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Sample records for lwr systems semiannual

  1. Long-term embrittlement of cast duplex stainless steels in LWR systems. Semiannual report, April--September 1992: Volume 7, No. 2

    SciTech Connect

    Chopra, O.K.

    1993-07-01

    This progress report summarizes work performed by Argonne National Laboratory on longterm thermal embrittlement of cast duplex stainless steels in LWR systems during the six months from April--September 1992. A procedure and correlations are presented for predicting Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, tearing modulus, and J{sub IC} of aged cast stainless steels from known material information. The ``saturation`` impact strength and fracture toughness of a specific cast stainless steel, i.e., the minimum value that would be achieved for the material after long-term service, is estimated from the chemical composition of the steel. Mechanical properties as a function of time and temperature of reactor service are estimated from impact energy and flow stress of the unaged material and the kinetics of embrittlement, which are also determined from chemical composition. The J{sub IC} values are determined from the estimated J-R curve and flow stress. Examples of estimating mechanical properties of cast stainless steel components during reactor service are presented. A common ``lower-bound`` J-R curve for cast stainless steels of unknown chemical composition is also defined for a given grade of steel, ferrite content, and temperature.

  2. Long-term embrittlement of cast duplex stainless steels in LWR systems. Semiannual report, October 1991--March 1992: Volume 7, No.1

    SciTech Connect

    Chopra, O.K.

    1993-05-01

    This progress report summarizes work performed by Argonne National Laboratory on long-term thermal embrittlement of cast duplex stainless steels in LWR systems during the six months from October 1991 to March 1992. Charpy-impact, tensile, and fracture toughness J-R curve data are presented for several heats of cast stainless steel that were aged 10,000-58,000 h at 290, 320, and 350{degree}C. The results indicate that thermal aging decreases the fracture toughness of cast stainless steels. In general, CF-3 steels are the least sensitive to thermal aging and CF-8M steels are the most sensitive. The values of fracture toughness J{sub IC} and tearing modulus for CF-8M steels can be as low as {approx}90 kJ/m{sup 2} and {approx}60, respectively. The fracture toughness data are consistent with the Charpy-impact results, i.e. unaged and aged steels that show low impact energy also exhibit lower fracture toughness. All steels reach a minimum saturation fracture toughness after thermal aging; the time to reach saturation depends on the aging temperature. The results also indicate that low-strength cast stainless steels are generally insensitive to thermal aging.

  3. Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study

    SciTech Connect

    Kristine Barrett; Shannon Bragg-Sitton

    2012-09-01

    The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R&D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental improvements are required in the areas of nuclear fuel composition, cladding integrity, and the fuel/cladding interaction to allow power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an “accident tolerant” fuel system that would offer improved coping time under accident scenarios. With a development time of about 20 – 25 years, advanced fuel designs must be started today and proven in current reactors if future reactor designs are to be able to use them with confidence.

  4. Ice Thermal Storage Systems for LWR Supplemental Cooling and Peak Power Shifting

    SciTech Connect

    Haihua Zhao; Hongbin Zhang; Phil Sharpe; Blaise Hamanaka; Wei Yan; WoonSeong Jeong

    2010-06-01

    Availability of enough cooling water has been one of the major issues for the nuclear power plant site selection. Cooling water issues have frequently disrupted the normal operation at some nuclear power plants during heat waves and long draught. The issues become more severe due to the new round of nuclear power expansion and global warming. During hot summer days, cooling water leaving a power plant may become too hot to threaten aquatic life so that environmental regulations may force the plant to reduce power output or even temporarily to be shutdown. For new nuclear power plants to be built at areas without enough cooling water, dry cooling can be used to remove waste heat directly into the atmosphere. However, dry cooling will result in much lower thermal efficiency when the weather is hot. One potential solution for the above mentioned issues is to use ice thermal storage systems (ITS) that reduce cooling water requirements and boost the plant’s thermal efficiency in hot hours. ITS uses cheap off-peak electricity to make ice and uses those ice for supplemental cooling during peak demand time. ITS is suitable for supplemental cooling storage due to its very high energy storage density. ITS also provides a way to shift large amount of electricity from off peak time to peak time. Some gas turbine plants already use ITS to increase thermal efficiency during peak hours in summer. ITSs have also been widely used for building cooling to save energy cost. Among three cooling methods for LWR applications: once-through, wet cooling tower, and dry cooling tower, once-through cooling plants near a large water body like an ocean or a large lake and wet cooling plants can maintain the designed turbine backpressure (or condensation temperature) during 99% of the time; therefore, adding ITS to those plants will not generate large benefits. For once-through cooling plants near a limited water body like a river or a small lake, adding ITS can bring significant economic

  5. Development of an integrated, unattended assay system for LWR-MOX fuel pellet trays

    SciTech Connect

    Stewart, J.E.; Hatcher, C.R.; Pollat, L.L.

    1994-08-01

    Four identical unattended plutonium assay systems have been developed for use at the new light-water-reactor mixed oxide (LWR-MOX) fuel fabrication facility at Hanau, Germany. The systems provide quantitative plutonium verification for all MOX pellet trays entering or leaving a large, intermediate store. Pellet-tray transport and storage systems are highly automated. Data from the ``I-Point`` (information point) assay systems will be shared by the Euratom and International Atomic Energy Agency (IAEA) Inspectorates. The I-Point system integrates, for the first time, passive neutron coincidence counting (NCC) with electro-mechanical sensing (EMS) in unattended mode. Also, provisions have been made for adding high-resolution gamma spectroscopy. The system accumulates data for every tray entering or leaving the store between inspector visits. During an inspection, data are analyzed and compared with operator declarations for the previous inspection period, nominally one month. Specification of the I-point system resulted from a collaboration between the IAEA, Euratom, Siemens, and Los Alamos. Hardware was developed by Siemens and Los Alamos through a bilateral agreement between the German Federal Ministry of Research and Technology (BMFT) and the US DOE. Siemens also provided the EMS subsystem, including software. Through the USSupport Program to the IAEA, Los Alamos developed the NCC software (NCC COLLECT) and also the software for merging and reviewing the EMS and NCC data (MERGE/REVIEW). This paper describes the overall I-Point system, but emphasizes the NCC subsystem, along with the NCC COLLECT and MERGE/REVIEW codes. We also summarize comprehensive testing results that define the quality of assay performance.

  6. LWR (Light Water Reactor) power plant simulations using the AD10 and AD100 systems

    SciTech Connect

    Wulff, W.; Cheng, H.S.; Chien, C.J.; Jang, J.Y.; Lin, H.C.; Mallen, A.N.; Wang, S.J.; Institute of Nuclear Energy Research, Lung-Tan; Tawian Power Co., Taipei; Brookhaven National Lab., Upton, NY; Institute of Nuclear Energy Research, Lung-Tan )

    1989-01-01

    Boiling (BWR) and Pressurized (PWR) Water Reactor Power Plants are being simulated at BNL with the AD10 and AD100 Peripheral Processor Systems. The AD10 system has been used for BWR simulations since 1984 for safety analyses, emergency training and optimization studies. BWR simulation capabilities have been implemented recently on the AD100 system and PWR simulation capabilities are currently being developed under the auspices of international cooperation. Modeling and simulation methods are presented with emphasis on the simulation of the Nuclear Steam Supply System. Results are presented for BWR simulation and performance characteristics are compared of the AD10 and AD100 systems. It will be shown that the AD100 simulates two times faster than two AD10 processors operating in parallel and that the computing capacity of one AD100 (with FMU processor) is twice as large as that of two AD10 processors. 9 refs., 5 figs., 1 tab.

  7. RELAP5 two-phase fluid model and numerical scheme for economic LWR system simulation

    SciTech Connect

    Ransom, V.H.; Wagner, R.J.; Trapp, J.A.

    1981-01-01

    The RELAP5 two-phase fluid model and the associated numerical scheme are summarized. The experience accrued in development of a fast running light water reactor system transient analysis code is reviewed and example of the code application are given.

  8. Experience with non-fuel-bearing components in LWR (light-water reactor) fuel systems

    SciTech Connect

    Bailey, W.J.; Berting, F.M.

    1990-12-01

    Many non-fuel-bearing components are so closely associated with the spent fuel assemblies that their integrity and behavior must be taken into consideration with the fuel assemblies, when handling spent fuel of planning waste management activities. Presented herein is some of the experience that has been gained over the past two decades from non-fuel-bearing components in light-water reactors (LWRs), both pressurized-water reactors (PWRs) and boiling-water reactors (BWRs). Among the most important of these components are the control rod systems, the absorber and burnable poison rods, and the fuel assembly channels. 15 refs., 5 figs., 2 tabs.

  9. Hydrogen-control systems for severe LWR accident conditions - a state-of-technology report

    SciTech Connect

    Hilliard, R K; Postma, A K; Jeppson, D W

    1983-03-01

    This report reviews the current state of technology regarding hydrogen safety issues in light water reactor plants. Topics considered in this report relate to control systems and include combustion prevention, controlled combustion, minimization of combustion effects, combination of control concepts, and post-accident disposal. A companion report addresses hydrogen generation, distribution, and combustion. The objectives of the study were to identify the key safety issues related to hydrogen produced under severe accident conditions, to describe the state of technology for each issue, and to point out ongoing programs aimed at resolving the open issues.

  10. Integrated High Temperature Coal to Hydrogen System with CO2 Separation: Semi-Annual Progress Report 1

    SciTech Connect

    Ruud, J A; Ku, A; Ramaswamy, V; Wei, W

    2005-12-21

    This is the first semi-annual progress report for the program "Integrated High Temperature Coal to Hydrogen System with CO2 Separation." The objective of the program is to develop a detailed design for a single high-temperature syngas-cleanup module to produce a pure stream of H2 from a coal-based system and to develop the new high-temperature membrane materials at the core of that design. The novel one-box process combines a shift reactor with a high-temperature CO2-selective membrane to convert CO to CO2, remove sulfur compounds, and remove CO2 in a simple, compact, fully integrated system. In the first six months of the program, a conceptual design for the one-box system was developed in Task 1 and the performance targets for the system and the membrane were evaluated. In Task 2.1 processes were developed for creating pore architectures in ceramics that are applicable to membrane structures. In Task 2.2, candidate materials were identified that have the potential for separation of CO2 and H2S at high temperatures.

  11. Enhanced Accident Tolerant LWR Fuels: Metrics Development

    SciTech Connect

    Shannon Bragg-Sitton; Lori Braase; Rose Montgomery; Chris Stanek; Robert Montgomery; Lance Snead; Larry Ott; Mike Billone

    2013-09-01

    The Department of Energy (DOE) Fuel Cycle Research and Development (FCRD) Advanced Fuels Campaign (AFC) is conducting research and development on enhanced Accident Tolerant Fuels (ATF) for light water reactors (LWRs). This mission emphasizes the development of novel fuel and cladding concepts to replace the current zirconium alloy-uranium dioxide (UO2) fuel system. The overall mission of the ATF research is to develop advanced fuels/cladding with improved performance, reliability and safety characteristics during normal operations and accident conditions, while minimizing waste generation. The initial effort will focus on implementation in operating reactors or reactors with design certifications. To initiate the development of quantitative metrics for ATR, a LWR Enhanced Accident Tolerant Fuels Metrics Development Workshop was held in October 2012 in Germantown, MD. This paper summarizes the outcome of that workshop and the current status of metrics development for LWR ATF.

