC waste after the optimization of waste loading, melt viscosity, melting temperature, and chemical durability. The KEP-A could satisfactorily vitrify PVC with a waste loading of 30 to 50 wt%. The PVC-frit was tolerant of variations in waste composition.

  9. Extending the lifespan of nuclear power plant structures

    SciTech Connect

    Naus, D.J.; Oland, C.B.; Ellingwood, B.

    1995-04-01

    By the end of this decade, 63 of the 111 commercial nuclear power plants in the United States will be more than 20 years old, with some nearing the end of their 40-year operating license term. Faced with the prospect of having to replace lost generating capacity from other sources and substantial shutdown and decommissioning costs, many utilities are expected to apply to continue the service of their plants past the initial licensing period. In support of such applications, evidence should be provided that the capacity of the safety-related systems and structures to mitigate potential extreme events has not deteriorated unacceptably due to either aging or environmental stressor effects during the previous service history.

  10. Next Generation Nuclear Plant Resilient Control System Functional Analysis

    SciTech Connect

    Lynne M. Stevens

    2010-07-01

    Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generation Nuclear Plant; defines resilient controls; assesses the current state of both traditional and resilient control systems; and documents the functional gaps existing between these two controls approaches as applicable to HTGRs. This report supports the development of an overall strategy for applying resilient controls to HTGRs by showing that control systems with adequate levels of resilience perform at higher levels, respond more quickly to disturbances, increase operational efficiency, and increase public protection.

  11. 78 FR 55117 - Ultimate Heat Sink for Nuclear Power Plants; Draft Regulatory Guide

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-09

    ...The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1275, ``Ultimate Heat Sink for Nuclear Power Plants.'' This regulatory guide (RG) describes methods and procedures acceptable to the NRC staff that nuclear power plant facility licensees and applicants may use to implement general design criteria (GDC) that are applicable to the ultimate......

  12. 10 CFR Appendix A to Part 50 - General Design Criteria for Nuclear Power Plants

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false General Design Criteria for Nuclear Power Plants A Appendix A to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. A Appendix A to Part 50—General Design Criteria for Nuclear Power Plants Table of Contents introduction definitions...

  13. 76 FR 32237 - Florida Power Corporation, Crystal River Unit 3 Nuclear Generating Plant; Notice of Availability...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-03

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Florida Power Corporation, Crystal River Unit 3 Nuclear Generating Plant; Notice of Availability of Draft Supplement 44 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants and Public Meetings for the License...

  14. 33 CFR 165.106 - Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false Security Zone: Seabrook Nuclear... Guard District § 165.106 Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire. (a... property boundary of Seabrook Nuclear Power Plant identified as follows: beginning at position 42°53′58″...

  15. 33 CFR 165.106 - Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Security Zone: Seabrook Nuclear... Guard District § 165.106 Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire. (a... property boundary of Seabrook Nuclear Power Plant identified as follows: beginning at position 42°53′58″...

  16. 33 CFR 165.106 - Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Security Zone: Seabrook Nuclear... Guard District § 165.106 Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire. (a... property boundary of Seabrook Nuclear Power Plant identified as follows: beginning at position 42°53′58″...

  17. 33 CFR 165.106 - Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false Security Zone: Seabrook Nuclear... Guard District § 165.106 Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire. (a... property boundary of Seabrook Nuclear Power Plant identified as follows: beginning at position 42°53′58″...

  18. 33 CFR 165.106 - Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Security Zone: Seabrook Nuclear... Guard District § 165.106 Security Zone: Seabrook Nuclear Power Plant, Seabrook, New Hampshire. (a... property boundary of Seabrook Nuclear Power Plant identified as follows: beginning at position 42°53′58″...

  19. 26 CFR 1.468A-6 - Disposition of an interest in a nuclear power plant.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 26 Internal Revenue 6 2013-04-01 2013-04-01 false Disposition of an interest in a nuclear power...-6 Disposition of an interest in a nuclear power plant. (a) In general. This section describes the... taxpayer (transferor) of all or a portion of its qualifying interest in a nuclear power plant to...

  20. 10 CFR Appendix A to Part 100 - Seismic and Geologic Siting Criteria for Nuclear Power Plants

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Seismic and Geologic Siting Criteria for Nuclear Power Plants A Appendix A to Part 100 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) REACTOR SITE CRITERIA Pt. 100, App. A Appendix A to Part 100—Seismic and Geologic Siting Criteria for Nuclear Power Plants i. purpose General Design Criterion 2 of...

  1. 10 CFR Appendix S to Part 50 - Earthquake Engineering Criteria for Nuclear Power Plants

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Earthquake Engineering Criteria for Nuclear Power Plants S Appendix S to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. S Appendix S to Part 50—Earthquake Engineering Criteria for Nuclear Power Plants General Information This...

  2. 10 CFR Appendix A to Part 100 - Seismic and Geologic Siting Criteria for Nuclear Power Plants

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Seismic and Geologic Siting Criteria for Nuclear Power Plants A Appendix A to Part 100 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) REACTOR SITE CRITERIA Pt. 100, App. A Appendix A to Part 100—Seismic and Geologic Siting Criteria for Nuclear Power Plants i. purpose General Design Criterion 2 of...

  3. 10 CFR Appendix S to Part 50 - Earthquake Engineering Criteria for Nuclear Power Plants

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Earthquake Engineering Criteria for Nuclear Power Plants S Appendix S to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. S Appendix S to Part 50—Earthquake Engineering Criteria for Nuclear Power Plants General Information This...

  4. 10 CFR Appendix S to Part 50 - Earthquake Engineering Criteria for Nuclear Power Plants

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Earthquake Engineering Criteria for Nuclear Power Plants S Appendix S to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. S Appendix S to Part 50—Earthquake Engineering Criteria for Nuclear Power Plants General Information This...

  5. 10 CFR Appendix A to Part 100 - Seismic and Geologic Siting Criteria for Nuclear Power Plants

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Seismic and Geologic Siting Criteria for Nuclear Power Plants A Appendix A to Part 100 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) REACTOR SITE CRITERIA Pt. 100, App. A Appendix A to Part 100—Seismic and Geologic Siting Criteria for Nuclear Power Plants i. purpose General Design Criterion 2 of...

  6. 77 FR 6598 - In the Matter of Entergy Nuclear Operations, Inc., Palisades Nuclear Plant, 27780 Blue Star...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-08

    ... entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION In the Matter of Entergy Nuclear Operations, Inc., Palisades Nuclear Plant, 27780 Blue...

  7. 75 FR 9620 - Southern Nuclear Operating Company, Inc.; Edwin I. Hatch Nuclear Plant, Units 1 and 2; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-03

    ... have a significant effect on the quality of the human environment (75 FR 3761; dated January 22, 2010... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern Nuclear Operating Company, Inc.; Edwin I. Hatch Nuclear Plant, Units 1 and 2; Exemption...

  8. 75 FR 76052 - Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant, Units 1 and 2; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-07

    ... environment (75 FR 73135, dated November 29, 2010). This exemption is effective upon issuance. Dated at... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant, Units 1 and 2;...

  9. Neural network recognition of nuclear power plant transients

    SciTech Connect

    Bartlett, E.B.; Danofsky, R.; Adams, J.; AlJundi, T.; Basu, A.; Dhanwada, C.; Kerr, J.; Kim, K.; Lanc, T.

    1993-02-23

    The objective of this report is to describe results obtained during the first year of funding that will lead to the development of an artificial neural network (ANN) fault - diagnostic system for the real - time classification of operational transients at nuclear power plants. The ultimate goal of this three-year project is to design, build, and test a prototype diagnostic adviser for use in the control room or technical support center at Duane Arnold Energy Center (DAEC); such a prototype could be integrated into the plant process computer or safety - parameter display system. The adviser could then warn and inform plant operators and engineers of plant component failures in a timely manner. This report describes the work accomplished in the first of three scheduled years for the project. Included herein is a summary of the first year's results as, well as individual descriptions of each of the major topics undertaken by the researchers. Also included are reprints of the articles written under this funding as well as those that were published during the funded period.

  10. Comparison of Options for a Pilot Plant Fusion Nuclear Mission

    SciTech Connect

    Brown, T; Goldston, R J; El-Guebaly, L; Kessel, C; Neilson, G H; Malang, S; Menard, J E; Prager, S; Waganer, L; Titus, P; Zarnstorff, M

    2012-08-27

    A fusion pilot plant study was initiated to clarify the development needs in moving from ITER to a first of a kind fusion power plant, following a path similar to the approach adopted for the commercialization of fission. The pilot plant mission encompassed component test and fusion nuclear science missions plus the requirement to produce net electricity with high availability in a device designed to be prototypical of the commercial device. Three magnetic configuration options were developed around this mission: the advanced tokamak (AT), spherical tokamak (ST) and compact stellarator (CS). With the completion of the study and separate documentation of each design option a question can now be posed; how do the different designs compare with each other as candidates for meeting the pilot plant mission? In a pro/con format this paper will examine the key arguments for and against the AT, ST and CS magnetic configurations. Key topics addressed include: plasma parameters, device configurations, size and weight comparisons, diagnostic issues, maintenance schemes, availability influences and possible test cell arrangement schemes.

  11. Desalination and sustainability - An appraisal and current perspective.

    PubMed

    Gude, Veera Gnaneswar

    2016-02-01

    Desalination technologies have evolved and advanced rapidly along with increasing water demands around the world since 1950s. Many reviews have focused on the techno-economic and environmental and ecological issues of the desalination technologies and emphasized the feasibility of desalination industry as an alternative to meet the water demands in many water scarce regions. Despite these efforts, many perceptions about desalination processes hinder their applications for potential water supplies. This article has two specific aims: 1) provide an overview of the desalination trends around the world and discuss the sustainability components of desalination processes in comparison with other water supply alternatives; and 2) discuss case studies for desalination, and drivers and factors that influence sustainable desalination and other alternative water sources for desalination to increase our current understanding on the sensitive and futuristic issues of water supply and resource management options for drought facing regions. Although some of the facts and recent developments discussed here show that desalination can be affordable and potentially sustainable, contributions that meaningfully address socio-economic and ecological and environmental issues of desalination processes are urgently required in this critical era of severe water stress for the present context and the future development of desalination technologies. PMID:26641014

  12. EXTENDING NUCLEAR ENERGY TO NON-ELECTRICAL APPLICATIONS

    SciTech Connect

    R. Boardman; M. McKellar; D. Ingersoll; Z. Houghton; , R. Bromm; C. Desportes

    2014-09-01

    Electricity represents less than half of all energy consumed in the United States and globally. Although a few commercial nuclear power plants world-wide provide energy to non-electrical applications such as district heating and water desalination, nuclear energy has been largely relegated to base-load electricity production. A new generation of smaller-sized nuclear power plants offers significant promise for extending nuclear energy to many non-electrical applications. The NuScale small modular reactor design is especially well suited for these non-traditional customers due to its small unit size, very robust reactor protection features and a highly flexible and scalable plant design. A series of technical and economic evaluation studies have been conducted to assess the practicality of using a NuScale plant to provide electricity and heat to a variety of non-electrical applications, including water desalination, oil refining, and hydrogen production. The studies serve to highlight the unique design features of the NuScale plant for these applications and provide encouraging conclusions regarding the technical and economic viability of extending clean nuclear energy to a broad range of non-electrical energy consumers.

  13. Optimization of ramified absorber networks doing desalination.

    PubMed

    Singleton, Martin S; Heiss, Gregor; Hübler, Alfred

    2011-01-01

    An iterated function system is used to generate fractal-like ramified graph networks of absorbers, which are optimized for desalination performance. The diffusion equation is solved for the boundary case of constant pressure difference at the absorbers and a constant ambient salt concentration far from the absorbers, while constraining both the total length of the network and the total area of the absorbers to be constant as functions of generation G. A linearized form of the solution was put in dimensionless form which depends only on a dimensionless membrane resistance, a dimensionless inverse svelteness ratio, and G. For each of the first nine generations G=2,…,10, the optimal graph shapes were obtained. Total water production rate increases parabolically as a function of generation, with a maximum at G=7. Total water production rate is shown to be approximately linearly related to the power consumed, for a fixed generation. Branching ratios which are optimal for desalination asymptote decreasingly to r=0.510 for large G, while branching angles which are optimal for desalination asymptote decreasingly to 1.17 radians. Asymmetric graphs were found to be less efficient for desalination than symmetric graphs. The geometry which is optimal for desalination does not depend strongly on the dimensionless parameters, but the optimal water production does. The optimal generation was found to increase with the inverse svelteness ratio. PMID:21405775

  14. The Zwilag interim storage plasma plant technology to handle operational waste from nuclear plants

    SciTech Connect

    Heep, Walter

    2007-07-01

    The first processing of low level radioactive wastes from Swiss nuclear power plants marks the successful completion of commissioning in March 2004 of a treatment facility for low and intermediate level radioactive wastes, which is operated with the help of plasma technology. The theoretical principles of this metallurgy-derived process technology are based on plasma technology, which has already been used for a considerable period outside of nuclear technology for the production of highly pure metal alloys and for the plasma synthesis of acetylene. The commercial operation of the Plasma Plant owned by Zwischenlager Wuerenlingen AG (ZWILAG) has also enabled this technology to be used successfully for the first time in the nuclear field, especially in compliance with radiation protection aspects. In addition to a brief presentation of the technology used in the plant, the melting process under operating conditions will be explained in more detail. The separation factors attained and volume reductions achieved open interesting perspectives for the further optimisation of the entire process in the future. (author)

  15. Series assembly of microbial desalination cells containing stacked electrodialysis cells for partial or complete seawater desalination.

    PubMed

    Kim, Younggy; Logan, Bruce E

    2011-07-01

    A microbial desalination cell (MDC) is a new approach for desalinating water based on using the electrical current generated by exoelectrogenic bacteria. Previously developed MDCs have used only one or two desalination chambers with substantial internal resistance, and used low salinity catholytes containing a buffered or acid solution. Here we show that substantially improved MDC performance can be obtained even with a nonbuffered, saline catholyte, by using an electrodialysis stack consisting of 5 pairs of desalting and concentrating cells. When 4 stacked MDCs were used in series (20 total pairs of desalination chambers), the salinity of 0.06 L of synthetic seawater (35 g/L NaCl) was reduced by 44% using 0.12 L of anode solution (2:1). The resistive loss in the electrodialysis stack was negligible due to minimization of the intermembrane distances, and therefore the power densities produced by the MDC were similar to those produced by single chamber microbial fuel cells (MFCs) lacking desalination chambers. The observed current efficiency was 86%, indicating separation of 4.3 pairs of sodium and chloride ions for every electron transferred through the circuit. With two additional stages (total of 3.8 L of anolyte), desalination was increased to 98% salt removal, producing 0.3 L of fresh water (12.6:1). These results demonstrate that stacked MDCs can be used for efficient desalination of seawater while at the same time achieving power densities comparable to those obtained in MFCs. PMID:21671676

  16. Optimizing desalinated sea water blending with other sources to meet magnesium requirements for potable and irrigation waters.

    PubMed

    Avni, Noa; Eben-Chaime, Moshe; Oron, Gideon

    2013-05-01

    Sea water desalination provides fresh water that typically lacks minerals essential to human health and to agricultural productivity. Thus the rising proportion of desalinated sea water consumed by both the domestic and agricultural sectors constitutes a public health risk. Research on low-magnesium water irrigation showed that crops developed magnesium deficiency symptoms that could lead to plant death, and tomato yields were reduced by 10-15%. The World Health Organization (WHO) reported on a relationship between sudden cardiac death rates and magnesium intake deficits. An optimization model, developed and tested to provide recommendations for Water Distribution System (WDS) quality control in terms of meeting optimal water quality requirements, was run in computational experiments based on an actual regional WDS. The expected magnesium deficit due to the operation of a large Sea Water Desalination Plant (SWDP) was simulated, and an optimal operation policy, in which remineralization at the SWDP was combined with blending desalinated and natural water to achieve the required quality, was generated. The effects of remineralization costs and WDS physical layout on the optimal policy were examined by sensitivity analysis. As part of the sensitivity blending natural and desalinated water near the treatment plants will be feasible up to 16.2 US cents/m(3), considering all expenses. Additional chemical injection was used to meet quality criteria when blending was not feasible. PMID:23537704

  17. Water desalination across nanoporous graphene.

    PubMed

    Cohen-Tanugi, David; Grossman, Jeffrey C

    2012-07-11

    We show that nanometer-scale pores in single-layer freestanding graphene can effectively filter NaCl salt from water. Using classical molecular dynamics, we report the desalination performance of such membranes as a function of pore size, chemical functionalization, and applied pressure. Our results indicate that the membrane's ability to prevent the salt passage depends critically on pore diameter with adequately sized pores allowing for water flow while blocking ions. Further, an investigation into the role of chemical functional groups bonded to the edges of graphene pores suggests that commonly occurring hydroxyl groups can roughly double the water flux thanks to their hydrophilic character. The increase in water flux comes at the expense of less consistent salt rejection performance, which we attribute to the ability of hydroxyl functional groups to substitute for water molecules in the hydration shell of the ions. Overall, our results indicate that the water permeability of this material is several orders of magnitude higher than conventional reverse osmosis membranes, and that nanoporous graphene may have a valuable role to play for water purification. PMID:22668008

  18. Satellite Surveillance of Nuclear Plant, Assisting IAEA Control

    NASA Astrophysics Data System (ADS)

    Mileikowsky, Curt

    1997-01-01

    One of the great problems for world society today is what to do with the 100 000 tons of spent fuel — produced by 400 power reactors in over 30 nations — that contain 1000 tons of civilian plutonium and that will double in volume over the next 10 to 15 years. That future amount of civilian plutonium represents material for 400 000 nuclear bombs: simple ones, relatively easily made, ideal for terrorists, of the strength of 10-70% of the Hiroshima bomb. Because of this risk, spent fuel has to be safeguarded for 10 000 years. The most straightforward way to eliminate the need for safeguarding spent fuel would be to burn it. That could best be done with an accelerator-driven subcritical reactor, i.e. one that cannot function without the assistance of a 1-2.5 GeV proton accelerator supplying the lacking neutrons and which therefore makes for an extremely safe plant that cannot run amok (as Chernobyl did for example). 100 of such plant could burn all the plutonium produced by the 400 present-type reactors in the world and simultaneously produce profitable electric power. But such a scheme requires proof that the accelerators could not themselves be used for producing nuclear bomb material. That utterly important task for world society could be significantly supported by the new commercial high resolution observation satellites.

  19. Nuclear power plant Generic Aging Lessons Learned (GALL). Appendix B

    SciTech Connect

    Kasza, K.E.; Diercks, D.R.; Holland, J.W.; Choi, S.U.

    1996-12-01

    The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This report consists of Volume 2, which consists of the GALL literature review tables for the NUMARC Industry Reports reviewed for the report.

  20. Cognitive skill training for nuclear power plant operational decision making

    SciTech Connect

    Mumaw, R.J.; Swatzler, D.; Roth, E.M.; Thomas, W.A.

    1994-06-01

    Training for operator and other technical positions in the commercial nuclear power industry traditionally has focused on mastery of the formal procedures used to control plant systems and processes. However, decisionmaking tasks required of nuclear power plant operators involve cognitive skills (e.g., situation assessment, planning). Cognitive skills are needed in situations where formal procedures may not exist or may not be as prescriptive, as is the case in severe accident management (SAM). The Westinghouse research team investigated the potential cognitive demands of SAM on the control room operators and Technical Support Center staff who would be most involved in the selection and execution of severe accident control actions. A model of decision making, organized around six general cognitive processes, was developed to identify the types of cognitive skills that may be needed for effective performance. Also, twelve SAM scenarios were developed to reveal specific decision-making difficulties. Following the identification of relevant cognitive skills, 19 approaches for training individual and team cognitive skills were identified. A review of these approaches resulted in the identification of general characteristics that are important in effective training of cognitive skills.

  1. 10 CFR 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... maintenance at nuclear power plants. 50.65 Section 50.65 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC... Construction Permits § 50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power..., including normal shutdown operations. (a)(1) Each holder of an operating license for a nuclear power...

  2. 10 CFR 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... maintenance at nuclear power plants. 50.65 Section 50.65 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC... Construction Permits § 50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power..., including normal shutdown operations. (a)(1) Each holder of an operating license for a nuclear power...

  3. 10 CFR 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... maintenance at nuclear power plants. 50.65 Section 50.65 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC... Construction Permits § 50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power..., including normal shutdown operations. (a)(1) Each holder of an operating license for a nuclear power...

  4. 10 CFR 50.65 - Requirements for monitoring the effectiveness of maintenance at nuclear power plants.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... maintenance at nuclear power plants. 50.65 Section 50.65 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC... Construction Permits § 50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power..., including normal shutdown operations. (a)(1) Each holder of an operating license for a nuclear power...

  5. Study of seismic design bases and site conditions for nuclear power plants

    SciTech Connect

    Not Available

    1980-04-01

    This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches.

  6. Thermal performance monitoring and assessment in Dukovany nuclear power plant

    SciTech Connect

    Madron, F.; Papuga, J.; Pliska, J.

    2006-07-01

    Competition in the European electricity market forces generators to achieve - in compliance with safety and environmental standards - efficiency of production as high as possible. This efficiency or heat rate is an important indicator of both the condition of the plant equipment and the quality of plant operation. Similar thermal performance indicators can also be calculated for components of the plant equipment such as heat exchangers. However, it is not easy to quantify these indicators with sufficient precision so that the results can be used for conduct of plant operation in near-real time and for predictive maintenance. This paper describes a present state of the system monitoring and evaluating thermal performance of the reactor units in Dukovany Nuclear Power Plant. The system provides information on actual and desirable (should-be) values of thermal performance indicators for control room operators, performance engineers and maintenance planners. The system is designed to monitor steady states and has two main functions: data validation and process simulation. Data validation is based on data reconciliation methodology and carried out with Recon software by Chemplant Technology. A detailed model of the secondary side for mass and heat balancing has been made up by means of the Recon's graphical editor; now it contains roughly 300 flows and employs data of about 200 measurements. Main advantages of the data reconciliation are: - reconciled data are consistent with the model, - reconciled data are more precise than data directly measured with consequence that the thermal power of steam generators is determined with substantially lower uncertainty than before - data reconciliation represents a solid basis for detection and identification of data corrupted by gross errors. Simulation is performed with a different analytical model of plant components configured into secondary side. The model has been developed by I and C Energo. Main purposes of simulation are

  7. Effect of the Fukushima nuclear accident on the risk perception of residents near a nuclear power plant in China

    PubMed Central

    Huang, Lei; Zhou, Ying; Han, Yuting; Hammitt, James K.; Bi, Jun; Liu, Yang

    2013-01-01

    We assessed the influence of the Fukushima nuclear accident (FNA) on the Chinese public’s attitude and acceptance of nuclear power plants in China. Two surveys (before and after the FNA) were administered to separate subsamples of residents near the Tianwan nuclear power plant in Lianyungang, China. A structural equation model was constructed to describe the public acceptance of nuclear power and four risk perception factors: knowledge, perceived risk, benefit, and trust. Regression analysis was conducted to estimate the relationship between acceptance of nuclear power and the risk perception factors while controlling for demographic variables. Meanwhile, we assessed the median public acceptable frequencies for three levels of nuclear events. The FNA had a significant impact on risk perception of the Chinese public, especially on the factor of perceived risk, which increased from limited risk to great risk. Public acceptance of nuclear power decreased significantly after the FNA. The most sensitive groups include females, those not in public service, those with lower income, and those living close to the Tianwan nuclear power plant. Fifty percent of the survey respondents considered it acceptable to have a nuclear anomaly no more than once in 50 y. For nuclear incidents and serious incidents, the frequencies are once in 100 y and 150 y, respectively. The change in risk perception and acceptance may be attributed to the FNA. Decreased acceptance of nuclear power after the FNA among the Chinese public creates additional obstacles to further development of nuclear power in China and require effective communication strategies. PMID:24248341

  8. Fiber optic pressure sensors for nuclear power plants

    SciTech Connect

    Hashemian, H.M.; Black, C.L.

    1995-04-01

    In the last few years, the nuclear industry has experienced some problems with the performance of pressure transmitters and has been interested in new sensors based on new technologies. Fiber optic pressure sensors offer the potential to improve on or overcome some of the limitations of existing pressure sensors. Up to now, research has been motivated towards development and refinement of fiber optic sensing technology. In most applications, reliability studies and failure mode analyses remain to be exhaustively conducted. Fiber optic sensors have currently penetrated certain cutting edge markets where they possess necessary inherent advantages over other existing technologies. In these markets (e.g. biomedical, aerospace, automotive, and petrochemical), fiber optic sensors are able to perform measurements for which no alternate sensor previously existed. Fiber optic sensing technology has not yet been fully adopted into the mainstream sensing market. This may be due to not only the current premium price of fiber optic sensors, but also the lack of characterization of their possible performance disadvantages. In other words, in conservative industries, the known disadvantages of conventional sensors are sometimes preferable to unknown or not fully characterized (but potentially fewer and less critical) disadvantages of fiber optic sensors. A six-month feasibility study has been initiated under the auspices of the US Nuclear Regulatory Commission (NRC) to assess the performance and reliability of existing fiber optic pressure sensors for use in nuclear power plants. This assessment will include establishment of the state of the art in fiber optic pressure sensing, characterization of the reliability of fiber optic pressure sensors, and determination of the strengths and limitations of these sensors for nuclear safety-related services.

  9. Aging of safety class 1E transformers in safety systems of nuclear power plants

    SciTech Connect

    Roberts, E.W.; Edson, J.L.; Udy, A.C.

    1996-02-01

    This report discusses aging effects on safety-related power transformers in nuclear power plants. It also evaluates maintenance, testing, and monitoring practices with respect to their effectiveness in detecting and mitigating the effects of aging. The study follows the US Nuclear Regulatory Commission`s (NRC`s) Nuclear Plant-Aging Research approach. It investigates the materials used in transformer construction, identifies stressors and aging mechanisms, presents operating and testing experience with aging effects, analyzes transformer failure events reported in various databases, and evaluates maintenance practices. Databases maintained by the nuclear industry were analyzed to evaluate the effects of aging on the operation of nuclear power plants.

  10. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

  11. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

  12. Using bacterial catalyst in the cathode of microbial desalination cell to improve wastewater treatment and desalination.

    PubMed

    Wen, Qinxue; Zhang, Huichao; Chen, Zhiqiang; Li, Yufei; Nan, Jun; Feng, Yujie

    2012-12-01

    A microbial desalination cell (MDC) is able to desalinate salt water without energy consumption whilst generating bioenergy. Previously MDCs used abiotic cathodes, which are restricted in application by high operating costs and low levels of sustainability whereas, in the present study, an aerobic biocathode consisting of carbon felt and bacterial catalysts was tested. The biocathode MDC produced a maximum voltage of 609 mV, the value of which was 136 mV higher than that of an air cathode MDC operated under the same conditions. The salinity of 39 mL of salt water (35 g L(-1) NaCl) was reduced by 92% using 0.441 L of anode solution (11.3:1), with a coulombic efficiency of 96.2 ± 3.8% and a total desalination rate of 2.83 mg h(-1). The biocathode MDC proved to be a promising approach for efficient desalination of salt water. PMID:23026321

  13. 76 FR 53994 - Final Environmental Impact Statement, Single Nuclear Unit at the Bellefonte Plant Site, Jackson...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-30

    ... three nuclear plants, 11 coal-fired plants, 12 gas-fired plants, 29 hydroelectric dams, and a pumped... load generation to balance resources with the projected load requirements. Neither coal- fired nor... Unit 1 also would provide TVA more flexibility to idle existing coal plants. These conclusions...