  12. Securities and Exchange Commission Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-26

    ... [Securities and Exchange Commission Semiannual Regulatory Agenda ] Part XXIII Securities and Exchange Commission Semiannual Regulatory Agenda ] SECURITIES AND EXCHANGE COMMISSION (SEC) SECURITIES AND EXCHANGE COMMISSION 17 CFR Ch. II Regulatory Flexibility Agenda AGENCY: Securities and Exchange Commission. ACTION: Semiannual regulatory...

  13. MCNP LWR Core Generator

    SciTech Connect

    Fischer, Noah A.

    2012-08-14

    The reactor core input generator allows for MCNP input files to be tailored to design specifications and generated in seconds. Full reactor models can now easily be created by specifying a small set of parameters and generating an MCNP input for a full reactor core. Axial zoning of the core will allow for density variation in the fuel and moderator, with pin-by-pin fidelity, so that BWR cores can more accurately be modeled. LWR core work in progress: (1) Reflectivity option for specifying 1/4, 1/2, or full core simulation; (2) Axial zoning for moderator densities that vary with height; (3) Generating multiple types of assemblies for different fuel enrichments; and (4) Parameters for specifying BWR box walls. Fuel pin work in progress: (1) Radial and azimuthal zoning for generating further unique materials in fuel rods; (2) Options for specifying different types of fuel for MOX or multiple burn assemblies; (3) Additional options for replacing fuel rods with burnable poison rods; and (4) Control rod/blade modeling.

  14. Subtask 3.12 -- Small power systems. Semi-annual report, January 1--June 30, 1996

    SciTech Connect

    1997-08-01

    The programmatic goal in advanced power systems is to develop small integrated waste treatment, water purification, and power systems in the range of 20 kW to 20 MW in cooperation with commercial vendors. These systems will be designed to incorporate the advanced technical capabilities of the Energy and Environmental Research Center (EERC) with the latest advancement in vendor-offered hardware and software. The primary objective for the work to be performed under this subtask is to develop a commercialization plan for small power systems, evaluate alternative design concepts, and select practical and economical designs for targeted development in upcoming years. A leading objective for the EERC will be to continue to form strong business partnerships with equipment manufacturers who can commercialize the selected power system and treatment design(s). FY95 activities were focused on collecting information from vendors and evaluating alternative design concepts. This year`s activities began with the process of selecting one or more designs for targeted development. Once the design(s) are selected, specific technical requirements will be defined that will be the subject of focused studies to overcome technical barriers to achieving a clean, cost-effective generating system. During this program year, the technical barriers limiting the use of the selected technology in the small power system market will be identified. A plan will be devised to overcome these barriers. Also during this program year, strong business partnerships will be developed between the EERC, Morgantown Energy Technology Center (METC), and equipment manufacturers who can commercialize the selected power system(s). A plan will be created for rapid development leading to commercialization. This may involve integration of this task with other research activities currently ongoing at the EERC and METC.

  15. Task 3.0: Advanced power systems. Semi-annual report, April 1--June 30, 1993

    SciTech Connect

    McCollor, D.P.; Zygarlicke, C.J.; Mann, M.D.; Willson, W.G.; Hurley, J.P.

    1993-07-01

    A variety of activities are incorporated into the Advanced Power Systems program. Tasks included are (1) fuel utilization properties, (2) pressurized combustion, (3) catalytic gasification, and (4) hot-gas cleanup. ATRAN is stochastic and combines initial coal inorganics in a random manner in order to predict the resulting fly ash particle size and composition. ASHPERT, is an expert system yielding a first-order estimate of fly ash size and composition. Both models are designed to emulate pulverized-coal combustion. Input data required include identity, chemistry, size, quantity, and mineral-to-coal associations. The pressurized combustion task has focused on the construction of a versatile reactor system to simulate pressurized fluidized-bed combustion. Both castable and monolithic refractories have been investigated in determining slag prevention under a variety of conditions. Catalytic gasification coupled with a molten carbonate fuel cell offers an extremely efficient and environmentally sound power generating system using coal. Work with an Illinois No. 6 bituminous coal has not been successful. Continued efforts will focus on using the more reactive low-rank coals to try to achieve this goal. Hot-gas cleanup is the critical issue in many of the proposed advanced power system operations on coal. The key to successful ash removal is an understanding of the properties of the ash to be collected as well as the interactions of this material with the barrier itself. The knowledge base under development will assist in assessing many of these barrier material issues for a variety of coal ashes.

  16. Fluidized-Bed Waste-Heat Recovery System development. Semiannual report, February 1-July 31, 1982

    SciTech Connect

    Cole, W. E.; DeSaro, R.; Griffith, J.; Joshi, C.

    1982-08-01

    The Fluidized-Bed Waste-Heat Recovery (FBWHR) System is designed to preheat this combustion air using the heat available in dirty flue gas streams. In this system, a recirculating medium is heated by the flue gas in a fluidized bed. The hot medium is then removed from the bed and placed in a second fluidized bed where it is fluidized by the combustion air. Through this process, the combustion air is heated. The cooled medium is then returned to the first bed. Initial development of this concept is for the aluminum smelting industry.

  17. Heavy vehicle propulsion system materials program semiannual progress report for April 1999 through September 1999

    SciTech Connect

    Johnson, D.R.

    2000-01-01

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks.

  18. HTGR applications program advanced systems. Semiannual report, October 1, 1982-March 31, 1983

    SciTech Connect

    1983-05-01

    Work Breakdown Structure (WBS 41) activities emphasize the advanced HTGR modular reactor system (MRS) for reformer (R) and steam cycle/-cogeneration (SC/C) applications. This report describes progress in system performance for a 250-MW(t) MRS-R and a 300-MW(t) MRS-SC/C plant; it details the groundrules and parameters for the FY-83 nuclear core design and examines and compares fuel cycle economics. This report gives results from a study on decay heat removal transients for the MRS-R and MRS-SC/C variants. It evaluates the bypass valve system and the number and location of helium circulators, and it describes the progress on circulator component design, a prestressed concrete vessel steel closure design, and plant licensing and safety. Under the Advanced Technology Transfer Task (WBS 15), this report includes a section on a pebble bed reactor (PBR) MRS core heatup thermal model analysis. This report also gives the results of a survey on candidate reformer tube materials from GA Technologies Inc. to identify acceptable substitute materials for Inconel 617 to alleviate possible cobalt activation and carburization problems.

  19. Propulsion System Materials Program semiannual progress report for April 1995 through September 1995

    SciTech Connect

    1996-04-01

    Significant accomplishments in fabricating ceramic components for the DOE, NASA, and DOD advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. These programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and data base and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially. An assessment of needs was completed, and a 5-year program plan was developed with extensive input from private industry. During the course of the Propulsion System Materials Program, remarkable progress has been made in the development of reliable structural ceramics. However, further work is needed to reduce the cost of ceramics to facilitate their commercial introduction, especially in the highly cost-sensitive automotive market. To this end, the direction of the Propulsion System Materials Program is now shifting toward reducing the cost of ceramics to facilitate commercial introduction of ceramic components for near-term engine applications. In response to extensive input from industry, the plan is to extend the engine types which were previously supported to include near-term (5--10 years) applications in conventional automobile and diesel truck engines. To facilitate the rapid transfer of this technology to US industry, the major portion of the work is being done in the ceramic industry, with technological support from government laboratories, other industrial laboratories, and universities. A systematic approach to reducing the cost of components is envisioned. The work elements are as follows: economic cost modeling, ceramic machining, powder synthesis, alternative forming and densification processes, yield improvement, system design studies, standards development, low-expansion ceramics, and testing and data base development.

  20. Heavy vehicle propulsion system materials program semiannual progress report for April 1998 thru September 1998

    SciTech Connect

    Johnson, D.R.

    1999-01-01

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1--3 trucks to realize a 35{percent} fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7--8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55{percent} efficiency and low emissions levels of 2.0 g/bhp-h NO{sub x} and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55{percent} efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy-duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies.

  1. Microfabricated DNA analysis system. Semi-annual report, August 1993--January 1994

    SciTech Connect

    Northrup, M.A.

    1994-01-01

    We are miniaturizing instrumentation for the polymerase chain reaction (PCR) -- a bioanalytical technique that amplifies target sections of DNA through thermal cycling. This report focuses on delineating reaction chamber, design parameters through computer modeling and infrared imaging. We have also continued micro-chamber-based PCR experiments and have successfully amplified three different targets from two different biological sources. Specifically, we have amplified DNA from {beta}-globin (a subunit of hemoglobin), and two different-sized targets from the Human Immunodeficiency Virus (HIV). These experiments were performed in newly-designed chambers. Reaction chambers are also being designed with detection in mind, specifically for the detection of fluorescent DNA labels. Finally, some new developments in PCR technology are described as they represent potential biological diagnostics to be evaluated in microfabricated DNA analysis systems.

  2. Heavy vehicle propulsion system materials program: Semiannual progress report, April 1996--September 1996

    SciTech Connect

    Johnson, D.R.

    1997-04-01

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55% efficiency and low emissions levels of 2.0 g/bhp-h NO{sub x} and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55% efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies. OTT OHVT also recognizes a significant opportunity for reduction in petroleum consumption by dieselization of pickup trucks, vans, and sport utility vehicles. Application of the diesel engine to class 1, 2, and 3 trucks is expected to yield a 35% increase in fuel economy per vehicle. The foremost barrier to diesel use in this market is emission control. Once an engine is made certifiable, subsequent challenges will be in cost; noise, vibration, and harshness (NVH); and performance. Separate abstracts have been submitted to the database for contributions to this report.

  3. Heavy Vehicle Propulsion System Materials Program Semiannual Progress Report for October 1998 Through March 1999

    SciTech Connect

    Johnson, R.D.

    1999-06-01

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OIT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55% efficiency and low emissions levels of 2.0 g/bhp-h NOX and 0.05 g/bhp-h particulate. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55% efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies. OIT OHVT also recognizes a significant opportunity for reduction in petroleum consumption by dieselization of pickup trucks, vans, and sport utility vehicles. Application of the diesel engine to class 1,2, and 3 trucks is expected to yield a 35% increase in fuel economy per vehicle. The foremost barrier to diesel use in this market is emission control. Once an engine is made certifiable, subsequent challenges will be in cost; noise, vibration, and harshness (NVH); and performance. The design of advanced components for high-efficiency diesel engines has, in some cases, pushed the performance envelope for materials of construction past the point of reliable operation. Higher mechanical and

  4. Heavy Vehicle Propulsion System Materials Program Semiannual Progress Report for April 2000 Through September 2000

    SciTech Connect

    Johnson, DR

    2000-12-11

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advantages LE-55 diesel engines with 55% efficiency and low emissions levels of 2.0 g/bhp-h NOx and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55% efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies. OTT OHVT also recognizes a significant opportunity for reduction in petroleum consumption by dieselization of pickup trucks, vans, and sport utility vehicles. Application of the diesel engine to class 1, 2, and 3 trucks is expected to yield a 35% increase in fuel economy per vehicle. The foremost barrier to diesel use in this market is emission control. Once an engine is made certifiable, subsequent challenges will be in cost; noise, vibration, and harshness (NVH); and performance. The design of advanced components for high-efficiency diesel engines has, in some cases, pushed the performance envelope for materials of construction past the point of reliable operation. Higher mechanical and

  5. Heavy Vehicle Propulsion System Materials Program semiannual progress report for October 1996 through March 1997

    SciTech Connect

    1997-07-01

    The purpose of the Heavy Vehicle Propulsion System Materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1-3 trucks to realize a 35% fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7-8 trucks. The design of advanced components for high-efficiency diesel engines has, in some cases, pushed the performance envelope for materials of construction past the point of reliable operation. Higher mechanical and tribological stresses and higher temperatures of advanced designs limit the engine designers; advanced materials allow the design of components that may operate reliably at higher stresses and temperatures, thus enabling more efficient engine designs. Advanced materials also offer the opportunity to improve the emissions, NVH, and performance of diesel engines for pickup trucks, vans, and sport utility vehicles. The principal areas of research are: (1) cost effective high performance materials and processing; (2) advanced manufacturing technology; (3) testing and characterization; and (4) materials and testing standards.