  14. Harmful algae and their potential impacts on desalination operations off southern California.

    PubMed

    Caron, David A; Garneau, Marie-Eve; Seubert, Erica; Howard, Meredith D A; Darjany, Lindsay; Schnetzer, Astrid; Cetinić, Ivona; Filteau, Gerry; Lauri, Phil; Jones, Burton; Trussell, Shane

    2010-01-01

    Seawater desalination by reverse osmosis (RO) is a reliable method for augmenting drinking water supplies. In recent years, the number and size of these water projects have increased dramatically. As freshwater resources become limited due to global climate change, rising demand, and exhausted local water supplies, seawater desalination will play an important role in the world's future water supply, reaching far beyond its deep roots in the Middle East. Emerging contaminants have been widely discussed with respect to wastewater and freshwater sources, but also must be considered for seawater desalination facilities to ensure the long-term safety and suitability of this emerging water supply. Harmful algal blooms, frequently referred to as 'red tides' due to their vibrant colors, are a concern for desalination plants due to the high biomass of microalgae present in ocean waters during these events, and a variety of substances that some of these algae produce. These compounds range from noxious substances to powerful neurotoxins that constitute significant public health risks if they are not effectively and completely removed by the RO membranes. Algal blooms can cause significant operational issues that result in increased chemical consumption, increased membrane fouling rates, and in extreme cases, a plant to be taken off-line. Early algal bloom detection by desalination facilities is essential so that operational adjustments can be made to ensure that production capacity remains unaffected. This review identifies the toxic substances, their known producers, and our present state of knowledge regarding the causes of toxic episodes, with a special focus on the Southern California Bight. PMID:19664796

  15. Ultrasonic waveguide sensor for acoustic monitoring of nuclear power plants

    SciTech Connect

    Mel'nikov, V.I.; Khokhlov, V.N.; Duntsev, A.V.

    1988-02-01

    Waveguide sensors are being increasingly used for acoustic emission monitoring of equipment in nuclear power plants and in systems for acoustic diagnostics of the coolant. In this paper we examine the construction of a waveguide sensor for acoustic monitoring for the example of an impedance sensor for the steam content of water coolant, intended for use in the active emission-reception mode. The dynamic properties of the sensor are determined by the construction and the dimensions of the transducer, and are usually represented by its amplitude-frequency characteristic, which, as a rule, is of the resonance type. The longitudinal-wave waveguide, made from steel wire 0.8-1.2 mm in diameter, can transmit signals in the band 50-1000 kHz. To increase the reliability and the ease of maintenance of the monitoring system the transducer and the waveguide are connected in a detachable manner.

  16. Advanced interaction media in nuclear power plant control rooms.

    PubMed

    Stephane, Lucas

    2012-01-01

    The shift from analog to digital Instruments (related mainly to information visualization) and Controls in Nuclear Power Plant Main Control Rooms (NPP MCR) is a central current topic of investigation. In NPP MCR, digitalization was implemented gradually, analog and digital systems still coexisting for the two main systems related to safety--Safety Instruments and Control System (SICS) and Process Instruments and Controls System (PICS). My ongoing research focuses on the introduction of Advanced Interaction Media (AIM) such as stereoscopic 3D visualization and multi-touch surfaces in control rooms. This paper proposes a Safety-Centric approach for gathering the Design Rationale needed in the specification of such novel AIM concepts as well as their evaluation through user tests. Beyond methodological research, the final output of the current research is to build an experimental simulator aiming to enhance improvements in Human-Systems Integration (HSI). This paper provides an overview of the topics under consideration. PMID:22317419

  17. Edwin I. Hatch nuclear plant implementation of improved technical specifications

    SciTech Connect

    Mahler, S.R.; Pendry, D.

    1994-12-31

    Edwin I. Hatch nuclear plant consists of two General Electric boiling water reactor/4 units, with a common control room and a common refueling floor. In March 1993, Hatch began conversion of both units` technical specifications utilizing NUREG 1433. The technical specifications amendment request was submitted February 25, 1994. Issuance is scheduled for October 21, 1994, with implementation on March 15, 1994. The current unit-1 technical specifications are in the {open_quotes}custom{close_quotes} format, and the unit-2 technical specifications are in the old standard format. Hatch previously relocated the fire protection and radiological technical specifications requirements. The Hatch conversion will provide consistency between the two units, to the extent practicable.

  18. HFE safety reviews of advanced nuclear power plant control rooms

    NASA Technical Reports Server (NTRS)

    Ohara, John

    1994-01-01

    Advanced control rooms (ACR's) will utilize human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator's overall role and means of interacting with the system. The Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) aspects of HSI's to ensure that they are designed to good HFE principles and support performance and reliability in order to protect public health and safety. However, the only available NRC guidance was developed more than ten years ago, and does not adequately address the human performance issues and technology changes associated with ACR's. Accordingly, a new approach to ACR safety reviews was developed based upon the concept of 'convergent validity'. This approach to ACR safety reviews is described.

  19. Management of aging of nuclear power plant containment structures

    SciTech Connect

    Naus, D.; Oland, C.B.; Ellingwood, B.; Norris, W.E.; Graves, H.L. III

    1998-06-01

    Research addressing aging management of nuclear power plant concrete and steel containment structures is summarized. Accomplishments related to concrete containment structures include formation of a materials` property database; an aging assessment methodology to identify critical structures and degradation factors; guidelines and evaluation criteria for use in condition assessments; and a time-dependent reliability-based methodology for condition assessments and estimations of future performance. Under the steel containments and liners activity, a degradation assessment methodology has been developed, mathematical models that describe time-dependent changes in the containment due to aggressive environmental factors have been identified, and statistical data supporting the use of these models in time-dependent reliability analysis have been summarized.

  20. Prognostics and Life Beyond 60 for Nuclear Power Plants

    SciTech Connect

    Leonard J. Bond; Pradeep Ramuhalli; Magdy S. Tawfik; Nancy J. Lybeck

    2011-06-01

    Safe, secure, reliable and sustainable energy supply is vital for advanced and industrialized life styles. To meet growing energy demand there is interest in longer term operation (LTO) for the existing nuclear power plant fleet and enhancing capabilities in new build. There is increasing use of condition based maintenance (CBM) for active components and periodic in service inspection (ISI) for passive systems: there is growing interest in deploying on-line monitoring. Opportunities exist to move beyond monitoring and diagnosis based on pattern recognition and anomaly detection to and prognostics with the ability to provide an estimate of remaining useful life (RUL). The adoption of digital I&C systems provides a framework within which added functionality including on-line monitoring can be deployed, and used to maintain and even potentially enhance safety, while at the same time improving planning and reducing both operations and maintenance costs.

  1. Radiation effects on organic materials in nuclear plants. Final report

    SciTech Connect

    Bruce, M B; Davis, M V

    1981-11-01

    A literature search was conducted to identify information useful in determining the lowest level at which radiation causes damage to nuclear plant equipment. Information was sought concerning synergistic effects of radiation and other environmental stresses. Organic polymers are often identified as the weak elements in equipment. Data on radiation effects are summarized for 50 generic name plastics and 16 elastomers. Coatings, lubricants, and adhesives are treated as separate groups. Inorganics and metallics are considered briefly. With a few noted exceptions, these are more radiation resistant than organic materials. Some semiconductor devices and electronic assemblies are extremely sensitive to radiation. Any damage threshold including these would be too low to be of practical value. With that exception, equipment exposed to less than 10/sup 4/ rads should not be significantly affected. Equipment containing no Teflon should not be significantly affected by 10/sup 5/ rads. Data concerning synergistic effects and radiation sensitization are discussed. The authors suggest correlations between the two effects.

  2. Seismic fragility levels of nuclear power plant equipment

    SciTech Connect

    Bandyopadhyay, K.K.; Hofmayer, C.H.

    1987-01-01

    Seismic fragility levels of safety-related electrical and mechanical equipment used in nuclear power plants are discussed. The fragility level is defined as the vibration level corresponding to initiation of equipment malfunctions. The test response spectrum is used as a measure of this vibration level. The fragility phenomenon of an equipment is represented by a number of response spectra corresponding to various failure modes. Analysis methods are described for determination of the fragility level by use of existing test data. Useful conversion factors are tabulated to transform test response spectra from one damping value to another. Results are presented for switch-gears and motor control centers. The capacity levels of these equipment assemblies are observed to be limited by malfunctioning of contactors, motor starters, relays and/or switches. The applicability of the fragility levels, determined in terms of test response spectra, to Seismic Margin Studies and Probabilistic Risk Assessments is discussed and specific recommendations are provided.

  3. The transport of nuclear power plant components. [via airships

    NASA Technical Reports Server (NTRS)

    Keating, S. J., Jr.

    1975-01-01

    The problems of transporting nuclear power plant components to landlocked sites where the usual mode of transport by barge cannot be used are considered. Existing methods of ground-based overland transport are discussed and their costs presented. Components are described and traffic density projections made to the year 2000. Plots of units transported versus distance transported are provided for units booked in 1973 and booked and proposed in 1974. It is shown that, for these cases, overland transport requirements for the industry will be over 5,000,000 ton-miles/year while a projection based on increasing energy demands shows that this figure will increase significantly by the year 2000. The payload size, distances, and costs of existing overland modes are significant enough to consider development of a lighter than air (LTA) mode for transporting NSSS components.

  4. MICROBIAL TRANSFORMATIONS OF RADIONUCLIDES RELEASED FROM NUCLEAR FUEL REPROCESSING PLANTS.

    SciTech Connect

    FRANCIS,A.J.

    2006-10-18

    Microorganisms can affect the stability and mobility of the actinides U, Pu, Cm, Am, Np, and the fission products Tc, I, Cs, Sr, released from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been investigated, we have only limited information on the effects of microbial processes. The mechanisms of microbial transformations of the major and minor actinides and the fission products under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed.

  5. Excess infant mortality after nuclear plant startup in rural Mississippi.

    PubMed

    Mangano, Joseph J

    2008-01-01

    In the United States, utility companies have recently begun ordering new nuclear power reactors, the first such orders in the country since 1978. One potential site would be the Grand Gulf plant near Port Gibson, Mississippi. In 1983-1984, the first two years in which the existing Grand Gulf reactor operated, significant increases were observed in local rates of infant deaths (+35.3%) and fetal deaths (+57.8%). Local infant mortality remained elevated for the next two decades. These changes match those experienced in the same five local counties during atomic bomb testing in the 1950s and 1960s. This report examines potential reasons why an indigent, largely African American community may be at higher risk than other populations from exposure to an environmental toxin such as radiation. It also considers potential health risks posed by new reactors at Grand Gulf. PMID:18459281

  6. Prognostics and Life Beyond 60 Years for Nuclear Power Plants

    SciTech Connect

    Bond, Leonard J.; Ramuhalli, Pradeep; Tawfik, Magdy; Lybeck, Nancy

    2011-09-23

    Safe, secure, reliable and sustainable energy supply is vital for advanced and industrialized life styles. To meet growing energy demand there is interest in longer term operation (LTO) for the existing nuclear power plant fleet and enhancing capabilities in new build. There is increasing use of condition based maintenance (CBM) for active components and growing interest in deploying on-line monitoring instead of periodic in service inspection (ISI) for passive systems. Opportunities exist to move beyond monitoring and diagnosis based on pattern recognition and anomaly detection to prognostics with the ability to provide an estimate of remaining useful life (RUL). The adoption of digital I&C systems provides a framework within which added functionality including on-line monitoring can be deployed, and used to maintain and even potentially enhance safety, while at the same time improving planning and reducing both operations and maintenance costs.

  7. Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)

    SciTech Connect

    Dr. Mark Schanfein; Philip Casey Durst

    2012-07-01

    The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

  8. DEVELOPMENT OF NUCLEAR POWER PLANT SIMULATORS FOR SOVIET-DESIGNED NUCLEAR REACTORS.

    SciTech Connect

    Kohut, P.; Tutu, N.K.; Cleary, E.J.; Erickson, K.G.; Yoder, J.; Kroshilin, A.

    2001-01-07

    The US Department of Energy (US DOE), under the US government's International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators, are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper.

  9. Cancer near the Three Mile Island nuclear plant: radiation emissions.

    PubMed

    Hatch, M C; Beyea, J; Nieves, J W; Susser, M

    1990-09-01

    As a public charge, cancers among the 159,684 residents living within a 10-mile (16-km) radius of the Three Mile Island nuclear plant were studied relative to releases of radiation during the March 28, 1979, accident as well as to routine plant emissions. The principal cancers considered were leukemia and childhood malignancies. Estimates of the emissions delivered to small geographic study tracts were derived from mathematical dispersion models which accounted for modifying factors such as wind and terrain; the model of accident emissions was validated by readings from off-site dosimeters. Incident cancers among area residents for the period 1975-1985 (n = 5,493) were identified by a review of the records at all local and regional hospitals; preaccident and postaccident trends in cancer rates were examined. For accident emissions, the authors failed to find definite effects of exposure on the cancer types and population subgroups thought to be most susceptible to radiation. No associations were seen for leukemia in adults or for childhood cancers as a group. For leukemia in children, the odds ratio was raised, but cases were few (n = 4), and the estimate was highly variable. Moreover, rates of childhood leukemia in the Three Mile Island area are low compared with national and regional rates. For exposure to routine emissions, the odds ratios were raised for childhood cancers as a whole and for childhood leukemia, but confidence intervals were wide and included 1.0. For leukemia in adults, there was a negative trend. Trends for two types of cancer ran counter to expectation. Non-Hodgkin's lymphoma showed raised risks relative to both accident and routine emissions; lung cancer (adjusted only indirectly for smoking) showed raised risks relative to accident emissions, routine emissions, and background gamma radiation. Overall, the pattern of results does not provide convincing evidence that radiation releases from the Three Mile Island nuclear facility influenced

  10. Strategic Co-Location in a Hybrid Process Involving Desalination and Pressure Retarded Osmosis (PRO).

    PubMed

    Sim, Victor S T; She, Qianhong; Chong, Tzyy Haur; Tang, Chuyang Y; Fane, Anthony G; Krantz, William B

    2013-01-01

    This paper focuses on a Hybrid Process that uses feed salinity dilution and osmotic power recovery from Pressure Retarded Osmosis (PRO) to achieve higher overall water recovery. This reduces the energy consumption and capital costs of conventional seawater desalination and water reuse processes. The Hybrid Process increases the amount of water recovered from the current 66.7% for conventional seawater desalination and water reuse processes to a potential 80% through the use of reclaimed water brine as an impaired water source. A reduction of up to 23% in energy consumption is projected via the Hybrid Process. The attractiveness is amplified by potential capital cost savings ranging from 8.7%-20% compared to conventional designs of seawater desalination plants. A decision matrix in the form of a customizable scorecard is introduced for evaluating a Hybrid Process based on the importance of land space, capital costs, energy consumption and membrane fouling. This study provides a new perspective, looking at processes not as individual systems but as a whole utilizing strategic co-location to unlock the synergies available in the water-energy nexus for more sustainable desalination. PMID:24956940

  11. Strategic Co-Location in a Hybrid Process Involving Desalination and Pressure Retarded Osmosis (PRO)

    PubMed Central

    Sim, Victor S.T.; She, Qianhong; Chong, Tzyy Haur; Tang, Chuyang Y.; Fane, Anthony G.; Krantz, William B.