  6. Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project

    SciTech Connect

    Brian G. Williams; Jim C. P. Liou; Hiral Kadakia; Bill Phoenix; Richard R. Schultz

    2007-02-27

    This project characterizes typical two-phase stratified flow conditions in advanced water reactor horizontal pipe sections, following activation of passive cooling systems. It provides (1) a means to educate nuclear engineering students regarding the importance of two-phase stratified flow in passive cooling systems to the safety of advanced reactor systems and (2) describes the experimental apparatus and process to measure key parameters essential to consider when designing passive emergency core cooling flow paths that may encounter this flow regime. Based on data collected, the state of analysis capabilities can be determined regarding stratified flow in advanced reactor systems and the best paths forward can be identified to ensure that the nuclear industry can properly characterize two-phase stratified flow in passive emergency core cooling systems.

  7. LWR improvement in EUV resist process

    NASA Astrophysics Data System (ADS)

    Koh, Chawon; Kim, Hyun-Woo; Kim, Sumin; Na, Hai-Sub; Park, Chang-Min; Park, Cheolhong; Cho, Kyoung-Yong

    2011-04-01

    Extreme ultraviolet lithography (EUVL) is the most effective way to print sub-30 nm features. The roughness of both the resist sidewall (line width roughness [LWR]) and resist top must be overcome soon for EUVL to be implemented. Currently, LWR can vary by about 1 nm according to the recipe used. We have characterized two promising techniques to improve LWR, an EUV rinse/TBAH process and an implant process, and demonstrated their efficacy. After cleaning inspection (ACI), LWR was improved with both the rinse and implant processes. After development inspection (ADI), LWR improved (0.12 nm, 2.4%) and ACI LWR improved (0.1 nm, 2.0% improvement) after using the EUV rinse process. ADI and ACI LWR improvement (0.45 nm, 9.1%, and 0.3 nm, 6.9%, respectively) was demonstrated with the EUV rinse/TBAH process. ADI LWR improvement (0.5 nm, 8.1%) and ACI LWR improvement (-0.5 nm, -16.9%) were characterized with the implant process. Critical dimension (CD) showed similar changes through pitch after the EUV rinse or TBAH process, but the degree of change depended on the initial pattern size giving CD difference of 2 nm between 30 nm HP and 50 nm HP after the implant process. For this technique, the dependence of CD change on pattern size must be minimized. Further extensive studies with rinse or implant are strongly encouraged for continued LWR improvement and real process implementation in EUVL. Demonstrating <2.2 nm LWR after pattern transfer is important in EUVL and needs to be pursued using various technical approaches. Initial resist LWR is important in assessing LWR improvements with additional process techniques. An initial EUV LWR < ~5.0 nm is required to properly assess the validity of the technique. Further study is required to improve ADI LWR and maintain better LWR after etch with advanced EUV rinse materials. Defects also need to be confirmed following the EUV rinse and TBAH developer. Further developing the implant process should focus on LWR improvement at low

  8. Incineration of LWR-type waste at Mound Facility

    SciTech Connect

    Alexander, B.M.; Grimm, R.S.; Doty, J.W. Jr.

    1980-01-01

    The Mound Cyclone Incinerator, demonstrated over several years for the combustion of radwaste containing plutonium, is now being developed for volume reduction of radwaste containing mixed beta- and gamma-emitters, from LWR facilities. To this end, a laboratory-scale feasibility study was developed and executed. Development of the feasibility study was based on known characteristics of LWR waste and on operating data compiled for the Mound Cyclone Incinerator since 1975. Feed spiked with several isotopes found in LWR waste was burned in the laboratory-scale cyclone incinerator, and samples were collected and analyzed. From these data, the applicability of cyclone incineration was demonstrated, and an efficient scrub liquor composition was chosen for the offgas treatment system. A Health Physics survey of the incinerator system after incineration of 220 ..mu..Ci of beta/gamma activity showed no exposure readings above background level. Future work planned includes incineration of simulated LWR waste in the full-scale Mound Cyclone Incinerator to begin later this year.

  9. SPACE-R Thermionic Space Nuclear Power System: Design and Technology Demonstration Program. Semiannual technical progress report for period ending March 1993

    SciTech Connect

    Not Available

    1993-05-01

    This Semiannual Technical Progress Report summarizes the technical progress and accomplishments for the Thermionic Space Nuclear Power System (TI-SNPS) Design and Technology Demonstration Program of the Prime Contractor, Space Power Incorporated (SPI), its subcontractors and supporting National Laboratories during the first half of the Government Fiscal Year (GFY) 1993. SPI`s subcontractors and supporting National Laboratories include: Babcock & Wilcox for the reactor core and externals; Space Systems/Loral for the spacecraft integration; Thermocore for the radiator heat pipes and the heat exchanger; INERTEK of CIS for the TFE, core elements and nuclear tests; Argonne National Laboratories for nuclear safety, physics and control verification; and Oak Ridge National laboratories for materials testing. Parametric trade studies are near completion. However, technical input from INERTEK has yet to be provided to determine some of the baseline design configurations. The INERTEK subcontract is expected to be initiated soon. The Point Design task has been initiated. The thermionic fuel element (TFE) is undergoing several design iterations. The reactor core vessel analysis and design has also been started.

  10. 48 CFR 222.406-13 - Semiannual enforcement reports.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Semiannual enforcement reports. 222.406-13 Section 222.406-13 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT OF DEFENSE SOCIOECONOMIC PROGRAMS APPLICATION OF LABOR LAWS TO GOVERNMENT ACQUISITIONS Labor Standards for...

  11. Multiphysics simulations for LWR analysis

    SciTech Connect

    Hamilton, S.; Clarno, K.; Berrill, M.; Evans, T.; Davidson, G.; Lefebvre, R.; Sampath, R.; Hansel, J.; Ragusa, J.; Josey, C.

    2013-07-01

    Accurate prediction of the neutron and temperature distributions within an operating nuclear reactor requires the solution of multiple coupled physics equations. In a light water reactor (LWR), there is a very strong coupling between the power distribution (described by the radiation transport equation) and the temperature and density distributions (described by a thermal diffusion equation in combination with a fluid flow model). This study aims to begin to quantify the impact of such feedback mechanisms as well as identify numerical difficulties associated with such multiphysics problems. A description of the multiphysics model and current solution strategy within the Exnihilo code package for coupling between 3-D radiation transport and 3-D heat transfer is given. Numerical results detailing the effects of varying the nature of the coupling and the impact of mesh refinement for a representative 3x3 pressurized water reactor (PWR) 'mini-assembly' are presented. (authors)

  12. Spatial-temporal patterns and driving mechanisms of semiannual variations in the Philippine Sea

    NASA Astrophysics Data System (ADS)

    Zhao, Jun; Li, Yuanlong; Wang, Fan; Zhai, Fangguo; Yu, Xiaolin

    2012-10-01

    Satellite altimetric sea surface height (SSH) measurements from 1992 through 2010 are used to explore the oceanic semiannual variations in the Philippine Sea (PS). Pronounced semiannual SSH variations are detected within two zonal bands. One lies east of Luzon Strait (19°-22°N) in the northern PS, while the other is southeast of Mindanao coast (4°-7°N) in the southern PS. In the two near-coast boxes where semiannual harmonic amplitude exceeds 4 cm, the northern box (127°-133°E, 19°-22°N) and the southern box (127°-133°E, 4°-7°N), semiannual changes contribute considerably to the total annual SSH variance by 12% and 17%, respectively. Despite prominent SSH variability, the bifurcation latitude of the North Equatorial Current (NBL) exhibits weak fluctuations with a peak-to-peak difference of only 0.3° on semiannual time scale. While the in-phase annual SSH variations between the two boxes work together to enhance annual NBL changes, their out-of-phase semiannual SSH variations offset each other in driving the NBL displacements. Further analysis with a 11/2-layer reduced-gravity model forced by ECMWF wind stress reveals that the observed semiannual SSH variations are primarily driven by local wind forcing in the far western Pacific. Rossby wave signals propagating from the eastern/central Pacific contribute much less due to along-path dispersion and cancellation. Semiannual signals of wind field in the northern PS reflect mainly the semiannual changes of the Asian Monsoon system, while those in the southern PS arise from the combined effects of Monsoon transition and the annual migration of the intertropical convergence zone (ITCZ).

  13. SciDAC's Earth System Grid Center for Enabling Technologies Semi-Annual Progress Report for the Period April 1, 2009 through September 30, 2009

    SciTech Connect

    Williams, Dean N.; Foster, I. T.; Middleton, D. E.

    2009-10-15

    This report summarizes work carried out by the ESG-CET during the period April 1, 2009 through September 30, 2009. It includes discussion of highlights, overall progress, period goals, collaborations, papers, and presentations. To learn more about our project, and to find previous reports, please visit the Earth System Grid Center for Enabling Technologies (ESG-CET) website. This report will be forwarded to the DOE SciDAC program management, the Office of Biological and Environmental Research (OBER) program management, national and international collaborators and stakeholders (e.g., the Community Climate System Model (CCSM), the Intergovernmental Panel on Climate Change (IPCC) 5th Assessment Report (AR5), the Climate Science Computational End Station (CCES), the SciDAC II: A Scalable and Extensible Earth System Model for Climate Change Science, the North American Regional Climate Change Assessment Program (NARCCAP), and other wide-ranging climate model evaluation activities). During this semi-annual reporting period, the ESG-CET team continued its efforts to complete software components needed for the ESG Gateway and Data Node. These components include: Data Versioning, Data Replication, DataMover-Lite (DML) and Bulk Data Mover (BDM), Metrics, Product Services, and Security, all joining together to form ESG-CET's first beta release. The launch of the beta release is scheduled for late October with the installation of ESG Gateways at NCAR and LLNL/PCMDI. Using the developed ESG Data Publisher, the ESG II CMIP3 (IPCC AR4) data holdings - approximately 35 TB - will be among the first datasets to be published into the new ESG enterprise system. In addition, the NCAR's ESG II data holdings will also be published into the new system - approximately 200 TB. This period also saw the testing of the ESG Data Node at various collaboration sites, including: the British Atmospheric Data Center (BADC), the Max-Planck-Institute for Meteorology, the University of Tokyo Center for

  14. Improving the safety of LWR power plants. Final report

    SciTech Connect

    Not Available

    1980-04-01

    This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs (improving or maintaining level of safety with simpler systems or in a more cost-effective manner).

  15. Fluidized-bed waste-heat recovery system development: Semiannual report, August 1, 1984-January 31, 1985

    SciTech Connect

    Cole, W.E.; Patch, K.D.

    1987-03-01

    A major energy loss in industry is the heat content of the flue gases from industrial process heaters. One effective way to utilize the energy is to preheat the combustion air for the process heater. The Fluidized-Bed Waste-Heat Recovery (FBWHR) System is designed to preheat this combustion air using the heat available in dirty flue gas streams. In this system, a recirculating medium is heated by the flue gas in a raining bed. The hot medium is then removed from the bed and placed in a fluidized bed where it is fluidized by the combustion air. Through this process, the combustion air is preheated. The cooled medium is then returned to the raining bed. Initial development of this concept is for the aluminum smelting industry. In this report, the accomplishments of the preceding six-month period are described. Specifically, tests in the laboratory FBWHR system, performing integrated system testing and subsystem development, were completed.