    2013-01-01

    This paper focuses on a Hybrid Process that uses feed salinity dilution and osmotic power recovery from Pressure Retarded Osmosis (PRO) to achieve higher overall water recovery. This reduces the energy consumption and capital costs of conventional seawater desalination and water reuse processes. The Hybrid Process increases the amount of water recovered from the current 66.7% for conventional seawater desalination and water reuse processes to a potential 80% through the use of reclaimed water brine as an impaired water source. A reduction of up to 23% in energy consumption is projected via the Hybrid Process. The attractiveness is amplified by potential capital cost savings ranging from 8.7%–20% compared to conventional designs of seawater desalination plants. A decision matrix in the form of a customizable scorecard is introduced for evaluating a Hybrid Process based on the importance of land space, capital costs, energy consumption and membrane fouling. This study provides a new perspective, looking at processes not as individual systems but as a whole utilizing strategic co-location to unlock the synergies available in the water-energy nexus for more sustainable desalination. PMID:24956940

  12. Managing Groundwater Radioactive Contamination at the Daiichi Nuclear Plant.

    PubMed

    Marui, Atsunao; Gallardo, Adrian H

    2015-07-01

    The Great East Japan Earthquake and tsunami of March 2011 severely damaged three reactors at the Fukushima Daiichi nuclear power station, leading to a major release of radiation into the environment. Groundwater flow through these crippled reactors continues to be one of the main causes of contamination and associated transport of radionuclides into the Pacific Ocean. In this context, a number of strategies are being implemented to manage radioactive pollution of the water resources at the nuclear plant site. Along with water treatment and purification, it is critical to restrict the groundwater flow to and from the reactors. Thus, the devised strategies combine walls containment, bores abstraction, infiltration control, and the use of tanks for the temporary storage of contaminated waters. While some of these techniques have been previously applied in other environments, they have never been tested at such a large scale. Therefore, their effectiveness remains to be seen. The present manuscript presents an overview of the methods being currently implemented to manage groundwater contamination and to mitigate the impact of hydrological pathways in the dispersion of radionuclides at Fukushima. PMID:26197330

  13. Seismic response for qualification of valves at nuclear plants

    SciTech Connect

    Bhargava, D.

    1996-12-01

    Power-operated valves constitute about a quarter to one-third of all safety-related components at a typical US nuclear plant. While extensive work has been done in the industry to quantify amplification factors for components such as electrical cabinets, little guidance is available to estimate amplification factors that can be applied to floor or piping anchor seismic response spectra to obtain valve responses. This paper establishes bounding amplification factors from which amplified response spectra and peak acceleration values can be obtained for the seismic qualification of valves. Parametric analyses of three representative nuclear piping systems consisting of different pipe sizes and support configurations are performed by the time-history method. Parameters such as the shape, frequency and energy content of the floor seismic spectra, peak shifting, size, weight and natural frequencies of the valves, support locations, and modal and spectral damping values are varied. Based on this study, amplified response spectra at the valve location for a variety of conditions are developed for each system. Amplification factors are then obtained by comparing spectra at the valve with the floor spectra. The peak seismic accelerations, which can be used in a valve`s static analysis, are automatically obtained form these results. They are, by definition, the zero period accelerations of the amplified response spectra at the valve.

  14. Managing Groundwater Radioactive Contamination at the Daiichi Nuclear Plant

    PubMed Central

    Marui, Atsunao; Gallardo, Adrian H.

    2015-01-01

    The Great East Japan Earthquake and tsunami of March 2011 severely damaged three reactors at the Fukushima Daiichi nuclear power station, leading to a major release of radiation into the environment. Groundwater flow through these crippled reactors continues to be one of the main causes of contamination and associated transport of radionuclides into the Pacific Ocean. In this context, a number of strategies are being implemented to manage radioactive pollution of the water resources at the nuclear plant site. Along with water treatment and purification, it is critical to restrict the groundwater flow to and from the reactors. Thus, the devised strategies combine walls containment, bores abstraction, infiltration control, and the use of tanks for the temporary storage of contaminated waters. While some of these techniques have been previously applied in other environments, they have never been tested at such a large scale. Therefore, their effectiveness remains to be seen. The present manuscript presents an overview of the methods being currently implemented to manage groundwater contamination and to mitigate the impact of hydrological pathways in the dispersion of radionuclides at Fukushima. PMID:26197330

  15. Nuclear Safety Risk Management in Refueling Outage of Qinshan Nuclear Power Plant

    SciTech Connect

    Meijing Wu; Guozhang Shen

    2006-07-01

    The NPP is used to planning maintenance, in-service inspection, surveillance test, fuel handling and design modification in the refueling outage; the operator response capability will be reduced plus some of the plant systems out of service or loss of power at this time. Based on 8 times refueling outage experiences of the Qinshan NPP, this article provide some good practice and lesson learned for the nuclear safety risk management focus at four safety function areas of Residual Heat Removal Capability, Inventory Control, Power availability and Reactivity control. (authors)

  16. Correlates of mental health in nuclear and coal-fired power plant workers.

    PubMed

    Parkinson, D K; Bromet, E J

    1983-08-01

    The mental health of 104 nuclear workers at the Three Mile Island plant was compared with that of 122 workers from another nuclear plant and 151 workers from two coal-fired generating plants. The coal-fired plant workers were somewhat more symptomatic than the nuclear plant workers. Assessments of work environments showed that the coal-fired plant workers perceived less stress but more problems with workplace exposures than the nuclear plant workers. Negative perceptions of work and marital stress were both strongly and independently related to mental distress. Overall, the results suggest that the Three Mile Island accident did not engender long-term psychological difficulties in workers evaluated 2.5 years after the accident. PMID:6635612

  17. Knowledge elicitation techniques and application to nuclear plant maintenance

    NASA Astrophysics Data System (ADS)

    Doyle, E. Kevin

    The new millennium has brought with it the opportunity of global trade which in turn requires the utmost in efficiency from each individual industry. This includes the nuclear power industry, a point which was emphasized when the electrical generation industry began to be de regulated across North America the late 1990s and re-emphasized when the northeast power grid of North America collapsed in the summer of 2003. This dissertation deals with reducing the cost of the maintenance function of Candu nuclear power plants and initiating a strong link between universities and the Canadian nuclear industry. Various forms of RCM (reliability-centred maintenance) have been the tools of choice in industry for improving the maintenance function during the last 20 years. In this project, pilot studies, conducted at Bruce Power between 1999 and 2005, and reported on in this dissertation, lay out a path to implement statistical improvements as the next step after RCM in reducing the cost of the maintenance. Elicitation protocols, designed for the age group being elicited, address the much-documented issue of a lack of data. Clear, graphical, inferential statistical interfaces are accentuated and developed to aid in building the teams required to implement the various methodologies and to help in achieving funding targets. Graphical analysis and Crow/AMSAA (army materials systems analysis activity) plots are developed and demonstrated from the point of view of justifying the expenditures of cost reduction efforts. This dissertation ultimately speaks to the great opportunity being presented by this approach at this time: of capturing the baby-boom generation's huge pool of knowledge before those people retire. It is expected that the protocols and procedures referenced here will have applicability across the many disciplines where collecting expert information from a similar age group is required.

  18. Containment hydrogen removal system for a nuclear power plant

    SciTech Connect

    Callaghan, V.M.; Flynn, E.P.; Pokora, B.M.

    1984-02-07

    A hydrogen removal system (10) separates hydrogen from the containment atmosphere of a nuclear power plant using a hydrogen permeable membrane separator (30). Water vapor is removed by condenser (14) from a gas stream withdrawn from the containment atmosphere. The gas stream is then compressed by compressor (24) and cooled (28,34) to the operating temperature of the hydrogen permeable membrane separator (30). The separator (30) separates the gas stream into a first stream, rich in hydrogen permeate, and a second stream that is hydrogen depleted. The separated hydrogen is passed through a charcoal adsorber (48) to adsorb radioactive particles that have passed through the hydrogen permeable membrane (44). The hydrogen is then flared in gas burner (52) with atmospheric air and the combustion products vented to the plant vent. The hydrogen depleted stream is returned to containment through a regenerative heat exchanger (28) and expander (60). Energy is extracted from the expander (60) to drive the compressor (24) thereby reducing the energy input necessary to drive the compressor (24) and thus reducing the hydrogen removal system (10) power requirements.

  19. Passive Safety Features in Advanced Nuclear Power Plant Design

    NASA Astrophysics Data System (ADS)

    Tahir, M.; Chughtai, I. R.; Aslam, M.

    2013-03-01

    For implementation of advance passive safety features in future nuclear power plant design, a passive safety system has been proposed and its response has been observed for Loss of Coolant Accident (LOCA) in the cold leg of a reactor coolant system. In a transient simulation the performance of proposed system is validated against existing safety injection system for a reference power plant of 325 MWe. The existing safety injection system is a huge system and consists of many active components including pumps, valves, piping and Instrumentation and Control (I&C). A good running of the active components of this system is necessary for its functionality as high head safety injection system under design basis accidents. Using reactor simulation technique, the proposed passive safety injection system and existing safety injection system are simulated and tested for their performance under large break LOCA for the same boundary conditions. Critical thermal hydraulic parameters of both the systems are presented graphically and discussed. The results obtained are approximately the same in both the cases. However, the proposed passive safety injection system is a better choice for such type of reactors due to reduction in components with improved safety.

  20. The Idaho Chemical Processing Plant Special Nuclear Material vault upgrade

    SciTech Connect

    Anderson, R.C.; Holloway, E.R.

    1992-06-24

    This document discusses storage space in a Special Nuclear Material (SNM) product storage vault at the Idaho Chemical Processing Plant (ICPP) which has been recently expanded by approximately 175%. This expansion required a minimum of space and funding and resulted in a large increase in net storage capacity. Security for the additional storage is provided by standard intrusion sensors and by a real-time monitoring system, which monitors the weight of the material as it rests on weight sensors (load cells). The monitoring system also feeds weight data to a Safeguards processor which provides further confidence to Safeguards personnel. The Department of Energy requirements for bimonthly inventories for SNM stored in a particular part of this facility have been eliminated because of the guarantees provided by a real-time monitoring system. A higher efficiency has been obtained by using the expensive real estate inside a hardened product storage vault. This project has provided the ICPP with a relatively inexpensive vault upgrade and when product material is placed in this area of the vault the manpower requirements to inventory it will be reduced, resulting in a net reduction in plant worker radiation exposure.

  1. The Decommissioning of the Trino Nuclear Power Plant

    SciTech Connect

    Brusa, L.; DeSantis, R.; Nurden, P. L.; Walkden, P.; Watson, B.

    2002-02-27

    Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt decommissioning strategy, with the target of releasing all of the nuclear sites by 2020. It was recognized that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The government also agreed that additional costs caused by the acceleration of the decommissioning program would be considered as stranded costs. These costs will be recovered by a levy on the kWh price of electricity, a process established and controlled by the Regulator of the Italian energy sector. Building on the successful collaboration to develop a prompt decommissioning strategy for the Latina Magnox reactor (1), BNFL and Sogin agreed to collaborate on an in depth study for the prompt decommissioning of the Sogin PWR at Trino. BNFL is currently decommissioning six NPPs and is at an advanced stage of planning for two further units, having completed a full and rigorous exercise to develop Baseline Decommissioning Plans (BDP's) for these stations. The BDP exercise utilizes the full range of

  2. Seismic isolation of nuclear power plants using sliding isolation bearings

    NASA Astrophysics Data System (ADS)

    Kumar, Manish

    Nuclear power plants (NPP) are designed for earthquake shaking with very long return periods. Seismic isolation is a viable strategy to protect NPPs from extreme earthquake shaking because it filters a significant fraction of earthquake input energy. This study addresses the seismic isolation of NPPs using sliding bearings, with a focus on the single concave Friction Pendulum(TM) (FP) bearing. Friction at the sliding surface of an FP bearing changes continuously during an earthquake as a function of sliding velocity, axial pressure and temperature at the sliding surface. The temperature at the sliding surface, in turn, is a function of the histories of coefficient of friction, sliding velocity and axial pressure, and the travel path of the slider. A simple model to describe the complex interdependence of the coefficient of friction, axial pressure, sliding velocity and temperature at the sliding surface is proposed, and then verified and validated. Seismic hazard for a seismically isolated nuclear power plant is defined in the United States using a uniform hazard response spectrum (UHRS) at mean annual frequencies of exceedance (MAFE) of 10-4 and 10 -5. A key design parameter is the clearance to the hard stop (CHS), which is influenced substantially by the definition of the seismic hazard. Four alternate representations of seismic hazard are studied, which incorporate different variabilities and uncertainties. Response-history analyses performed on single FP-bearing isolation systems using ground motions consistent with the four representations at the two shaking levels indicate that the CHS is influenced primarily by whether the observed difference between the two horizontal components of ground motions in a given set is accounted for. The UHRS at the MAFE of 10-4 is increased by a design factor (≥ 1) for conventional (fixed base) nuclear structure to achieve a target annual frequency of unacceptable performance. Risk oriented calculations are performed for

  3. Melanoma screening in a hungarian nuclear power plant.

    PubMed

    Tóth, Veronika; Somlai, Beáta; Hatvani, Zsófia; Szakonyi, József; Gaudi, István; Kárpáti, Sarolta

    2013-04-01

    The industrial use of the ionizing radiation (IR) particularly stresses the safe work, regular health control is inevitable. Since previous occupational cohorts reported contradictory data on the incidence of melanoma among nuclear industry workers, and in few publications significant increase of it has been described, our clinic was requested by the industry to screen malignant skin tumours among the workers of a power plant. Within a year we have investigated 556 workers, 275 females and 281 males. Out of them 283, majorly males had been officially confirmed as to be employed at hazardous, but strictly controlled environment for an average of 18 years (1-32 years). To distinguish between IR and environmental UV (UVA+UVB) induced cutaneous malignancies we determined the sun and tanning bed exposure of the workers. One in situ melanoma developed in a woman with type I skin, bullous sunburns in the history, who had worked in safe environment for 26 years. Basal cell carcinoma was identified in two men, each of them worked for more than 20 years with IR (in hazardous environment). One had type I skin, the other had type II skin. These results didn't differ significantly (chi-squared test; p = 0, 2437 and 1, 0) from the national population data and the results of Euromelanoma screening campaign in Hungary. Our data clearly show, that 1./UV exposure and skin type should be evaluated in occupation cohort studies. 2./The melanoma incidence was not significantly higher among the employees of the power plant than in the general Hungarian population, according to the results of our study, the only Hungarian power plant is safe as far as the skin carcinogenesis is concerned. PMID:23242566

  4. Reduction of Sodium Nitrate Liquid Waste in Nuclear Reprocessing Plants

    SciTech Connect

    Numata, M.; Mihara, S.; Kojima, S.; Ito, H.; Kato, T.

    2006-07-01

    Sodium nitrate solution has been generated from nuclear reprocessing plant as a result of neutralization of nitric acid. The sodium nitrate has been immobilized by bitumen, cement or other material in the site and waste packages have been produced. In order to reduce an environmental impact of the waste packages from the reprocessing plant, it is preferable to decompose nitrate ion to harmless gases such as nitrogen. A combination of formic acid and catalyst has been proposed for this purpose. But, the method is inadequate for a full decomposition of the nitrate ion. In addition, a mixture of NO and NO{sub 2} is produced during the reaction. Formaldehyde and hydrazine were selected as reductants and a combined use of Pd-Cu catalyst was tried to decompose the nitrate ion. As a result, the nitrate ion can almost entirely be decomposed without any generation of NO and NO{sub 2}. The test was conducted by 1 L flask. In case of formaldehyde, nitrate ion concentration can be reduced from 0.017 mol/l to 3.9x10{sup -4} mol/l. In case of hydrazine, nitrate concentration can be decreased from 2.8 mol/l to 9.5 x 10{sup -3} mol/l and ammonium ion is detected. The ammonium ion concentration in the final solution is 0.12 mol/l when 2.8 mol/l nitrate is reduced by hydrazine. Chemical reactions for formaldehyde on the Pd-Cu catalyst are estimated as combination of: NO{sub 3-} + HCHO = NO{sub 2-} + HCOOH; 2NO{sub 2-} + 3HCOOH = N{sub 2} + 3CO{sub 2} + 2H{sub 2}O + 2OH-; 4NO{sub 2-} + 3HCHO = 2N{sub 2} + 3CO{sub 2} + H{sub 2}O + 4OH-. the other hand, for hydrazine with the Pd-Cu catalyst: 3N{sub 2}H{sub 4} = 2NH{sub 3} + 2N{sub 2} + 3H{sub 2}; NO{sub 3-} + H{sub 2} = NO{sub 2-} + H{sub 2}O; NO{sub 2-} + NH{sub 3} = N{sub 2} + H{sub 2}O + OH-. The fundamental research shows that the combination usage of the Pd-Cu catalyst and formaldehyde or hydrazine is applicable for the reduction of nitrate liquid waste in the nuclear reprocessing plant. (authors)

  5. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect

    P. E. MacDonald

    2005-01-01

    The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

  6. Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants

    SciTech Connect

    Stephen Schey

    2009-07-01

    Cooperative Agreement DE-FC07-06ID14788 was executed between the U.S. Department of Energy, Electric Transportation Applications, and Idaho National Laboratory to investigate the economics of producing hydrogen by electrolysis using electricity generated by nuclear power. The work under this agreement is divided into the following four tasks: Task 1 – Produce Data and Analyses Task 2 – Economic Analysis of Large-Scale Alkaline Electrolysis Task 3 – Commercial-Scale Hydrogen Production Task 4 – Disseminate Data and Analyses. Reports exist on the prospect that utility companies may benefit from having the option to produce electricity or produce hydrogen, depending on market conditions for both. This study advances that discussion in the affirmative by providing data and suggesting further areas of study. While some reports have identified issues related to licensing hydrogen plants with nuclear plants, this study provides more specifics and could be a resource guide for further study and clarifications. At the same time, this report identifies other area of risks and uncertainties associated with hydrogen production on this scale. Suggestions for further study in some of these topics, including water availability, are included in the report. The goals and objectives of the original project description have been met. Lack of industry design for proton exchange membrane electrolysis hydrogen production facilities of this magnitude was a roadblock for a significant period. However, recent design breakthroughs have made costing this facility much more accurate. In fact, the new design information on proton exchange membrane electrolyzers scaled to the 1 kg of hydrogen per second electrolyzer reduced the model costs from $500 to $100 million. Task 1 was delayed when the original electrolyzer failed at the end of its economic life. However, additional valuable information was obtained when the new electrolyzer was installed. Products developed during this study

  7. Seismic isolation of nuclear power plants using elastomeric bearings

    NASA Astrophysics Data System (ADS)

    Kumar, Manish

    Seismic isolation using low damping rubber (LDR) and lead-rubber (LR) bearings is a viable strategy for mitigating the effects of extreme earthquake shaking on safety-related nuclear structures. Although seismic isolation has been deployed in nuclear structures in France and South Africa, it has not seen widespread use because of limited new build nuclear construction in the past 30 years and a lack of guidelines, codes and standards for the analysis, design and construction of isolation systems specific to nuclear structures. The nuclear accident at Fukushima Daiichi in March 2011 has led the nuclear community to consider seismic isolation for new large light water and small modular reactors to withstand the effects of extreme earthquakes. The mechanical properties of LDR and LR bearings are not expected to change substantially in design basis shaking. However, under shaking more intense than design basis, the properties of the lead cores in lead-rubber bearings may degrade due to heating associated with energy dissipation, some bearings in an isolation system may experience net tension, and the compression and tension stiffness may be affected by the horizontal displacement of the isolation system. The effects of intra-earthquake changes in mechanical properties on the response of base-isolated nuclear power plants (NPPs) were investigated using an advanced numerical model of a lead-rubber bearing that has been verified and validated, and implemented in OpenSees and ABAQUS. A series of experiments were conducted at University at Buffalo to characterize the behavior of elastomeric bearings in tension. The test data was used to validate a phenomenological model of an elastomeric bearing in tension. The value of three times the shear modulus of rubber in elastomeric bearing was found to be a reasonable estimate of the cavitation stress of a bearing. The sequence of loading did not change the behavior of an elastomeric bearing under cyclic tension, and there was no

  8. 76 FR 52356 - Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 1; Environmental Assessment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-22

    ... COMMISSION Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 1; Environmental Assessment and... to Indiana Michigan Power Company (the licensee), for operation of Donald C. Cook Nuclear Plant, Unit 1 (DCCNP-1), located in Berrien County, Michigan, in accordance with Title 10 of the Code of...

  9. 76 FR 53972 - Florida Power Corporation, Crystal River Unit No. 3 Nuclear Generating Plant; Notice of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-08-30

    ... rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to submit and serve all... COMMISSION Florida Power Corporation, Crystal River Unit No. 3 Nuclear Generating Plant; Notice of... Facility Operating License No. DPR-72 for Crystal River Unit 3 Nuclear generating Plant (CR-3),...

  10. 76 FR 5216 - Florida Power Corporation, Crystal River Unit 3 Nuclear Generating Plant; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-28

    ... COMMISSION Florida Power Corporation, Crystal River Unit 3 Nuclear Generating Plant; Exemption 1.0 Background... authorizes operation of the Crystal River ] Unit 3 Nuclear Generating Plant (Crystal River). The license... under 10 CFR 55.11 from the schedule requirements of 10 CFR 55.59. Specifically for Crystal River,...

  11. A Post Licensing Study of Community Effects at Two Operating Nuclear Power Plants. Final Report.

    ERIC Educational Resources Information Center

    Purdy, Bruce J.; And Others

    In an effort to identify and assess the social, economic, and political effects of nuclear power plant construction and operation upon two host communities (Plymouth, Massachusetts and Waterford, Connecticut), a post-licensing review revealed that the primary impact of the nuclear power plants in both communities was an increase in the property…

  12. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  13. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  14. 78 FR 67206 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-08

    ... Plants'' on May 1, 2013, (78 FR 25488) for a 60 day public comment period. The public comment period... COMMISSION Qualification Tests for Safety-Related Actuators in Nuclear Power Plants AGENCY: Nuclear... Commission (NRC) is issuing revision 1 to regulatory guide (RG) 1.73, ``Qualification Tests for...

  15. 33 CFR 165.1155 - Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach, California.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Nuclear Power Plant, Avila Beach, California. 165.1155 Section 165.1155 Navigation and Navigable Waters... Coast Guard District § 165.1155 Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach... Captain of the Port, Los Angeles-Long Beach, or his or her designated representative. (2) Persons...

  16. 33 CFR 165.1155 - Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach, California.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Nuclear Power Plant, Avila Beach, California. 165.1155 Section 165.1155 Navigation and Navigable Waters... Coast Guard District § 165.1155 Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach... Captain of the Port, Los Angeles-Long Beach, or his or her designated representative. (2) Persons...

  17. 33 CFR 165.1155 - Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach, California.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Nuclear Power Plant, Avila Beach, California. 165.1155 Section 165.1155 Navigation and Navigable Waters... Coast Guard District § 165.1155 Security Zone; Diablo Canyon Nuclear Power Plant, Avila Beach... Captain of the Port, Los Angeles-Long Beach, or his or her designated representative. (2) Persons...

  18. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  19. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  20. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  1. ATMOSPHERIC RELEASES FROM STANDARDIZED NUCLEAR POWER PLANTS: A WIND TUNNEL STUDY

    EPA Science Inventory

    Laboratory experiments were conducted to simulate radiopollutant effluents released to the atmosphere from two standard design nuclear power plants. The main objective of the study was to compare the dispersion in the wake of the standardized nuclear power plants with that in a s...

  2. Coupling Power Generation, Geologic CO2 Storage and Saline Groundwater Desalination to Address Growing Energy Needs in Water Constrained Regions

    NASA Astrophysics Data System (ADS)

    Davidson, C. L.; Wurstner, S. K.; Fortson, L. A.

    2010-12-01

    As humanity works to both minimize climate change and adapt to its early impacts, co-management of energy and water resources will become increasingly important. In some parts of the US, power plants have been denied permits, in part because of the significant burden placed on local water supplies by assigning new water rights for the facility’s entire design life. Water resources may be allocated 30 to 50 years into a future where water availability and quality are uncertain due to supply impacts associated with climate change and increased demand from growing populations, agriculture and industry. In many areas, particularly those with access to seawater, desalination is being employed with increasing frequency to augment conventional sources of fresh water. At the same time, many of the world’s developed nations are moving to reduce greenhouse gas emissions. One key technological option for addressing emissions from the power generation sector is CO2 capture and geologic storage (CCS). This process is both water and energy intensive for many power and industrial facilities, compounding the impact of declining water availability for plants faced with deploying CCS in a CO2-constrained future. However, a unique opportunity may exist to couple power generation and CCS by extracting and desalinating brine from the CO2 storage formation to produce fresh water. While this coupled approach is unlikely to be attractive for most CCS projects, it may represent a viable option in areas where there is demand for additional electricity but conventional water supplies are unable to meet the needs of the power generation and CO2 capture systems, or in areas where brine produced from CCS projects can be desalinated to supplement strained municipal supplies. This paper presents a preliminary analysis of the factors impacting the feasibility of coupled CCS-desalination projects. Several injection / extraction scenarios have been examined via the STOMP geochemical flow model

  3. Potential health impacts of consuming desalinated bottled water.

    PubMed

    Rowell, Candace; Kuiper, Nora; Shomar, Basem

    2015-06-01

    This study compared physicochemical properties, anion and carbon content and major and trace elements in desalinated and non-desalinated bottled water available in Qatar, and assessed the potential health risks associated with prolonged consumption of desalinated water. Results indicate that Qatar's population is not at elevated risk of dietary exposure to As (mean = 666 ng/L), Ba (48.0 μg/L), Be (9.27 ng/L), Cd (20.1 ng/L), Cr (874 ng/L), Pb (258 ng/L), Sb (475 ng/L) and U (533 ng/L) from consumption of both desalinated and non-desalinated bottled water types available in the country. Consumers who primarily consume desalinated water brands further minimize risk of exposure to heavy metals as levels were significantly lower than in non-desalinated bottled water. Desalinated bottled water was not a significant contributor to recommended daily intakes for Ca, Mg and F(-) for adults and children and may increase risk of deficiencies. Desalinated bottled water accounted for only 3% of the Institute of Medicine (IOM) adequate intake (AI) for Ca, 5-6% of the recommended daily allowance for Mg and 4% of the AI for F among adults. For children desalinated water contributed 2-3% of the IOM AICa, 3-10% of the RDA(Mg) and 3-9% of the AIF. PMID:26042976

  4. Activities in support of continuing the service of nuclear power plant concrete structures

    SciTech Connect

    Naus, Dan J

    2012-01-01

    In general, nuclear power plant concrete structure s performance has been very good; however, aging of concrete structures occurs with the passage of time that can potentially result in degradation if is effects are not controlled. Safety-related nuclear power plant concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The interaction of the license renewal process and concrete structures is noted. A summary of operating experience related to aging of nuclear power plant concrete structures is provided. Several candidate areas are identified where additional research would be beneficial for aging management of nuclear power plant concrete structures. Finally, an update on recent activities at Oak Ridge National Laboratory related to aging management of nuclear power plant concrete structures is provided.

  5. Use of probabilistic risk assessment (PRA) in expert systems to advise nuclear plant operators and managers

    SciTech Connect

    Uhrig, R.E.