  16. 78 FR 1570 - Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-08

    ... January 8, 2013 Part VII Department of Energy Semiannual Regulatory Agenda #0;#0;Federal Register / Vol. 78 , No. 5 / Tuesday, January 8, 2013 / Unified Agenda#0;#0; ] DEPARTMENT OF ENERGY 10 CFR Chs. II, III, and X 48 CFR Ch. 9 Semiannual Regulatory Agenda AGENCY: Department of Energy. ACTION: Notice...

  17. Department of Labor Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-26

    ... Part XI Department of Labor Semiannual Regulatory Agenda ] DEPARTMENT OF LABOR (DOL) DEPARTMENT OF LABOR Office of the Secretary 20 CFR Chs. I, IV, V, VI, VII, and IX 29 CFR Subtitle A and Chs. II, IV, V, XVII, and XXV 30 CFR Ch. I 41 CFR Ch. 60 48 CFR Ch. 29 Semiannual Agenda of Regulations AGENCY: Office of the Secretary, Labor....

  18. Department of Justice Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-20

    ... [The Regulatory Plan and Unified Agenda of Federal Regulatory and Deregulatory Actions] Part XI Department of Justice Semiannual Regulatory Agenda ] DEPARTMENT OF JUSTICE (DOJ) DEPARTMENT OF JUSTICE 8 CFR Ch. V 21 CFR Ch. I 27 CFR Ch. II 28 CFR Ch. I, V Regulatory Agenda AGENCY: Department of Justice. ACTION: Semiannual regulatory agenda....

  19. Cable insulation development (1). Superconducting power transmission system development (2). Semiannual report, 1 April 1985-30 September 1985

    SciTech Connect

    Not Available

    1986-04-07

    Objective of the program is to develop an undergound superconducting power transmission system which is economical and technically attractive to the utility industry. The system would be capable of carrying very large blocks of electric power, thus enabling it to supplant overhead lines in urban and suburban areas and regions of natural beauty. the program consisted initially of work in the laboratory to develop suitable materials, cryostats and cable concepts. The materials work covers the development and testing of suitable superconductors and dielectric insulation. The laboratory work has now been extended to an outside test facility which represents an intermediate step between the laboratory scale and a full-scale system. The facility allows cables several hundred feet long to be tested under realistic conditions. Six operating runs of two to four weeks duration each have been accomplished.

  20. Fluidized-Bed Waste-Heat Recovery System development. Semiannual report, 1 August 1982-31 January 1983

    SciTech Connect

    Cole, W.E.; DeSaro, R.; Joshi, C.

    1983-02-01

    The Fluidized-Bed Waste-Heat Recovery (FBWHR) System is designed to preheat this combustion air using the heat available in dirty flue gas streams. In this system, a recirculating medium is heated by the flue gas in a fluidized bed. The hot medium is then removed from the bed and placed in a second fluidized bed where it is fluidized by the combustion air. Through this process, the combustion air is heated. The cooled medium is then returned to the first bed. Initial development of this concept is for the aluminum smelting industry.

  1. Fluidized-Bed Waste-Heat Recovery System development. Semiannual report, 1 August 1981-31 January 1982

    SciTech Connect

    Cole, W. E.; DeSaro, R.; Joshi, C.

    1982-02-01

    The Fluidized-Bed Waste-Heat Recovery (FBWHR) System is designed to preheat this combustion air using the heat available in dirty flue gas streams. In this system, a recirculating medium is heated by the flue gas in a fluidized bed. The hot medium is then removed from the bed and placed in a second fluidized bed where it is fluidized by the combustion air. Through this process, the combustion air is heated. The cooled medium is then returned to the first bed. Initial development of this concept is for the aluminum smelting industry.

  2. Fort Hood solar total energy project: technical support and systems integration. Third semiannual report, May 1, 1979-October 31, 1979

    SciTech Connect

    Not Available

    1980-02-01

    Work on the Fort Hood STES which was planned by DOE as a Large Scale Experiment for the Solar Total Energy Program is described. The history of the design evolution and management of the project which began in 1973 is summarized. The project was discontinued by DOE in December 1979. Supporting studies underway at the time are reported including: (1) reassessment of energy loads, (2) revised system concept, (3) plant sizing calculations, and (4) insolation variation measurement planning. (WHK)

  3. Heavy vehicle propulsion system materials program semi-annual progress report for October 1997 through March 1998

    SciTech Connect

    Johnson, D.R.

    1998-06-01

    The purpose of the Heavy Vehicle Propulsion System materials Program is the development of materials: ceramics, intermetallics, metal alloys, and metal and ceramic coatings, to support the dieselization of class 1--3 trucks to realize a 35{percent} fuel-economy improvement over current gasoline-fueled trucks and to support commercialization of fuel-flexible LE-55 low-emissions, high-efficiency diesel engines for class 7--8 trucks. The Office of Transportation Technologies, Office of Heavy Vehicle Technologies (OTT OHVT) has an active program to develop the technology for advanced LE-55 diesel engines with 55{percent} efficiency and low emissions levels of 2.0 g/bhp-h NO{sub x} and 0.05 g/bhp-h particulates. The goal is also for the LE-55 engine to run on natural gas with efficiency approaching that of diesel fuel. The LE-55 program is being completed in FY 1997 and, after approximately 10 years of effort, has largely met the program goals of 55{percent} efficiency and low emissions. However, the commercialization of the LE-55 technology requires more durable materials than those that have been used to demonstrate the goals. Heavy Vehicle Propulsion System Materials will, in concert with the heavy-duty diesel engine companies, develop the durable materials required to commercialize the LE-55 technologies.

  4. Fluidized-bed waste-heat recovery system development. Semiannual report, February 1, 1983-July 31, 1983

    SciTech Connect

    Cole, W. E.; De Saro, R.; Joshi, C.

    1983-08-01

    A major energy loss in industry is the heat content of the flue gases from industrial process heaters. One effective way to utilize this energy, which is applicable to all processes, is to preheat the combustion air from the process heater. Although recuperators are available to preheat this air when the flue gases are clean, recuperators to recover the heat from dirty and corrosive flue gases do not exist. The Fluidized-Bed Waste-Heat Recovery (FBWHR) System is designed to preheat this combustion air using the heat available in dirty flue gas streams. In this system, a recirculating medium is heated by the flue gas in a fluidized bed. The hot medium is then removed from the bed and placed in a second fluidized bed where it is fluidized by the combustion air. Through this process, the combustion air is heated. The cooled medium is then returned to the first bed. Initial development of this concept is for the aluminum smelting industry. In this report, the accomplishments of the proceeding six-month period are described.

  5. SciDAC's Earth System Grid Center for Enabling Technologies Semiannual Progress Report October 1, 2010 through March 31, 2011

    SciTech Connect

    Williams, Dean N.

    2011-04-02

    This report summarizes work carried out by the Earth System Grid Center for Enabling Technologies (ESG-CET) from October 1, 2010 through March 31, 2011. It discusses ESG-CET highlights for the reporting period, overall progress, period goals, and collaborations, and lists papers and presentations. To learn more about our project and to find previous reports, please visit the ESG-CET Web sites: http://esg-pcmdi.llnl.gov/ and/or https://wiki.ucar.edu/display/esgcet/Home. This report will be forwarded to managers in the Department of Energy (DOE) Scientific Discovery through Advanced Computing (SciDAC) program and the Office of Biological and Environmental Research (OBER), as well as national and international collaborators and stakeholders (e.g., those involved in the Coupled Model Intercomparison Project, phase 5 (CMIP5) for the Intergovernmental Panel on Climate Change (IPCC) 5th Assessment Report (AR5); the Community Earth System Model (CESM); the Climate Science Computational End Station (CCES); SciDAC II: A Scalable and Extensible Earth System Model for Climate Change Science; the North American Regional Climate Change Assessment Program (NARCCAP); the Atmospheric Radiation Measurement (ARM) program; the National Aeronautics and Space Administration (NASA), the National Oceanic and Atmospheric Administration (NOAA)), and also to researchers working on a variety of other climate model and observation evaluation activities. The ESG-CET executive committee consists of Dean N. Williams, Lawrence Livermore National Laboratory (LLNL); Ian Foster, Argonne National Laboratory (ANL); and Don Middleton, National Center for Atmospheric Research (NCAR). The ESG-CET team is a group of researchers and scientists with diverse domain knowledge, whose home institutions include eight laboratories and two universities: ANL, Los Alamos National Laboratory (LANL), Lawrence Berkeley National Laboratory (LBNL), LLNL, NASA/Jet Propulsion Laboratory (JPL), NCAR, Oak Ridge National

  6. Determination of optimal LWR containment design, excluding accidents more severe than Class 8

    SciTech Connect

    Cave, L.; Min, T.K.

    1980-04-01

    Information is presented concerning the restrictive effect of existing NRC requirements; definition of possible targets for containment; possible containment systems for LWR; optimization of containment design for class 3 through class 8 accidents (PWR); estimated costs of some possible containment arrangements for PWR relative to the standard dry containment system; estimated costs of BWR containment.

  7. CO2 annual and semiannual cycles from multiple satellite retrievals and models

    NASA Astrophysics Data System (ADS)

    Jiang, Xun; Crisp, David; Olsen, Edward T.; Kulawik, Susan S.; Miller, Charles E.; Pagano, Thomas S.; Liang, Maochang; Yung, Yuk L.

    2016-02-01

    Satellite CO2 retrievals from the Greenhouse gases Observing SATellite (GOSAT), Atmospheric Infrared Sounder (AIRS), and Tropospheric Emission Spectrometer (TES) and in situ measurements from the National Oceanic and Atmospheric Administration - Earth System Research Laboratory (NOAA-ESRL) Surface CO2 and Total Carbon Column Observing Network (TCCON) are utilized to explore the CO2 variability at different altitudes. A multiple regression method is used to calculate the CO2 annual cycle and semiannual cycle amplitudes from different data sets. The CO2 annual cycle and semiannual cycle amplitudes for GOSAT XCO2 and TCCON XCO2 are consistent but smaller than those seen in the NOAA-ESRL surface data. The CO2 annual and semiannual cycles are smallest in the AIRS midtropospheric CO2 compared with other data sets in the Northern Hemisphere. The amplitudes for the CO2 annual cycle and semiannual cycle from GOSAT, TES, and AIRS CO2 are small and comparable to each other in the Southern Hemisphere. Similar regression analysis is applied to the Model for OZone And Related chemical Tracers-2 and CarbonTracker model CO2. The convolved model CO2 annual cycle and semiannual cycle amplitudes are similar to those from the satellite CO2 retrievals, although the models tend to underestimate the CO2 seasonal cycle amplitudes in the Northern Hemisphere midlatitudes and underestimate the CO2 semiannual cycle amplitudes in the high latitudes. These results can be used to better understand the vertical structures for the CO2 annual cycle and semiannual cycle and help identify deficiencies in the models, which are very important for the carbon budget study.

  8. Thermochemical evaluation of PCI failures in LWR fuel pins

    NASA Astrophysics Data System (ADS)

    Götzmann, Odo

    1982-06-01

    In searching for the reasons behind the PCI failures of LWR fuel pins two questions have obviously remained unanswered: (a) what is the iodine potential necessary to cause SCC of zircaloy, and (b) is this iodine potential available in a fuel pin. To answer these two questions, a consistent set of thermochemical data for the Zr-I system was created, the results of laboratory tests of iodine-induced SCC of zircaloy were evaluated, and, finally, equilibrium calculations for the fuel-fission-product system were performed to determine the temperature and oxygen potential required to produce an iodine potential high enough to cause SCC of zircaloy. The conclusion of this study is that SCC of zircaloy can be caused by an iodine potential equal to or greater than that needed to form ZrI with metallic zirconium. This iodine potential is available in an LWR fuel pin at oxygen potentials corresponding to stoichiometric fuel. The carrier of the potential, i.e. The attacking species, is CsI.

  9. Technical report on LWR design decision methodology. Phase I

    SciTech Connect

    1980-03-01

    Energy Incorporated (EI) was selected by Sandia Laboratories to develop and test on LWR design decision methodology. Contract Number 42-4229 provided funding for Phase I of this work. This technical report on LWR design decision methodology documents the activities performed under that contract. Phase I was a short-term effort to thoroughly review the curret LWR design decision process to assure complete understanding of current practices and to establish a well defined interface for development of initial quantitative design guidelines.

  10. 32 CFR 70.11 - DoD semiannual report.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... DISCHARGE REVIEW BOARD (DRB) PROCEDURES AND STANDARDS § 70.11 DoD semiannual report. (a) Semiannual reports..., 1977, and Special Discharge Review Program Cases. (3) Part 3. Cases Heard under Pub. L. 95-126 by.... Semiannual DRB Report—RCS DD-M(SA) 1489; Summary of Statistics for Discharge Review Board (FY) Name of...

  11. 32 CFR 70.11 - DoD semiannual report.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 32 National Defense 1 2014-07-01 2014-07-01 false DoD semiannual report. 70.11 Section 70.11 National Defense Department of Defense OFFICE OF THE SECRETARY OF DEFENSE PERSONNEL, MILITARY AND CIVILIAN DISCHARGE REVIEW BOARD (DRB) PROCEDURES AND STANDARDS § 70.11 DoD semiannual report. (a) Semiannual...

  12. 18 CFR 1315.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 18 Conservation of Power and Water Resources 2 2011-04-01 2011-04-01 false Semi-annual compilation... RESTRICTIONS ON LOBBYING Agency Reports § 1315.600 Semi-annual compilation. (a) The head of each agency shall... first semi-annual compilation shall be submitted on May 31, 1990, and shall contain a compilation of...

  13. 20 CFR 438.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Semi-annual compilation. 438.600 Section 438....600 Semi-annual compilation. (a) The Commissioner of Social Security will collect and compile the... semi-annual compilation was submitted on May 31, 1990, and contains a compilation of the...

  14. 49 CFR 20.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 1 2011-10-01 2011-10-01 false Semi-annual compilation. 20.600 Section 20.600... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  15. 34 CFR 82.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 34 Education 1 2013-07-01 2013-07-01 false Semi-annual compilation. 82.600 Section 82.600....600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  16. 20 CFR 438.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 20 Employees' Benefits 2 2012-04-01 2012-04-01 false Semi-annual compilation. 438.600 Section 438....600 Semi-annual compilation. (a) The Commissioner of Social Security will collect and compile the... semi-annual compilation was submitted on May 31, 1990, and contains a compilation of the...

  17. 7 CFR 3018.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 7 Agriculture 15 2012-01-01 2012-01-01 false Semi-annual compilation. 3018.600 Section 3018.600..., DEPARTMENT OF AGRICULTURE NEW RESTRICTIONS ON LOBBYING Agency Reports § 3018.600 Semi-annual compilation. (a... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  18. 44 CFR 18.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 44 Emergency Management and Assistance 1 2013-10-01 2013-10-01 false Semi-annual compilation. 18... OF HOMELAND SECURITY GENERAL NEW RESTRICTIONS ON LOBBYING Agency Reports § 18.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  19. 22 CFR 311.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 22 Foreign Relations 2 2010-04-01 2010-04-01 true Semi-annual compilation. 311.600 Section 311.600 Foreign Relations PEACE CORPS NEW RESTRICTIONS ON LOBBYING Agency Reports § 311.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  20. 7 CFR 3018.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 7 Agriculture 15 2013-01-01 2013-01-01 false Semi-annual compilation. 3018.600 Section 3018.600..., DEPARTMENT OF AGRICULTURE NEW RESTRICTIONS ON LOBBYING Agency Reports § 3018.600 Semi-annual compilation. (a... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  1. 41 CFR 105-69.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Semi-annual compilation... Administration 69-NEW RESTRICTIONS ON LOBBYING Agency Reports § 105-69.600 Semi-annual compilation. (a) The head... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  2. 45 CFR 93.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 45 Public Welfare 1 2011-10-01 2011-10-01 false Semi-annual compilation. 93.600 Section 93.600... LOBBYING Agency Reports § 93.600 Semi-annual compilation. (a) The head of each agency shall collect and... first semi-annual compilation shall be submitted on May 31, 1990, and shall contain a compilation of...

  3. 44 CFR 18.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 44 Emergency Management and Assistance 1 2011-10-01 2011-10-01 false Semi-annual compilation. 18... OF HOMELAND SECURITY GENERAL NEW RESTRICTIONS ON LOBBYING Agency Reports § 18.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  4. 45 CFR 1230.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 45 Public Welfare 4 2012-10-01 2012-10-01 false Semi-annual compilation. 1230.600 Section 1230.600... SERVICE NEW RESTRICTIONS ON LOBBYING Agency Reports § 1230.600 Semi-annual compilation. (a) The head of... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  5. 10 CFR 601.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Semi-annual compilation. 601.600 Section 601.600 Energy... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  6. 32 CFR 28.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 32 National Defense 1 2013-07-01 2013-07-01 false Semi-annual compilation. 28.600 Section 28.600... REGULATIONS NEW RESTRICTIONS ON LOBBYING Agency Reports § 28.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  7. 49 CFR 20.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 1 2013-10-01 2013-10-01 false Semi-annual compilation. 20.600 Section 20.600... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  8. 45 CFR 1230.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 45 Public Welfare 4 2013-10-01 2013-10-01 false Semi-annual compilation. 1230.600 Section 1230.600... SERVICE NEW RESTRICTIONS ON LOBBYING Agency Reports § 1230.600 Semi-annual compilation. (a) The head of... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  9. 32 CFR 28.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 32 National Defense 1 2010-07-01 2010-07-01 false Semi-annual compilation. 28.600 Section 28.600... REGULATIONS NEW RESTRICTIONS ON LOBBYING Agency Reports § 28.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  10. 45 CFR 604.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 45 Public Welfare 3 2013-10-01 2013-10-01 false Semi-annual compilation. 604.600 Section 604.600... RESTRICTIONS ON LOBBYING Agency Reports § 604.600 Semi-annual compilation. (a) The head of each agency shall... first semi-annual compilation shall be submitted on May 31, 1990, and shall contain a compilation of...

  11. 49 CFR 20.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 1 2012-10-01 2012-10-01 false Semi-annual compilation. 20.600 Section 20.600... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  12. 22 CFR 519.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 22 Foreign Relations 2 2012-04-01 2009-04-01 true Semi-annual compilation. 519.600 Section 519.600... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  13. 38 CFR 45.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 38 Pensions, Bonuses, and Veterans' Relief 2 2010-07-01 2010-07-01 false Semi-annual compilation... (CONTINUED) NEW RESTRICTIONS ON LOBBYING Agency Reports § 45.600 Semi-annual compilation. (a) The head of... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  14. 29 CFR 93.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 29 Labor 1 2013-07-01 2013-07-01 false Semi-annual compilation. 93.600 Section 93.600 Labor Office of the Secretary of Labor NEW RESTRICTIONS ON LOBBYING Agency Reports § 93.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  15. 24 CFR 87.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 24 Housing and Urban Development 1 2012-04-01 2012-04-01 false Semi-annual compilation. 87.600... Development NEW RESTRICTIONS ON LOBBYING Agency Reports § 87.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  16. 22 CFR 311.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 22 Foreign Relations 2 2013-04-01 2009-04-01 true Semi-annual compilation. 311.600 Section 311.600 Foreign Relations PEACE CORPS NEW RESTRICTIONS ON LOBBYING Agency Reports § 311.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  17. 45 CFR 1158.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 45 Public Welfare 3 2011-10-01 2011-10-01 false Semi-annual compilation. 1158.600 Section 1158.600... HUMANITIES NATIONAL ENDOWMENT FOR THE ARTS NEW RESTRICTIONS ON LOBBYING Agency Reports § 1158.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  18. 45 CFR 93.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 45 Public Welfare 1 2013-10-01 2013-10-01 false Semi-annual compilation. 93.600 Section 93.600... LOBBYING Agency Reports § 93.600 Semi-annual compilation. (a) The head of each agency shall collect and... first semi-annual compilation shall be submitted on May 31, 1990, and shall contain a compilation of...

  19. 22 CFR 227.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 22 Foreign Relations 1 2012-04-01 2012-04-01 false Semi-annual compilation. 227.600 Section 227... § 227.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  20. 24 CFR 87.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Semi-annual compilation. 87.600... Development NEW RESTRICTIONS ON LOBBYING Agency Reports § 87.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  1. 45 CFR 1230.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 45 Public Welfare 4 2010-10-01 2010-10-01 false Semi-annual compilation. 1230.600 Section 1230.600... SERVICE NEW RESTRICTIONS ON LOBBYING Agency Reports § 1230.600 Semi-annual compilation. (a) The head of... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  2. 45 CFR 1158.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 45 Public Welfare 3 2013-10-01 2013-10-01 false Semi-annual compilation. 1158.600 Section 1158.600... HUMANITIES NATIONAL ENDOWMENT FOR THE ARTS NEW RESTRICTIONS ON LOBBYING Agency Reports § 1158.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  3. 34 CFR 82.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 34 Education 1 2011-07-01 2011-07-01 false Semi-annual compilation. 82.600 Section 82.600....600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  4. 40 CFR 34.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 40 Protection of Environment 1 2012-07-01 2012-07-01 false Semi-annual compilation. 34.600 Section... NEW RESTRICTIONS ON LOBBYING Agency Reports § 34.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  5. 44 CFR 18.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Semi-annual compilation. 18... OF HOMELAND SECURITY GENERAL NEW RESTRICTIONS ON LOBBYING Agency Reports § 18.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  6. 22 CFR 311.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 22 Foreign Relations 2 2011-04-01 2009-04-01 true Semi-annual compilation. 311.600 Section 311.600 Foreign Relations PEACE CORPS NEW RESTRICTIONS ON LOBBYING Agency Reports § 311.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  7. 22 CFR 138.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 22 Foreign Relations 1 2012-04-01 2012-04-01 false Semi-annual compilation. 138.600 Section 138... § 138.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  8. 49 CFR 20.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 1 2010-10-01 2010-10-01 false Semi-annual compilation. 20.600 Section 20.600... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  9. 38 CFR 45.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 38 Pensions, Bonuses, and Veterans' Relief 2 2012-07-01 2012-07-01 false Semi-annual compilation... (CONTINUED) NEW RESTRICTIONS ON LOBBYING Agency Reports § 45.600 Semi-annual compilation. (a) The head of... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  10. 22 CFR 519.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 22 Foreign Relations 2 2011-04-01 2009-04-01 true Semi-annual compilation. 519.600 Section 519.600... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  11. 38 CFR 45.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 38 Pensions, Bonuses, and Veterans' Relief 2 2011-07-01 2011-07-01 false Semi-annual compilation... (CONTINUED) NEW RESTRICTIONS ON LOBBYING Agency Reports § 45.600 Semi-annual compilation. (a) The head of... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  12. 24 CFR 87.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 24 Housing and Urban Development 1 2011-04-01 2011-04-01 false Semi-annual compilation. 87.600... Development NEW RESTRICTIONS ON LOBBYING Agency Reports § 87.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  13. 7 CFR 3018.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 7 Agriculture 15 2010-01-01 2010-01-01 false Semi-annual compilation. 3018.600 Section 3018.600..., DEPARTMENT OF AGRICULTURE NEW RESTRICTIONS ON LOBBYING Agency Reports § 3018.600 Semi-annual compilation. (a... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  14. 45 CFR 604.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 45 Public Welfare 3 2011-10-01 2011-10-01 false Semi-annual compilation. 604.600 Section 604.600... RESTRICTIONS ON LOBBYING Agency Reports § 604.600 Semi-annual compilation. (a) The head of each agency shall... first semi-annual compilation shall be submitted on May 31, 1990, and shall contain a compilation of...