    1988-01-01

    The use of expert systems in nuclear power plants to provide advice to managers, supervisors and/or operators is a concept that is rapidly gaining acceptance. Generally, expert systems rely on the expertise of human experts or knowledge that has been modified in publications, books, or regulations to provide advice under a wide variety of conditions. In this work, a probabilistic risk assessment (PRA)/sup 3/ of a nuclear power plant performed previously is used to assess the safety status of nuclear power plants and to make recommendations to the plant personnel. 5 refs., 1 fig., 2 tabs.

  6. Progress under the USDI-SWCC agreement for technical cooperation in desalination

    SciTech Connect

    Jamjoom, I.M.R.; Al-Yousef, A.R.F.; Heizer, R.T.

    1981-07-01

    Progress is reported on two desalination projects in Saudi Arabia sponsored by a joint agreement of the Saline Water Conversion Corporation (SWCC) and the US Department of the Interior (USDI). Project A, research, development, and training center (R, D and T), conducts needs analyses and trains Saudi Arabians to operate and maintain desalination plants. Project B is developing the technology for large-scale multistage flash (MSF) evaporation plants. A recent change in focus is deemphasizing project B, but the Joint Agreement continues to make progress on its goals. The appendix presents a summary of the operation and projects and lists the major design features of the R, D and T Center. 1 reference, 1 table. (DCK)

  7. 75 FR 77919 - Carolina Power & Light Company Shearon Harris Nuclear Power Plant, Unit 1; Environmental...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-14

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Carolina Power & Light Company Shearon Harris Nuclear Power Plant, Unit 1; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC, the Commission) is considering issuance of an exemption,...

  8. 77 FR 51071 - Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 2, Environmental Assessment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-23

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 2, Environmental Assessment and Finding of No Significant Impact The Nuclear Regulatory Commission (NRC or the Commission) is considering issuance of an exemption and an...

  9. 10 CFR 50.120 - Training and qualification of nuclear power plant personnel.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Training and qualification of nuclear power plant personnel. 50.120 Section 50.120 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Additional Standards for Licenses, Certifications, and Regulatory Approvals § 50.120 Training and qualification of nuclear...

  10. 26 CFR 1.468A-6 - Disposition of an interest in a nuclear power plant.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 26 Internal Revenue 6 2011-04-01 2011-04-01 false Disposition of an interest in a nuclear power...-6 Disposition of an interest in a nuclear power plant. (a) In general. This section describes the Federal income tax consequences of a transfer of the assets of a nuclear decommissioning fund...

  11. 26 CFR 1.468A-6 - Disposition of an interest in a nuclear power plant.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 26 Internal Revenue 6 2014-04-01 2014-04-01 false Disposition of an interest in a nuclear power...-6 Disposition of an interest in a nuclear power plant. (a) In general. This section describes the Federal income tax consequences of a transfer of the assets of a nuclear decommissioning fund...

  12. 26 CFR 1.468A-6 - Disposition of an interest in a nuclear power plant.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 26 Internal Revenue 6 2012-04-01 2012-04-01 false Disposition of an interest in a nuclear power...-6 Disposition of an interest in a nuclear power plant. (a) In general. This section describes the Federal income tax consequences of a transfer of the assets of a nuclear decommissioning fund...

  13. 77 FR 73056 - Initial Test Programs for Water-Cooled Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-07

    ...The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1259, ``Initial Test Programs for Water-Cooled Nuclear Power Plants.'' This guide describes the general scope and depth that the staff of the NRC considers acceptable for Initial Test Programs (ITPs) for light water cooled nuclear power...

  14. Nuclear power plant simulators: their use in operator training and requalification

    SciTech Connect

    Jones, D.W.; Baer, D.K.; Francis, C.C.

    1980-07-01

    This report presents the results of a study performed for the Nuclear Regulatory Commission to evaluate the capabilities and use of nuclear power plant simulators either built or being built by the US nuclear power industry; to determine the adequacy of existing standards for simulator design and for the training of power plant operators on simulators; and to assess the issues about simulator training programs raised by the March 28, 1979, accident at Three Mile Island Unit 2.

  15. Managed Aquifer Recharge of Surplus Desalinated Seawater: a MARSOL Case Study from Israel

    NASA Astrophysics Data System (ADS)

    Kurtzman, Daniel; Ganot, Yonatan; Russak, Ammos; Nitzan, Ido; Bernstein, Anat; Katz, Yoram; Guttman, Yossi

    2015-04-01

    MARSOL is an EU-funded project on demonstrating managed aquifer recharge (MAR) as a solution to water scarcity and drought. Among other activities in MARSOL, 7 demo-sites in Mediterranean countries were chosen for research and demonstration of different types of MAR (e.g. soil aquifer treatment, river infiltration basins etc.). One of these demo sites is the Menashe infiltration basin (Israel) in which MAR of surplus desalinated sea water is demonstrated, monitored and investigated in the last year. Different operational circumstances create periods in which water from the Hadera seawater desalination plant cannot be distributed through the national water carrier to consumers. A solution was set in MAR of this water through sandy infiltration ponds to the Israeli coastal aquifer which is consisted mainly from calcareous sandstone. Hydrological and geochemical aspects are of interest in this MAR operation due to the high discharge rates of low-salinity chlorinated water to the infiltration pond. Monitoring of operational events, laboratory experiments, controlled field-experiments and modelling are carried out aiming at clarifying the following issues: infiltration rates - spatial and temporal variability; recharge and withdrawal operation; disinfection by-products due to infiltration of chlorinated water; changes in hydraulic properties due to dissolution/precipitation processes; and using MAR of desalinated water as a remineralization treatment. We will present some results concerning these aspects concentrating on the last one. Observations show that desalinated water dissolve carbonates relatively fast in the unsaturated zone and shallow groundwater of the infiltration site. This process which increases significantly the water's alkalinity also enriches the water with magnesium which its deficiency in desalinated seawater is an unsolved concern. Further increase in calcium and magnesium concentration requires flow in the aquifer through the calcareous

  16. Desalination of water. June, 1970-December, 1981 (citations from the Engineering Index Data Base). Report for Jun 70-Dec 81

    SciTech Connect

    Not Available

    1981-12-01

    The industrial desalination of water is discussed with particular reference to large scale plants in the Middle East. Methods include electrodialysis, reverse osmosis, and ion exchange. Problems associated with corrosion and scale formation are also discussed. (This updated bibliography contains 268 citations, 68 of which are new entries to the previous edition.)

  17. Fifty years of safe operation of the Novovoronezh nuclear power plant

    NASA Astrophysics Data System (ADS)

    Fedorov, A. I.; Vitkovskii, S. L.; Vitkovskii, I. L.; Fomenko, V. I.; Loskutov, V. F.; Topchiyan, R. M.; Nikitenko, M. P.; Zhurbenko, A. V.

    2014-02-01

    Information on the experience gained from safe operation of the Novovoronezh nuclear power plant from the moment its first power unit was commissioned and till now is presented. The following modifications and design solutions on improving the equipment and systems of the Novovoronezh nuclear power plant units that were introduced during plant operation are of special importance: (i) further development of the designs of fuel rods and fuel assemblies

  18. Is irrigation with partial desalinated seawater a policy option for saving freshwater in the Kingdom of Saudi Arabia

    NASA Astrophysics Data System (ADS)

    Multsch, Sebastian; Alquwaizany, Abdulaziz S.; Lehnert, Karl-H.; Frede, Hans-Georg; Breuer, Lutz

    2015-04-01

    The agriculture sector consumes with 88 % a majority of the almost fossil water resources in the Kingdom of Saudi Arabia (KSA). Irrigation with saline water has been highlighted to be a promising technique to reduce fresh water consumption. Current desalination techniques, further developments, salt tolerant crop types and improved irrigation systems can potentially redesign future perspectives for irrigation agriculture, in particular by considering the growing desalination capacity in KSA (5 million m3 day-1 in 2003). Hence, we have analyzed the potential of using desalinated and partial desalinated seawater for growing crops in KSA by considering scenarios of salinity levels and desalination costs. The desalination process has been modelled with the ROSA© software considering a reverse osmosis (RO) plant. The spatial decision support system SPARE:WATER has been applied to assess the water footprint of crops (WFcrop). In order to maintain high crop yields, salts need to be washed out from the rooting zone, which requires the application of additional salt-free water. Therefore, high crop yields come along with additional water requirements and increased desalination effort and increased costs for proving high quality water. As an example, growing wheat with partial desalinated seawater from the Arabian Gulf with a RO plant has been investigated. Desalination reduces the salinity level from 76 dS m-1 to 0.5 dS m-1 considering two RO cycles, with cost of desalinized water in the range of 0.5 to 1.2 m-3. We acknowledge that cost only refer to desalination without considering others such as transport, water pumping or crop fertilization. The study shows that Boron is the most problematic salt component, because it is difficult to remove by RO and toxic in high concentrations for crops (wheat threshold of 0.5 to 1.0 mg l-1). The nationwide average WFcrop of wheat under surface irrigation is 2,628 m3 t-1 considering high water quality of 1 dS m-1 and 3,801 m3 t-1 at

  19. Seismic fragility of nuclear power plant components. Phase I

    SciTech Connect

    Bandyopadhyay, K.K.; Hofmayer, C.H.

    1986-06-01

    As part of the Component Fragility Research Program, sponsored by the US Nuclear Regulatory Commission, BNL is involved in establishing seismic fragility levels for various nuclear power plant equipment by identifying, collecting and analyzing existing test data from various sources. In Phase I of this program, BNL has reviewed approximately seventy test reports to collect fragility or high level test data for switchgears, motor control centers and similar electrical cabinets, valve actuators and numerous electrical devices of various manufacturers and models. This report provides an assessment and evaluation of the data collected in Phase I. The fragility data for medium voltage and low voltage switchgears and motor control centers are analyzed using the test response spectra (TRS) as a measure of the fragility level. The analysis reveals that fragility levels can best be described by a group of TRS curves corresponding to various failure modes. The lower-bound curve indicates the initiation of malfunctioning or structural damage; whereas, the upper-bound curve corresponds to overall failure of the equipment based on known failure modes. High level test data for some components are included in the report. These data indicate that some components are inherently strong and do not exhibit any failure mode even when tested at the vibration limit of a shake table. The common failure modes are identified in the report. The fragility levels determined in this report have been compared with those used in the PRA and Seismic Margin Studies. It appears that the BNL data better correlate with the HCLPF (High Confidence of a Low Probability of Failure) level used in Seismic Margin Studies and can improve this level as high as 60% for certain applications. Specific recommendations are provided for proper application of BNL fragility data to other studies.

  20. Korean Standard Nuclear Power Plant Response to Common Mode Failure of the Digital Plant Protection System

    SciTech Connect

    Lee, Cheol Shin; Park, Chan Eok; Choi, Chul Jin; Seo, Jong Tae

    2002-07-15

    The Korean Standard Nuclear Power Plant (KSNP) has adopted the digital plant protection system (PPS) to enhance the reliability and safety of the plant. Although the digital PPS can be designed with high reliability, it is considered to be vulnerable to common mode failure (CMF) in the system software, resulting in a total loss of the built-in hardware redundancy. Therefore, a comprehensive evaluation has been performed to demonstrate the intrinsic capability of the KSNP design in coping with the design-basis events concurrent with CMF in the digital PPS. Instead of the conservative bounding analysis methodology, a best-estimate analysis methodology has been developed and utilized since the design-basis events accompanied by CMF in the digital PPS are categorized as beyond-design-basis events. An additional reactor trip function on high containment pressure in the diverse protection system (DPS), which is totally diverse from the PPS and is not affected by the CMF in the digital PPS, has been proposed to meet the acceptance criteria of the evaluation results. A variety of diverse means such as the DPS, process control systems, and operator actions including design modification have been verified to be effective in mitigating the design-basis events with CMF in the digital PPS.

  1. Nuclear Technology Series. Course 10: Power Plant Systems.

    ERIC Educational Resources Information Center

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  2. Nuclear Technology Series. Course 13: Power Plant Chemistry.

    ERIC Educational Resources Information Center

    Center for Occupational Research and Development, Inc., Waco, TX.

    This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

  3. Safeguards Issues at Nuclear Reactors and Enrichment Plants

    SciTech Connect

    Boyer, Brian D

    2012-08-15

    The Agency's safeguards technical objective is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection.

  4. Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

    SciTech Connect

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-09-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  5. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2007-01-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  6. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-12-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  7. Technical basis for staffing levels at nuclear power plants

    SciTech Connect

    Shurberg, D.A.; Haber, S.B.; Morisseau, D.

    1995-04-01

    The objective of this project is to provide a technical basis for the establishment of criteria for minimum staffing levels of licensed and non-licensed NPP shift personnel. Minimum staffing levels for the purpose of this study, are defined as those necessary for successful accomplishment of all safety and additional functions that must be performed in order for the licensee to meet applicable regulatory requirements. This project involves a multi-faceted approach to the investigation of the issue. Relevant NRC documentation was identified and reviewed. Using the information obtained from this documentation review, a test plan was developed to aid in the collection of further information regarding the adequacy of current shift staffing levels. The test plan addresses three different activities to be conducted to provide information to the NRC for use in the assessment of current minimum staffing levels. The first activity is collection of data related to industry shift staffing practices through site visits to seven nuclear power plants. The second activity is a simulator study, which will use licensed operator crews responding to a simulated event, under two different staffing levels. Finally, workload models will be constructed for both licensed and non-licensed personnel, using a priori knowledge of the simulator scenarios with data resulting from one of the staffing levels studied in the simulator, and the data collected from the site visits. The model will then be validated against the data obtained from the second staffing level studied in the simulator. The validated model can then be used to study the impact of changing staffing-related variables on the plant shift crew`s ability to effectively mitigate an event.

  8. HTGR-GT closed-cycle gas turbine: a plant concept with inherent cogeneration (power plus heat production) capability

    SciTech Connect

    McDonald, C.F.

    1980-04-01

    The high-grade sensible heat rejection characteristic of the high-temperature gas-cooled reactor-gas turbine (HTGR-GT) plant is ideally suited to cogeneration. Cogeneration in this nuclear closed-cycle plant could include (1) bottoming Rankine cycle, (2) hot water or process steam production, (3) desalination, and (4) urban and industrial district heating. This paper discusses the HTGR-GT plant thermodynamic cycles, design features, and potential applications for the cogeneration operation modes. This paper concludes that the HTGR-GT plant, which can potentially approach a 50% overall efficiency in a combined cycle mode, can significantly aid national energy goals, particularly resource conservation.