  15. 32 CFR 28.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 32 National Defense 1 2012-07-01 2012-07-01 false Semi-annual compilation. 28.600 Section 28.600... REGULATIONS NEW RESTRICTIONS ON LOBBYING Agency Reports § 28.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  16. 45 CFR 1158.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 45 Public Welfare 3 2012-10-01 2012-10-01 false Semi-annual compilation. 1158.600 Section 1158.600... HUMANITIES NATIONAL ENDOWMENT FOR THE ARTS NEW RESTRICTIONS ON LOBBYING Agency Reports § 1158.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  17. 45 CFR 604.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 45 Public Welfare 3 2012-10-01 2012-10-01 false Semi-annual compilation. 604.600 Section 604.600... RESTRICTIONS ON LOBBYING Agency Reports § 604.600 Semi-annual compilation. (a) The head of each agency shall... first semi-annual compilation shall be submitted on May 31, 1990, and shall contain a compilation of...

  18. 22 CFR 519.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 22 Foreign Relations 2 2010-04-01 2010-04-01 true Semi-annual compilation. 519.600 Section 519.600... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  19. 22 CFR 227.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 22 Foreign Relations 1 2013-04-01 2013-04-01 false Semi-annual compilation. 227.600 Section 227... § 227.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  20. 40 CFR 34.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 1 2013-07-01 2013-07-01 false Semi-annual compilation. 34.600 Section... NEW RESTRICTIONS ON LOBBYING Agency Reports § 34.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  1. 44 CFR 18.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 44 Emergency Management and Assistance 1 2012-10-01 2011-10-01 true Semi-annual compilation. 18... OF HOMELAND SECURITY GENERAL NEW RESTRICTIONS ON LOBBYING Agency Reports § 18.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  2. 24 CFR 87.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 24 Housing and Urban Development 1 2013-04-01 2013-04-01 false Semi-annual compilation. 87.600... Development NEW RESTRICTIONS ON LOBBYING Agency Reports § 87.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  3. 38 CFR 45.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 38 Pensions, Bonuses, and Veterans' Relief 2 2013-07-01 2013-07-01 false Semi-annual compilation... (CONTINUED) NEW RESTRICTIONS ON LOBBYING Agency Reports § 45.600 Semi-annual compilation. (a) The head of... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  4. 22 CFR 138.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 22 Foreign Relations 1 2013-04-01 2013-04-01 false Semi-annual compilation. 138.600 Section 138... § 138.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  5. 7 CFR 3018.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 7 Agriculture 15 2011-01-01 2011-01-01 false Semi-annual compilation. 3018.600 Section 3018.600..., DEPARTMENT OF AGRICULTURE NEW RESTRICTIONS ON LOBBYING Agency Reports § 3018.600 Semi-annual compilation. (a... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  6. 22 CFR 311.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 22 Foreign Relations 2 2012-04-01 2009-04-01 true Semi-annual compilation. 311.600 Section 311.600 Foreign Relations PEACE CORPS NEW RESTRICTIONS ON LOBBYING Agency Reports § 311.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  7. 29 CFR 93.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 29 Labor 1 2011-07-01 2011-07-01 false Semi-annual compilation. 93.600 Section 93.600 Labor Office of the Secretary of Labor NEW RESTRICTIONS ON LOBBYING Agency Reports § 93.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  8. 41 CFR 105-69.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 41 Public Contracts and Property Management 3 2013-07-01 2013-07-01 false Semi-annual compilation... Administration 69-NEW RESTRICTIONS ON LOBBYING Agency Reports § 105-69.600 Semi-annual compilation. (a) The head... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  9. 20 CFR 438.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 20 Employees' Benefits 2 2011-04-01 2011-04-01 false Semi-annual compilation. 438.600 Section 438....600 Semi-annual compilation. (a) The Commissioner of Social Security will collect and compile the... semi-annual compilation was submitted on May 31, 1990, and contains a compilation of the...

  10. 41 CFR 105-69.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 41 Public Contracts and Property Management 3 2012-01-01 2012-01-01 false Semi-annual compilation... Administration 69-NEW RESTRICTIONS ON LOBBYING Agency Reports § 105-69.600 Semi-annual compilation. (a) The head... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  11. 40 CFR 34.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Semi-annual compilation. 34.600 Section... NEW RESTRICTIONS ON LOBBYING Agency Reports § 34.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  12. 29 CFR 93.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 29 Labor 1 2010-07-01 2010-07-01 true Semi-annual compilation. 93.600 Section 93.600 Labor Office of the Secretary of Labor NEW RESTRICTIONS ON LOBBYING Agency Reports § 93.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  13. 40 CFR 34.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 1 2014-07-01 2014-07-01 false Semi-annual compilation. 34.600 Section... NEW RESTRICTIONS ON LOBBYING Agency Reports § 34.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  14. 20 CFR 438.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 20 Employees' Benefits 2 2014-04-01 2014-04-01 false Semi-annual compilation. 438.600 Section 438....600 Semi-annual compilation. (a) The Commissioner of Social Security will collect and compile the... semi-annual compilation was submitted on May 31, 1990, and contains a compilation of the...

  15. 10 CFR 601.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 4 2014-01-01 2014-01-01 false Semi-annual compilation. 601.600 Section 601.600 Energy... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  16. 49 CFR 20.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 1 2014-10-01 2014-10-01 false Semi-annual compilation. 20.600 Section 20.600... Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  17. 22 CFR 138.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 22 Foreign Relations 1 2014-04-01 2014-04-01 false Semi-annual compilation. 138.600 Section 138... § 138.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  18. 41 CFR 105-69.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 41 Public Contracts and Property Management 3 2014-01-01 2014-01-01 false Semi-annual compilation... Administration 69-NEW RESTRICTIONS ON LOBBYING Agency Reports § 105-69.600 Semi-annual compilation. (a) The head... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  19. 29 CFR 93.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 29 Labor 1 2014-07-01 2013-07-01 true Semi-annual compilation. 93.600 Section 93.600 Labor Office of the Secretary of Labor NEW RESTRICTIONS ON LOBBYING Agency Reports § 93.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  20. 45 CFR 604.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 45 Public Welfare 3 2014-10-01 2014-10-01 false Semi-annual compilation. 604.600 Section 604.600... RESTRICTIONS ON LOBBYING Agency Reports § 604.600 Semi-annual compilation. (a) The head of each agency shall... first semi-annual compilation shall be submitted on May 31, 1990, and shall contain a compilation of...

  1. 38 CFR 45.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 38 Pensions, Bonuses, and Veterans' Relief 2 2014-07-01 2014-07-01 false Semi-annual compilation... (CONTINUED) NEW RESTRICTIONS ON LOBBYING Agency Reports § 45.600 Semi-annual compilation. (a) The head of... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  2. 22 CFR 227.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 22 Foreign Relations 1 2014-04-01 2014-04-01 false Semi-annual compilation. 227.600 Section 227... § 227.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  3. 44 CFR 18.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 44 Emergency Management and Assistance 1 2014-10-01 2014-10-01 false Semi-annual compilation. 18... OF HOMELAND SECURITY GENERAL NEW RESTRICTIONS ON LOBBYING Agency Reports § 18.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  4. 22 CFR 311.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 22 Foreign Relations 2 2014-04-01 2014-04-01 false Semi-annual compilation. 311.600 Section 311.600 Foreign Relations PEACE CORPS NEW RESTRICTIONS ON LOBBYING Agency Reports § 311.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  5. 7 CFR 3018.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 7 Agriculture 15 2014-01-01 2014-01-01 false Semi-annual compilation. 3018.600 Section 3018.600..., DEPARTMENT OF AGRICULTURE NEW RESTRICTIONS ON LOBBYING Agency Reports § 3018.600 Semi-annual compilation. (a... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  6. 24 CFR 87.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 24 Housing and Urban Development 1 2014-04-01 2014-04-01 false Semi-annual compilation. 87.600... Development NEW RESTRICTIONS ON LOBBYING Agency Reports § 87.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  7. 45 CFR 93.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 45 Public Welfare 1 2014-10-01 2014-10-01 false Semi-annual compilation. 93.600 Section 93.600... LOBBYING Agency Reports § 93.600 Semi-annual compilation. (a) The head of each agency shall collect and... first semi-annual compilation shall be submitted on May 31, 1990, and shall contain a compilation of...

  8. 34 CFR 82.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 34 Education 1 2014-07-01 2014-07-01 false Semi-annual compilation. 82.600 Section 82.600....600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  9. 22 CFR 519.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 22 Foreign Relations 2 2014-04-01 2014-04-01 false Semi-annual compilation. 519.600 Section 519... § 519.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure... information shall not be available for public inspection. (e) The first semi-annual compilation shall...

  10. 45 CFR 1158.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 45 Public Welfare 3 2014-10-01 2014-10-01 false Semi-annual compilation. 1158.600 Section 1158.600... HUMANITIES NATIONAL ENDOWMENT FOR THE ARTS NEW RESTRICTIONS ON LOBBYING Agency Reports § 1158.600 Semi-annual... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  11. 32 CFR 28.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 32 National Defense 1 2014-07-01 2014-07-01 false Semi-annual compilation. 28.600 Section 28.600... REGULATIONS NEW RESTRICTIONS ON LOBBYING Agency Reports § 28.600 Semi-annual compilation. (a) The head of each... available for public inspection. (e) The first semi-annual compilation shall be submitted on May 31,...

  12. 32 CFR 70.11 - DoD semiannual report.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 32 National Defense 1 2012-07-01 2012-07-01 false DoD semiannual report. 70.11 Section 70.11... DISCHARGE REVIEW BOARD (DRB) PROCEDURES AND STANDARDS § 70.11 DoD semiannual report. (a) Semiannual reports... 1 through March 31 and April 1 through September 30). (b) The reporting period will be...

  13. 32 CFR 70.11 - DoD semiannual report.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 32 National Defense 1 2011-07-01 2011-07-01 false DoD semiannual report. 70.11 Section 70.11... DISCHARGE REVIEW BOARD (DRB) PROCEDURES AND STANDARDS § 70.11 DoD semiannual report. (a) Semiannual reports... 1 through March 31 and April 1 through September 30). (b) The reporting period will be...

  14. LWR spent fuel reduction by the removal of U and the compact storage of Pu with FP for long-term nuclear sustainability

    SciTech Connect

    Fukasawa, T.; Hoshino, K.; Takano, M.; Sato, S.; Shimazu, Y.

    2013-07-01

    Fast breeder reactors (FBR) nuclear fuel cycle is needed for long-term nuclear sustainability while preventing global warming and maximum utilizing the limited uranium (U) resources. The 'Framework for Nuclear Energy Policy' by the Japanese government on October 2005 stated that commercial FBR deployment will start around 2050 under its suitable conditions by the successive replacement of light water reactors (LWR) to FBR. Even after Fukushima Daiichi Nuclear Power Plant accident which made Japanese tendency slow down the nuclear power generation activities, Japan should have various options for energy resources including nuclear, and also consider the delay of FBR deployment and increase of LWR spent fuel (LWR-SF) storage amounts. As plutonium (Pu) for FBR deployment will be supplied from LWR-SF reprocessing and Japan will not possess surplus Pu, the authors have developed the flexible fuel cycle initiative (FFCI) for the transition from LWR to FBR. The FFCI system is based on the possibility to stored recycled materials (U, Pu)temporarily for a suitable period according to the FBR deployment rate to control the Pu demand/supply balance. This FFCI system is also effective after the Fukushima accident for the reduction of LWR-SF and future LWR-to-FBR transition. (authors)

  15. Multilevel transport solution of LWR reactor cores

    SciTech Connect

    Jose Ignacio Marquez Damian; Cassiano R.E. de Oliveira; HyeonKae Park

    2008-09-01

    This work presents a multilevel approach for the solution of the transport equation in typical LWR assemblies and core configurations. It is based on the second-order, even-parity formulation of the transport equation, which is solved within the framework provided by the finite element-spherical harmonics code EVENT. The performance of the new solver has been compared with that of the standard conjugate gradient solver for diffusion and transport problems on structured and unstruc-tured grids. Numerical results demonstrate the potential of the multilevel scheme for realistic reactor calculations.

  16. Thermal Properties of Structural Materials Used in LWR Vessels

    SciTech Connect

    J. E. Daw; J. L. Rempe; D. L. Knudson

    2011-01-01

    High temperature material property data for structural materials used in existing Light Water Reactors (LWRs) are limited. Often, extrapolated values recommended in the literature differ significantly. To reduce uncertainties in predictions relying upon extrapolated data for LWR vessel and penetration materials, high temperature tests were completed on SA533 Grade B, Class 1 (SA533B1) low alloy steel, Stainless Steel 304 (SS304), and Inconel 600 using material property measurement systems available in the High Temperature Test Laboratory (HTTL) at the Idaho National Laboratory (INL). Properties measured include thermal expansion, specific heat capacity, and thermal diffusivity for temperatures up to 1200 °C. From these results, thermal conductivity and density were calculated. Results show that, in some cases, previously recommended values for these materials differ significantly from measured values at high temperatures.

  17. Task 3.0 -- Advanced power systems: Subtask 3.18 -- Ash behavior in power systems. Semi-annual report, June 1--December 31, 1997

    SciTech Connect

    Zygarlicke, C.J.; McCollor, D.P.; Folkedahl, B.C.; Swanson, M.L.; Musich, M.A.

    1998-10-01

    Advanced power systems such as integrated gasifier combined cycle systems and fluidized bed systems are at the forefront of power industry research because of the need for increased efficiency and the reduction of greenhouse gases. Ash behavior in power systems can have a significant impact on the design and performance of these systems. The Energy and Environmental Research Center (EERC) has developed a focused research initiative aimed at filling gaps in the understanding of fundamental mechanisms of ash behavior, which has relevance to commercial application and marketable products associated with advanced power systems. This program develops methods and means to better understand and mitigate adverse coal ash behavior in advanced power systems and can act to relieve the US reliance on diminishing recoverable oil resources and other greenhouse-producing fossil fuels. Subtask 3.18 is structured as three tasks. Task 1 pertains to summarizing the critical issues in ash behavior, especially for advanced power systems. Task 2 focuses on fundamental ash sintering and viscosity-ash composition relationships that are critical for developing a better mechanistic understanding of ash deposit formation and for predicting ash behavior. Task 3 is aimed primarily at determining the role of the ash chemistry and phase relationships for specific ash interactions in advanced power systems. The role of sulfides in the formation of ash deposits in gasification systems and the factors that influence alloy corrosion in supercritical boilers will be specifically analyzed. Task results to date are presented.

  18. LIFE vs. LWR: End of the Fuel Cycle

    SciTech Connect

    Farmer, J C; Blink, J A; Shaw, H F

    2008-10-02

    The worldwide energy consumption in 2003 was 421 quadrillion Btu (Quads), and included 162 quads for oil, 99 quads for natural gas, 100 quads for coal, 27 quads for nuclear energy, and 33 quads for renewable sources. The projected worldwide energy consumption for 2030 is 722 quads, corresponding to an increase of 71% over the consumption in 2003. The projected consumption for 2030 includes 239 quads for oil, 190 quads for natural gas, 196 quads for coal, 35 quads for nuclear energy, and 62 quads for renewable sources [International Energy Outlook, DOE/EIA-0484, Table D1 (2006) p. 133]. The current fleet of light water reactors (LRWs) provides about 20% of current U.S. electricity, and about 16% of current world electricity. The demand for electricity is expected to grow steeply in this century, as the developing world increases its standard of living. With the increasing price for oil and gasoline within the United States, as well as fear that our CO2 production may be driving intolerable global warming, there is growing pressure to move away from oil, natural gas, and coal towards nuclear energy. Although there is a clear need for nuclear energy, issues facing waste disposal have not been adequately dealt with, either domestically or internationally. Better technological approaches, with better public acceptance, are needed. Nuclear power has been criticized on both safety and waste disposal bases. The safety issues are based on the potential for plant damage and environmental effects due to either nuclear criticality excursions or loss of cooling. Redundant safety systems are used to reduce the probability and consequences of these risks for LWRs. LIFE engines are inherently subcritical, reducing the need for systems to control the fission reactivity. LIFE engines also have a fuel type that tolerates much higher temperatures than LWR fuel, and has two safety systems to remove decay heat in the event of loss of coolant or loss of coolant flow. These features of

  19. ADVANCED POWER SYSTEMS - ASH BEHAVIOR IN POWER SYSTEMS. INCLUDES THE SEMIANNUAL REPORT FOR THE PERIOD JANUARY 01, 1998 - JUNE 30, 1998.

    SciTech Connect

    1998-09-01

    The overall goal of this initiative is to develop fundamental knowledge of ash behavior in power systems for the purpose of increasing power production efficiency, reducing operation and maintenance costs, and reducing greenhouse gas emissions into the atmosphere. The specific objectives of this initiative focus primarily on ash behavior related to advanced power systems and include the following: Determine the current status of the fundamental ash interactions and deposition formation mechanisms as already reported through previous or ongoing projects at the EERC or in the literature; Determine sintering mechanisms for temperatures and particle compositions that are less well known and remain for the most part undetermined; Identify the relationship between the temperature of critical viscosity (T{sub cv}) as measured in a viscometer and the crystallization occurring in the melt; Perform a literature search on the use of heated-stage microscopy (HSM) for examining in situ ash-sintering phenomena and then validate the use of HSM in the determination of viscosity in spherical ash particles; Ascertain the formation and stability of specific mineral or amorphous phases in deposits typical of advanced power systems; and Evaluate corrosion for alloys being used in supercritical combustion systems.

  20. 12 CFR 8.2 - Semiannual assessment.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... the Table in 12 CFR 8.2(a); however, only the total domestic assets of the Federal branch or Federal... 12 Banks and Banking 1 2011-01-01 2011-01-01 false Semiannual assessment. 8.2 Section 8.2 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY ASSESSMENT OF FEES §...

  1. 12 CFR 8.2 - Semiannual assessment.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... the Table in 12 CFR 8.2(a); however, only the total domestic assets of the Federal branch or Federal... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Semiannual assessment. 8.2 Section 8.2 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY ASSESSMENT OF FEES §...

  2. Securities and Exchange Commission Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-20

    ... [The Regulatory Plan and Unified Agenda of Federal Regulatory and Deregulatory Actions] Part XXIV Securities and Exchange Commission Semiannual Regulatory Agenda ] SECURITIES AND EXCHANGE COMMISSION (SEC) SECURITIES AND EXCHANGE COMMISSION 17 CFR Ch. II Regulatory Flexibility Agenda AGENCY: Securities and Exchange Commission. ACTION:...

  3. Nuclear Regulatory Commission Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-20

    ...) 2010, less the amounts appropriated from the Nuclear Waste Fund, amounts appropriated for Waste... agenda on April 26, 2010 (75 FR 21960). For this edition of the NRC's regulatory agenda, the most... publication of the last NRC semiannual agenda on April 26, 2010 (75 FR 21960). Within each group, the...

  4. Nuclear Regulatory Commission Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-26

    ... amounts appropriated from the Nuclear Waste Fund, amounts appropriated for Waste Incidental to... December 7, 2009 (74 FR 64572). ADDRESSES: Comments on any rule in the agenda may be sent to the Secretary... occurred on rules since publication of the last NRC semiannual agenda on December 7, 2009 (74 FR...

  5. 77 FR 8020 - Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-13

    ... Agenda for the agency. SBA's last semiannual regulatory agenda was published on July 7, 2011, at 76 FR... Administration--Completed Actions Regulation Sequence No. Title Identifier No. 474 Implementation of Military... individual SBDC client data. Timetable: Action Date FR Cite ANPRM 06/00/12 Regulatory Flexibility...

  6. 12 CFR 8.2 - Semiannual assessment.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... computed at the same rate as provided in the Table in 12 CFR 8.2(a); however, only the total domestic... 12 Banks and Banking 1 2014-01-01 2014-01-01 false Semiannual assessment. 8.2 Section 8.2 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY ASSESSMENT OF FEES §...

  7. 78 FR 44247 - Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-23

    ... measuring ice maker energy use. Timetable: Action Date FR Cite NPRM 07/00/13 Final Action 07/00/14..., Office of Building Technologies Program, EE-2J, Department of Energy, Energy Efficiency and Renewable... July 23, 2013 Part VII Department of Energy Semiannual Regulatory Agenda #0;#0;Federal Register /...

  8. Department of Interior Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-26

    ...: Action Date FR Cite Final Action 04/00/10 Regulatory Flexibility Analysis Required: Yes Agency Contact... idle facilities. Timetable: Action Date FR Cite NPRM 12/00/10 NPRM Comment Period End 02/00/11... Part IX Department of the Interior Semiannual Regulatory Agenda ] DEPARTMENT OF THE INTERIOR...

  9. 78 FR 1636 - Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-08

    ...This Regulatory Agenda is a semiannual summary of all current and projected rulemakings, existing regulations, and completed actions of the Small Business Administration (SBA). For this fall edition of the SBA's Regulatory Agenda, a Regulatory Plan that contains a list of the Agency's most important and significant regulatory actions and a Statement of Regulatory Priorities is also included.......

  10. 78 FR 44331 - Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-23

    ...This Regulatory Agenda is a semiannual summary of all current and projected rulemakings and completed actions of the Small Business Administration (SBA). SBA expects that this summary information will enable the public to be more aware of, and effectively participate in, SBA's regulatory activity. SBA invites the public to submit comments on any aspect of this...

  11. 76 FR 40136 - Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-07

    ... FR 79864. The semiannual agenda of the SBA conforms to the Unified Agenda format developed by the... agencies; and revising the definitions of some terms. Timetable: Action Date FR Cite NPRM 08/00/11... agencies; and revising the definitions of some terms. Timetable: Action Date FR Cite NPRM...

  12. Department of Commerce Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-20

    ... [The Regulatory Plan and Unified Agenda of Federal Regulatory and Deregulatory Actions] Part IV Department of Commerce Semiannual Regulatory Agenda ] DEPARTMENT OF COMMERCE (DOC) DEPARTMENT OF COMMERCE Office of the Secretary 13 CFR Ch. III 15 CFR Subtitle A; Subtitle B, Chs. I, II, III, VII, VIII, IX, and XI 19 CFR Ch. III 37 CFR Chs. I, IV,...