  9. Developing a Hierarchical Decision Model to Evaluate Nuclear Power Plant Alternative Siting Technologies

    NASA Astrophysics Data System (ADS)

    Lingga, Marwan Mossa

    A strong trend of returning to nuclear power is evident in different places in the world. Forty-five countries are planning to add nuclear power to their grids and more than 66 nuclear power plants are under construction. Nuclear power plants that generate electricity and steam need to improve safety to become more acceptable to governments and the public. One novel practical solution to increase nuclear power plants' safety factor is to build them away from urban areas, such as offshore or underground. To date, Land-Based siting is the dominant option for siting all commercial operational nuclear power plants. However, the literature reveals several options for building nuclear power plants in safer sitings than Land-Based sitings. The alternatives are several and each has advantages and disadvantages, and it is difficult to distinguish among them and choose the best for a specific project. In this research, we recall the old idea of using the alternatives of offshore and underground sitings for new nuclear power plants and propose a tool to help in choosing the best siting technology. This research involved the development of a decision model for evaluating several potential nuclear power plant siting technologies, both those that are currently available and future ones. The decision model was developed based on the Hierarchical Decision Modeling (HDM) methodology. The model considers five major dimensions, social, technical, economic, environmental, and political (STEEP), and their related criteria and sub-criteria. The model was designed and developed by the author, and its elements' validation and evaluation were done by a large number of experts in the field of nuclear energy. The decision model was applied in evaluating five potential siting technologies and ranked the Natural Island as the best in comparison to Land-Based, Floating Plant, Artificial Island, and Semi-Embedded plant.

  10. Nuclear Energy Research Initiative. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants. Annual Report

    SciTech Connect

    Ritterbusch, S.E.

    2000-08-01

    The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-informed approach for the design and regulation of nuclear power plants. This approach will include the development and.lor confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRs) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go farther by focusing on the design of new plants.

  11. Knowledge of and Attitude to Nuclear Power among Residents around Tianwan Nuclear Power Plant in Jiangsu of China

    PubMed Central

    Yu, Ningle; Zhang, Yimei; Wang, Jin; Cao, Xingjiang; Fan, Xiangyong; Xu, Xiaosan; Wang, Furu

    2012-01-01

    Aims: The aims of this paper were to determine the level of knowledge of and attitude to nuclear power among residents around Tianwan Nuclear power plant in Jiangsu of China. Design: A descriptive, cross-sectional design was adopted. Participants: 1,616 eligible participants who lived around the Tianwan nuclear power plant within a radius of 30km and at least 18 years old were recruited into our study and accepted epidemiological survey. Methods: Data were collected through self-administered questionnaires consisting of a socio-demographic sheet. Inferential statistics, t-test, ANOVA test and multivariate regression analysis were used to compare the differences between each subgroup and correlation analysis was conducted to understand the relationship between different factors and dependent variables. Results: Our investigation found that the level of awareness and acceptance of nuclear power was generally not high. Respondents' gender, age, marital status, residence, educational level, family income and the distance away from the nuclear power plant are important effect factors to the knowledge of and attitude to nuclear power. Conclusions: The public concerns about nuclear energy's impact are widespread. The level of awareness and acceptance of nuclear power needs to be improved urgently. PMID:22811610

  12. Design related aspects in advanced nuclear fission plants

    NASA Astrophysics Data System (ADS)

    Hoffelner, Wolfgang

    2011-02-01

    Important issues to be considered for design of future reactors are: extrapolation of stress rupture data, creep-fatigue, negligible creep, damage monitoring. The paper highlights some new developments taking examples from a martensitic steel (mod 9% Cr), oxide dispersion strengthened (ODS) steels and nickel-base superalloys. Traditional approaches to extrapolation of (thermal) stress rupture data like Larson-Miller Parameter or Monkman-Grant rule seem to be valid concepts also for advanced reactors. However, a significant influence of cyclic softening on creep rates and stress rupture data can be expected as shown for grade 91. This is particularly true for creep-fatigue interactions. Based on cyclic stress-strain behaviour it is also possible to get very good life-time predictions under creep-fatigue with a strain range separation (inelastic fatigue and creep ranges) technique which could replace the currently used linear life fraction rule. Results from in-beam irradiation creep reveal no significant influence of dispersoid size. It can be assumed that irradiation creep is a matrix property. Finally it is shown that micro-sample testing of exposed material could be used as an advanced method for damage assessment in future nuclear power plants.

  13. Reassessment of selected factors affecting siting of Nuclear Power Plants

    SciTech Connect

    Davis, R.E.; Hanson, A.L.; Mubayi, V.; Nourbakhsh, H.P.

    1997-02-01

    Brookhaven National Laboratory has performed a series of probabilistic consequence assessment calculations for nuclear reactor siting. This study takes into account recent insights into severe accident source terms and examines consequences in a risk based format consistent with the quantitative health objectives (QHOs) of the NRC`s Safety Goal Policy. Simplified severe accident source terms developed in this study are based on the risk insights of NUREG-1150. The results of the study indicate that both the quantity of radioactivity released in a severe accident as well as the likelihood of a release are lower than those predicted in earlier studies. The accident risks using the simplified source terms are examined at a series of generic plant sites, that vary in population distribution, meteorological conditions, and exclusion area boundary distances. Sensitivity calculations are performed to evaluate the effects of emergency protective action assumptions on the risk of prompt fatality and latent cancers fatality, and population relocation. The study finds that based on the new source terms the prompt and latent fatality risks at all generic sites meet the QHOs of the NRC`s Safety Goal Policy by margins ranging from one to more than three orders of magnitude. 4 refs., 17 figs., 24 tabs.

  14. Status of radioiodine control for nuclear fuel reprocessing plants

    SciTech Connect

    Burger, L.L.; Scheele, R.D.

    1983-07-01

    This report summarizes the status of radioiodine control in a nuclear fuel reprocessing plant with respect to capture, fixation, and disposal. Where possible, we refer the reader to a number of survey documents which have been published in the last four years. We provide updates where necessary. Also discussed are factors which must be considered in developing criteria for iodine control. For capture from gas streams, silver mordenite and a silver nitrate impregnated silica (AC-6120) are considered state-of-the-art and are recommended. Three aqueous scrubbing processes have been demonstrated: Caustic scrubbing is simple but probably will not give an adequate iodine retention by itself. Mercurex (mercuric nitrate-nitric acid scrubbing) has a number of disadvantages including the use of toxic mercury. Iodox (hyperazeotropic nitric acid scrubbing) is effective but employs a very corrosive and hazardous material. Other technologies have been tested but require extensive development. The waste forms recommended for long-term storage or disposal are silver iodide, the iodates of barium, strontium, or calcium, and silver loaded sorbents, all fixed in cement. Copper iodide in bitumen (asphalt) is a possibility but requires testing. The selection of a specific form will be influenced by the capture process used.

  15. Seismic fragility of nuclear power plant components (Phase II)

    SciTech Connect

    Bandyopadhyay, K.K.; Hofmayer, C.H.; Kassir, M.K.; Pepper, S.E. )

    1990-02-01

    As part of the Component Fragility Program which was initiated in FY 1985, three additional equipment classes have been evaluated. This report contains the fragility results and discussions on these equipment classes which are switchgear, I and C panels and relays. Both low and medium voltage switchgear assemblies have been considered and a separate fragility estimate for each type is provided. Test data on cabinets from the nuclear instrumentation/neutron monitoring system, plant/process protection system, solid state protective system and engineered safeguards test system comprise the BNL data base for I and C panels (NSSS). Fragility levels have been determined for various failure modes of switchgear and I C panels, and the deterministic results are presented in terms of test response spectra. In addition, the test data have been evaluated for estimating the respective probabilistic fragility levels which are expressed in terms of a median value, an uncertainty coefficient, a randomness coefficient and an HCLPF value. Due to a wide variation of relay design and the fragility level, a generic fragility level cannot be established for relays. 7 refs., 13 figs., 12 tabs.

  16. Aging assessment of surge protective devices in nuclear power plants

    SciTech Connect

    Davis, J.F.; Subudhi, M.; Carroll, D.P.

    1996-01-01

    An assessment was performed to determine the effects of aging on the performance and availability of surge protective devices (SPDs), used in electrical power and control systems in nuclear power plants. Although SPDs have not been classified as safety-related, they are risk-important because they can minimize the initiating event frequencies associated with loss of offsite power and reactor trips. Conversely, their failure due to age might cause some of those initiating events, e.g., through short circuit failure modes, or by allowing deterioration of the safety-related component(s) they are protecting from overvoltages, perhaps preventing a reactor trip, from an open circuit failure mode. From the data evaluated during 1980--1994, it was found that failures of surge arresters and suppressers by short circuits were neither a significant risk nor safety concern, and there were no failures of surge suppressers preventing a reactor trip. Simulations, using the ElectroMagnetic Transients Program (EMTP) were performed to determine the adequacy of high voltage surge arresters.

  17. Impacts of the Fukushima nuclear power plants on marine radioactivity.

    PubMed

    Buesseler, Ken; Aoyama, Michio; Fukasawa, Masao

    2011-12-01

    The impacts on the ocean of releases of radionuclides from the Fukushima Dai-ichi nuclear power plants remain unclear. However, information has been made public regarding the concentrations of radioactive isotopes of iodine and cesium in ocean water near the discharge point. These data allow us to draw some basic conclusions about the relative levels of radionuclides released which can be compared to prior ocean studies and be used to address dose consequences as discussed by Garnier-Laplace et al. in this journal. The data show peak ocean discharges in early April, one month after the earthquake and a factor of 1000 decrease in the month following. Interestingly, the concentrations through the end of July remain higher than expected implying continued releases from the reactors or other contaminated sources, such as groundwater or coastal sediments. By July, levels of (137)Cs are still more than 10,000 times higher than levels measured in 2010 in the coastal waters off Japan. Although some radionuclides are significantly elevated, dose calculations suggest minimal impact on marine biota or humans due to direct exposure in surrounding ocean waters, though considerations for biological uptake and consumption of seafood are discussed and further study is warranted. PMID:22013920

  18. Information Foraging in Nuclear Power Plant Control Rooms

    SciTech Connect

    R.L. Boring

    2011-09-01

    nformation foraging theory articulates the role of the human as an 'informavore' that seeks information and follows optimal foraging strategies (i.e., the 'information scent') to find meaningful information. This paper briefly reviews the findings from information foraging theory outside the nuclear domain and then discusses the types of information foraging strategies operators employ for normal and off-normal operations in the control room. For example, operators may employ a predatory 'wolf' strategy of hunting for information in the face of a plant upset. However, during routine operations, the operators may employ a trapping 'spider' strategy of waiting for relevant indicators to appear. This delineation corresponds to information pull and push strategies, respectively. No studies have been conducted to determine explicitly the characteristics of a control room interface that is optimized for both push and pull information foraging strategies, nor has there been empirical work to validate operator performance when transitioning between push and pull strategies. This paper explores examples of control room operators as wolves vs. spiders and con- cludes by proposing a set of research questions to investigate information foraging in control room settings.

  19. Applications of neural networks to monitoring and decision making in the operation of nuclear power plants

    SciTech Connect

    Uhrig, R.E. Oak Ridge National Lab., TN )

    1990-01-01

    Application of neural networks to monitoring and decision making in the operation of nuclear power plants is being investigated under a US Department of Energy sponsored program at the University of Tennessee. Projects include the feasibility of using neural networks for the following tasks: (1) diagnosing specific abnormal conditions or problems in nuclear power plants, (2) detection of the change of mode of operation of the plant, (3) validating signals coming from detectors, (4) review of noise'' data from TVA's Sequoyah Nuclear Power Plant, and (5) examination of the NRC's database of Letter Event Reports'' for correlation of sequences of events in the reported incidents. Each of these projects and its status are described briefly in this paper. This broad based program has as its objective the definition of the state-of-the-art in using neural networks to enhance the performance of commercial nuclear power plants.

  20. Mild desalination of various raw water streams.

    PubMed

    Groot, C K; van den Broek, W B P; Loewenberg, J; Koeman-Stein, N; Heidekamp, M; de Schepper, W

    2015-01-01

    For chemical industries, fresh water availability is a pre-requisite for sustainable operation. However, in many delta areas around the world, fresh water is scarce. Therefore, the E4 Water project (www.e4water.eu) comprises a case study at the Dow site in Terneuzen, The Netherlands, which is designed to develop commercial applications for mild desalination of brackish raw water streams from various origins to enable reuse in industry or agriculture. This study describes an effective two-stage work process, which was used to narrow down a broad spectrum of desalination technologies to a selection of the most promising techniques for a demonstration pilot at 2-4 m³/hour. Through literature study, laboratory experiments and multi-criteria analysis, nanofiltration and electrodialysis reversal were selected, both having the potential to attain the objectives of E4Water at full scale. PMID:26204068

  1. Waters and desalination programs of Saudi Arabia

    SciTech Connect

    Wojcik, C.K.; Maadhah, A.G.

    1981-07-01

    Saudi Arabia is an arid desert country without rivers or sweet-water lakes. It does, however, have large amounts of ground water and seawater. These waters must be desalted by some means in order to make them potable. The most frequently used methods for that purpose are: multistage flash (MSF) evaporation, reverse osmosis (RO), and electrodialysis (ED). Because of rapid industrialization of the country, the demand for fresh water has been growing steadily. This, in turn, has resulted in a spectacular growth of the water-desalination industry. This paper discusses the availability and properties of the waters. It gives a detailed description of the major accomplishments and of the ongoing and future programs in the field of water desalination in Saudi Arabia. 14 references, 6 figures, 8 tables.

  2. 75 FR 14637 - James A. FitzPatrick Nuclear Power Plant; Environmental Assessment and Finding of No Significant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-26

    ... COMMISSION James A. FitzPatrick Nuclear Power Plant; Environmental Assessment and Finding of No Significant...), for the operation of the James A. FitzPatrick Nuclear Power Plant (JAFNPP) located in Oswego County... related to operation of James A. FitzPatrick Nuclear Power Plant Power Authority of the State of New...

  3. Desalination with carbon aerogel electrodes. Revision 1

    SciTech Connect

    Farmer, J.C.; Richardson, J.H.; Fix, D.V.; Thomson, S.L.; May, S.C.

    1996-12-04

    Electrically regenerated electrosorption process (carbon aerogel CDI) was developed by LLNL for continuously removing ionic impurities from aqueous streams. A salt solution flows in a channel formed by numerous pairs of parallel carbon aerogel electrodes. Each electrode has a very high BET surface area (2-5.4x10{sup 6}ft{sup 2}lb{sup -1} or 400-1100 m{sup 2}g{sup -1}) and very low electrical resistivity ({le}40 m{Omega}). Ions are removed from the electrolyte by the electric field and electrosorbed onto the carbon aerogel. It is concluded that carbon aerogel CDI may be an energy-efficient alternative to electrodialysis and reverse osmosis for desalination of brackish water ({le}5000 ppM). The intrinsic energy required by this process is about QV/2, where Q is the stored electrical charge and V is the voltage between the electrodes, plus losses. Estimated requirement for desalination of a 2000 ppM feed is -0.53-2.5 Wh/gal{sup -1} (0.5-2.4 kJ L{sup -1}), depending on voltage, flow rate, cell dimensions, aerogel density, recovery ratio, etc. This assumes that 50-70% of the stored electrical energy is reclaimed during regeneration (electrical discharge). Though the energy requirement for desalination of sea water is also low, this application will be much more difficult. Additional work will be required for desalination of streams that contain more than 5000 ppM total dissolved solids (2000 ppM will require electrochemical cells with extremely tight, demanding tolerances). At this present time, the process is best suited for streams with dilute impurities, as recently demonstrated during a field test at LLNL Treatment Facility C.

  4. Graphene and graphene oxide for desalination.

    PubMed

    You, Yi; Sahajwalla, Veena; Yoshimura, Masamichi; Joshi, Rakesh K

    2016-01-01

    There is a huge scope for graphene-based materials to be used as membranes for desalination. A very recent study has confirmed that 100% salt rejection can be achieved for commonly used ions by utilizing single layer nonporous graphene. However, the cost effective fabrication procedure for graphene oxide membranes with precise control of pore size can offer a practical solution for filtration if one can achieve 100% percent salt rejection. PMID:26615882

  5. Review of Water Resources and Desalination Technologies

    SciTech Connect

    MILLER, JAMES E.

    2003-03-01

    Water shortages affect 88 developing countries that are home to half of the world's population. In these places, 80-90% of all diseases and 30% of all deaths result from poor water quality. Furthermore, over the next 25 years, the number of people affected by severe water shortages is expected to increase fourfold. Low cost methods to desalinate brackish water and sea water can help reverse this destabilizing trend. Desalination has now been practiced on a large scale for more than 50 years. During this time continual improvements have been made, and the major technologies are now remarkably efficient, reliable, and inexpensive. For many years, thermal technologies were the only viable option, and multi-stage flash (MSF) was established as the baseline technology. Multi-effect evaporation (MEE) is now the state-of-the-art thermal technology, but has not been widely implemented. With the growth of membrane science, reverse osmosis (RO) overtook MSF as the leading desalination technology, and should be considered the baseline technology. Presently, RO of seawater can be accomplished with an energy expenditure in the range of 11-60 kJ/kg at a cost of $2 to $4 per 1000 gallons. The theoretical minimum energy expenditure is 3-7 kJ/kg. Since RO is a fairly mature technology, further improvements are likely to be incremental in nature, unless design improvements allow major savings in capital costs. Therefore, the best hope to dramatically decrease desalination costs is to develop ''out of the box'' technologies. These ''out of the box'' approaches must offer a significant advantage over RO (or MEE, if waste heat is available) if they are to be viable. When making these comparisons, it is crucial that the specifics of the calculation are understood so that the comparison is made on a fair and equivalent basis.

  6. 78 FR 49305 - Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-13

    ... COMMISSION Luminant Generation Company LLC, Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2; Application... Operating Reactor Licensing, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission... Nuclear Power Plant, Unit Nos. 1 and 2, respectively, located in Somervell County, Texas. The...

  7. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FOR NUCLEAR POWER PLANTS Pt. 52, App. N Appendix N to Part 52—Standardization of Nuclear Power...

  8. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FOR NUCLEAR POWER PLANTS Pt. 52, App. N Appendix N to Part 52—Standardization of Nuclear Power...

  9. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FOR NUCLEAR POWER PLANTS Pt. 52, App. N Appendix N to Part 52—Standardization of Nuclear Power...

  10. Confirmation of the seismic resistance of nuclear power plant equipment after assembly

    SciTech Connect

    Kaznovsky, P. S.; Kaznovsky, A. P.; Saakov, E. S.; Ryasnyj, S. I.

    2013-05-15

    It is shown that the natural frequencies and damping decrements of nuclear power plant equipment can only be determined experimentally and directly at the power generation units (reactors) of nuclear power plants under real disassembly conditions for the equipment, piping network, thermal insulation, etc. A computational experimental method is described in which the natural frequencies and damping decrements are determined in the field and the seismic resistance is reevaluated using these values. This method is the basis of the standards document 'Methods for confirming the dynamic characteristics of systems and components of the generating units of nuclear power plants which are important for safety' prepared and introduced in 2012.

  11. Dose estimation for nuclear power plant 4 accident in Taiwan at Fukushima nuclear meltdown emission level.

    PubMed

    Tang, Mei-Ling; Tsuang, Ben-Jei; Kuo, Pei-Hsuan

    2016-05-01

    An advanced Gaussian trajectory dispersion model is used to evaluate the evacuation zone due to a nuclear meltdown at the Nuclear Power Plant 4 (NPP4) in Taiwan, with the same emission level as that occurred at Fukushima nuclear meltdown (FNM) in 2011. Our study demonstrates that a FNM emission level would pollute 9% of the island's land area with annual effective dose ≥50 mSv using the meteorological data on 11 March 2011 in Taiwan. This high dose area is also called permanent evacuation zone (denoted as PEZ). The PEZ as well as the emergency-planning zone (EPZ) are found to be sensitive to meteorological conditions on the event. In a sunny day under the dominated NE wind conditions, the EPZ can be as far as 100 km with the first 7-day dose ≥20 mSv. Three hundred sixty-five daily events using the meteorological data from 11 March 2011 to 9 March 2012 are evaluated. It is found that the mean land area of Taiwan in becoming the PEZ is 11%. Especially, the probabilities of the northern counties/cities (Keelung, New Taipei, Taipei, Taoyuan, Hsinchu City, Hsinchu County and Ilan County) to be PEZs are high, ranging from 15% in Ilan County to 51% in Keelung City. Note that the total population of the above cities/counties is as high as 10 million people. Moreover, the western valleys of the Central Mountain Range are also found to be probable being PEZs, where all of the reservoirs in western Taiwan are located. For example, the probability can be as high as 3% in the far southern-most tip of Taiwan Island in Pingtung County. This shows that the entire populations in western Taiwan can be at risk due to the shortage of clean water sources under an event at FNM emission level, especially during the NE monsoon period. PMID:26913979

  12. Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability

    SciTech Connect

    Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

    1986-03-01

    This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants.

  13. Nuclear power plant licensing: jurisdiction to consider foreign impacts

    SciTech Connect

    Silver, M.

    1983-01-01

    Natural Resources Defense Council (NRDC), Inc. v. Nuclear Regulatory Commission (NRC) challenges NRC's approval for Westinghouse to ship a nuclear reactor and nuclear materials to the Philippines. The NRDC contends that the NRC lacks jurisdiction over political and environmental decisions in a foreign country. Background evidence indicates the Philippines would meet US nonproliferation goals, but the decision in favor of NRC does not set a precedent jeopardizing future health and safety reviews of nuclear exports. 63 references. (DCK)

  14. Assessment of next generation nuclear plant intermediate heat exchanger design.

    SciTech Connect

    Majumdar, S.; Moisseytsev, A.; Natesan, K.; Nuclear Engineering Division

    2008-10-17

    The Next Generation Nuclear Plant (NGNP), which is an advanced high temperature gas reactor (HTGR) concept with emphasis on production of both electricity and hydrogen, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000 C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the vary high temperature reactor (VHTR) can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K. This report has made an assessment on the issues pertaining to the intermediate heat exchanger (IHX) for the NGNP. A detailed thermal hydraulic analysis, using models developed at ANL, was performed to calculate heat transfer, temperature distribution, and pressure drop. Two IHX designs namely, shell and straight tube and compact heat exchangers were considered in an earlier assessment. Helical coil heat exchangers were analyzed in the current report and the results were compared with the performance features of designs from industry. In addition, a comparative analysis is presented between the shell and straight tube, helical, and printed circuit heat exchangers from the standpoint of heat exchanger volume, primary and secondary sides pressure drop, and number of tubes. The IHX being a high temperature component, probably needs to be designed using ASME Code Section III, Subsection NH, assuming that the IHX will be classified as a class 1 component. With input from thermal hydraulic calculations performed at ANL, thermal conduction and stress analyses were performed for the helical heat exchanger design and the results were compared with earlier-developed results on

  15. Protein targeting to the nuclear pore. What can we learn from plants. [Nuclear pore complex

    SciTech Connect

    Smith, H.M.S.; Raikhel, N.V. . DOE Plant Research Lab.)

    1999-04-01

    Characteristic of eukaryotic cells are the numerous types of membrane-bound organelles or compartments found in the cytoplasm, with each type carrying out an essential function for the cell. The spatial separation of proteins and biochemical pathways typical of the various types of organelles requires selective targeting apparatuses. Because each type of organelle contains its own targeting apparatus, proteins destined for a particular organelle must contain the proper targeting signal(s) for entry. These signal-dependent targeting pathways ensure that proteins are targeted to the proper organelle. Understanding how proteins are targeted to the different types of organelles is an important goal in the field of cell biology. In plants recent studies have highlighted a number of unusual features, and as the understanding of import in plants increases, the authors have gained new insights, such as a model for the targeting of proteins from the cytoplasm to the NPC. These advances will contribute to further expansion of the knowledge of nuclear import in eukaryotes.

  16. Contribution of Anticipated Transients Without Scram (ATWS) to core melt at United States nuclear power plants

    SciTech Connect

    Giachetti, R.T. , Ann Arbor, MI )

    1989-09-01

    This report looks at WASH-1400 and several other Probabilistic Risk Assessments (PRAs) and Probabilistic Safety Studies (PSSs) to determine the contribution of Anticipated Transients Without Scram (ATWS) events to the total core melt probability at eight nuclear power plants in the United States. After considering each plant individually, the results are compared from plant to plant to see if any generic conclusions regarding ATWS, or core melt in general, can be made. 8 refs., 34 tabs.

  17. Trial application of guidelines for nuclear plant response to an earthquake. Final report

    SciTech Connect

    Schmidt, W.; Oliver, R.; O`Connor, W.

    1993-09-01

    Guidelines have been developed to assist nuclear plant personnel in the preparation of earthquake response procedures for nuclear power plants. These guidelines are published in EPRI report NP-6695, ``Guidelines for Nuclear Plant Response to an Earthquake,`` dated December 1989. This report includes two sets of nuclear plant procedures which were prepared to implement the guidelines of EPRI report NP-6695. The first set were developed by the Toledo Edison Company Davis-Besse plant. Davis-Besse is a pressurized water reactor (PWR) and contains relatively standard seismic monitoring instrumentation typical of many domestic nuclear plants. The second set of procedures were prepared by Yankee Atomic Electric Company for the Vermont Yankee facility. This plant is a boiling water reactor (BWR) with state-of-the-art seismic monitoring and PC-based data processing equipment, software developed specifically to implement the OBE Exceedance Criterion presented in EPRI report NP-5930, ``A Criterion for Determining Exceedance of the operating Basis Earthquake.`` The two sets of procedures are intended to demonstrate how two different nuclear utilities have interpreted and applied the EPRI guidance given in report NP-6695.

  18. Overview of United States Department of Energy activities to support life extension of nuclear power plants

    SciTech Connect

    Harrison, D.L.; Rosinski, S.T.

    1993-11-01

    Today, 109 nuclear power plants provide over 20 percent of the electrical energy generated in the US The operating license of the first of these plants will expire in the year 2000; one-third of the operating licenses will expire by 2010 and the remaining plant licenses are scheduled to expire by 2033. The National Energy Strategy assumes that 70 percent of these plants will continue to operate beyond their current license expiration to assist in ensuring an adequate, diverse, and environmentally acceptable energy supply for economic growth. In order to preserve this energy resource in the US three major tasks must be successfully completed: establishment of regulations, technical standards, and procedures for the preparation and review of a license renewal application; development, verification, and validation of technical criteria and bases for monitoring, refurbishing, and/or replacing plant equipment; and demonstration of the regulatory process. Since 1985, the US Department of Energy (DOE) has been working with the nuclear industry and the US Nuclear Regulatory Commission (NRC) to establish and demonstrate the option to extend the life of nuclear power plants through the renewal of operating licenses. This paper focuses primarily on DOE`s Plant Lifetime Improvement (PLIM) Program efforts to develop the technical criteria and bases for effective aging management and lifetime improvement for continued operation of nuclear power plants. This paper describes current projects to resolve generic technical issues in the principal areas of reactor pressure vessel (RPV) integrity, fatigue, and environmental qualification (EQ).

  19. DC power transmission from the Leningradskaya Nuclear Power Plant to Vyborg

    SciTech Connect

    Koshcheev, L. A.; Shul'ginov, N. G.

    2011-05-15

    DC power transmission from the Leningradskaya Nuclear Power Plant (LAES) to city of Vyborg is proposed. This will provide a comprehensive solution to several important problems in the development and control of the unified power system (EES) of Russia.

  20. Computer program for afterheat temperature distribution for mobile nuclear power plant

    NASA Technical Reports Server (NTRS)

    Parker, W. G.; Vanbibber, L. E.

    1972-01-01

    ESATA computer program was developed to analyze thermal safety aspects of post-impacted mobile nuclear power plants. Program is written in FORTRAN 4 and designed for IBM 7094/7044 direct coupled system.