  13. Environmental Protection Agency Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-26

    ...:// Not in FR www.epa.gov/lawsregs/search/regagenda.html Semiannual Regulatory Flexibility Agenda www....html issue ] Monthly Action Initiation List http://www.regulations.gov/fdmspublic/component/ Not in FR... Rulemaking Gateway www.epa.gov/rulemaking/ Not in FR B. What Are EPA's Regulatory Goals, and What...

  14. LWR-PV damage estimate methodology

    SciTech Connect

    Wagschal, J.J.; Maerker, R.E.; Broadhead, B.L.

    1980-01-01

    A credible estimate of the pressure vessel lifetime due to neutron-induced embrittlement is studied. The first step toward this goal is the accurate prediction of fluence and neutron energy spectrum at the pressure vessel. This, in turn, is obtained from least squares unfolding techniques of dosimetry measurements at a surveillance position, transport calculations, and a translation of information obtained at the surveillance position to the damage position. Including a prototypic neutron field like the ORNL Pool Critical Assembly, in which measurements are performed to serve as benchmarks for the LWR-PV surveillance dosimetry program, involves the use of approximate calculational methods. These approximate methods are supplemented by correction factors also known as calculational bias factors, the proper utilization of which requires estimated uncertainties of these biases as well. The source of a few biases for the PCA and some biases and correlations for the group fluxes at two PCA locations are presented.

  15. Note on the semi-annual effect in the thermosphere

    NASA Technical Reports Server (NTRS)

    Volland, H.; Mayr, H. G.

    1972-01-01

    The semi-annual variation in the thermospheric density is discussed in terms of the spatial and temporal variations in the solar heat input. Two heat sources are considered: the solar heat input associated with the semi-annual migration of the sun, and the auroral heat associated with the semi-annual component in magnetic storms. It is shown that the relatively large global component in the semi-annual effect of the total mass density can be explained by the lack of advective loss which otherwise damps the latitude dependent components in the annual and semi-annual variations, and the significant latitude dependence in the semi-annual variations of composition and temperature can be tied to the diffusion process which is induced by the thermospheric circulation.

  16. 32 CFR 70.11 - DoD semiannual report.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 32 National Defense 1 2013-07-01 2013-07-01 false DoD semiannual report. 70.11 Section 70.11 National Defense Department of Defense OFFICE OF THE SECRETARY OF DEFENSE PERSONNEL, MILITARY AND CIVILIAN DISCHARGE REVIEW BOARD (DRB) PROCEDURES AND STANDARDS § 70.11 DoD semiannual report. (a) Semiannual reports will be submitted by the 20th of...

  17. Options for Burning LWR SNF in LIFE Engine

    SciTech Connect

    Farmer, J

    2008-09-09

    We have pursued two processes in parallel for the burning of LWR SNF in the LIFE engine: (1) solid fuel option and (2) liquid fuel option. Approaches with both are discussed. The assigned Topical Report on liquid fuels is attached.

  18. Evaluation of FSV-1 cask for the transport of LWR irradiated fuel assemblies

    SciTech Connect

    Not Available

    1980-05-01

    The Model FSV-1 spent fuel shipping cask was designed by General Atomic Company (GA) to service the Fort St. Vrain (FSV) nuclear generating station, a High Temperature Gas Reactor (HTGR) owned and operated by Public Service Company of Colorado (PSC). This report presents an evaluation of the suitability of the FSV-1 cask for the transport of irradiated Light Water Reactor (LWR) fuel assemblies from both Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). The FSV-1 cask evaluation parameters covered a wide spectrum of LWR fuel assemblies, based on burnup in Megawatt Days/Metric Ton of Heavy Metal (MWD/MTHM) and years of decay since irradiation. The criteria for suitability included allowable radiation dose rates, cask surface and interior temperatures and the Gross Vehicle Weight (GVW) of the complete shipping system.

  19. Incineration of LWR-type waste in the Mound Cyclone Incinerator: a feasibility study

    SciTech Connect

    Alexander, B.M.

    1980-12-23

    The Mound Cyclone Incinerator has been demonstrated for several years for combustion of radwaste containing plutonium. It is now being developed for volume reduction of radwaste from light water reactor (LWR) facilities containing mixed beta- and gamma-emitters. To this end, a laboratory-scale feasibility study has been developed and executed. Development of the feasibility study was based on known characteristics of LWR waste and on operating data compiled for the Mound Cyclone Incinerator since 1975. Feed spiked with several isotopes found in LWR waste was burned in the laboratory-scale cyclone incinerator, and samples collected and analyzed. From these data, the applicability of cyclone incineration was demonstrated, and an efficient scrub liquor composition was chosen for the offgas treatment system. A Health Physics survey of the incinerator system after incineration of 220 ..mu..Ci of beta/gamma activity showed no exposure readings above background levels. Supplemental experiments were also performed to determine the effect of the chemical form of iodine on its volatility, as well as to calculate the cost-benefit relationship for the addition of potassium iodide to scrub liquor.

  20. 77 FR 25523 - Semi-Annual Workforce Management Conference

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-30

    ... Office of the Secretary Semi-Annual Workforce Management Conference AGENCY: U.S. Department of... of Transportation, Office of the Secretary, announces the second Semi-Annual Workforce Management... for addressing labor/management issues, and safety. Registration Space is limited. Registration...

  1. 6 CFR 9.51 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 6 Domestic Security 1 2012-01-01 2012-01-01 false Semi-annual compilation. 9.51 Section 9.51 Domestic Security DEPARTMENT OF HOMELAND SECURITY, OFFICE OF THE SECRETARY RESTRICTIONS UPON LOBBYING Agency Reports § 9.51 Semi-annual compilation. (a) The head of each agency shall collect and compile...

  2. 45 CFR 93.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 45 Public Welfare 1 2010-10-01 2010-10-01 false Semi-annual compilation. 93.600 Section 93.600 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION NEW RESTRICTIONS ON... first semi-annual compilation shall be submitted on May 31, 1990, and shall contain a compilation of...

  3. 15 CFR 28.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 15 Commerce and Foreign Trade 1 2012-01-01 2012-01-01 false Semi-annual compilation. 28.600... Agency Reports § 28.600 Semi-annual compilation. (a) The head of each agency shall collect and compile... committees. Such information shall not be available for public inspection. (e) The first...

  4. 43 CFR 18.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false Semi-annual compilation. 18.600 Section 18... Reports § 18.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  5. 14 CFR 1271.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 14 Aeronautics and Space 5 2011-01-01 2010-01-01 true Semi-annual compilation. 1271.600 Section... LOBBYING Agency Reports § 1271.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  6. 45 CFR 1158.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 45 Public Welfare 3 2010-10-01 2010-10-01 false Semi-annual compilation. 1158.600 Section 1158.600 Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES NATIONAL ENDOWMENT FOR THE ARTS NEW RESTRICTIONS ON LOBBYING Agency Reports § 1158.600 Semi-annual compilation. (a) The head of...

  7. 31 CFR 21.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 31 Money and Finance: Treasury 1 2011-07-01 2011-07-01 false Semi-annual compilation. 21.600... LOBBYING Agency Reports § 21.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  8. 43 CFR 18.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 43 Public Lands: Interior 1 2013-10-01 2013-10-01 false Semi-annual compilation. 18.600 Section 18... Reports § 18.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  9. 28 CFR 69.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 28 Judicial Administration 2 2012-07-01 2012-07-01 false Semi-annual compilation. 69.600 Section... Reports § 69.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  10. 28 CFR 69.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Semi-annual compilation. 69.600 Section... Reports § 69.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  11. 14 CFR 1271.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 14 Aeronautics and Space 5 2013-01-01 2013-01-01 false Semi-annual compilation. 1271.600 Section... LOBBYING Agency Reports § 1271.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  12. 43 CFR 18.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 43 Public Lands: Interior 1 2012-10-01 2011-10-01 true Semi-annual compilation. 18.600 Section 18... Reports § 18.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  13. 31 CFR 21.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 31 Money and Finance: Treasury 1 2012-07-01 2012-07-01 false Semi-annual compilation. 21.600... LOBBYING Agency Reports § 21.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  14. 12 CFR 411.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 12 Banks and Banking 4 2011-01-01 2011-01-01 false Semi-annual compilation. 411.600 Section 411... Reports § 411.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  15. 31 CFR 21.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 31 Money and Finance: Treasury 1 2013-07-01 2013-07-01 false Semi-annual compilation. 21.600... LOBBYING Agency Reports § 21.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  16. 43 CFR 18.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 43 Public Lands: Interior 1 2011-10-01 2011-10-01 false Semi-annual compilation. 18.600 Section 18... Reports § 18.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  17. 28 CFR 69.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 28 Judicial Administration 2 2011-07-01 2011-07-01 false Semi-annual compilation. 69.600 Section... Reports § 69.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  18. 31 CFR 21.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Semi-annual compilation. 21.600... LOBBYING Agency Reports § 21.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  19. 15 CFR 28.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 15 Commerce and Foreign Trade 1 2011-01-01 2011-01-01 false Semi-annual compilation. 28.600... Agency Reports § 28.600 Semi-annual compilation. (a) The head of each agency shall collect and compile... committees. Such information shall not be available for public inspection. (e) The first...

  20. 15 CFR 28.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 15 Commerce and Foreign Trade 1 2013-01-01 2013-01-01 false Semi-annual compilation. 28.600... Agency Reports § 28.600 Semi-annual compilation. (a) The head of each agency shall collect and compile... committees. Such information shall not be available for public inspection. (e) The first...

  1. 14 CFR 1271.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Semi-annual compilation. 1271.600 Section... LOBBYING Agency Reports § 1271.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  2. 22 CFR 712.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 22 Foreign Relations 2 2011-04-01 2009-04-01 true Semi-annual compilation. 712.600 Section 712.600... LOBBYING Agency Reports § 712.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  3. 22 CFR 712.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 22 Foreign Relations 2 2010-04-01 2010-04-01 true Semi-annual compilation. 712.600 Section 712.600... LOBBYING Agency Reports § 712.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  4. 18 CFR 1315.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 18 Conservation of Power and Water Resources 2 2010-04-01 2010-04-01 false Semi-annual compilation. 1315.600 Section 1315.600 Conservation of Power and Water Resources TENNESSEE VALLEY AUTHORITY NEW RESTRICTIONS ON LOBBYING Agency Reports § 1315.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the...

  5. 45 CFR 604.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 45 Public Welfare 3 2010-10-01 2010-10-01 false Semi-annual compilation. 604.600 Section 604.600 Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION NEW RESTRICTIONS ON LOBBYING Agency Reports § 604.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports...

  6. 28 CFR 69.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 28 Judicial Administration 2 2013-07-01 2013-07-01 false Semi-annual compilation. 69.600 Section... Reports § 69.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  7. 12 CFR 411.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 12 Banks and Banking 5 2013-01-01 2013-01-01 false Semi-annual compilation. 411.600 Section 411... Reports § 411.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  8. 14 CFR 1271.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 14 Aeronautics and Space 5 2014-01-01 2014-01-01 false Semi-annual compilation. 1271.600 Section... LOBBYING Agency Reports § 1271.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  9. 31 CFR 21.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 31 Money and Finance: Treasury 1 2014-07-01 2014-07-01 false Semi-annual compilation. 21.600... LOBBYING Agency Reports § 21.600 Semi-annual compilation. (a) The head of each agency shall collect and... committees. Such information shall not be available for public inspection. (e) The first...

  10. 15 CFR 28.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 15 Commerce and Foreign Trade 1 2014-01-01 2014-01-01 false Semi-annual compilation. 28.600... Agency Reports § 28.600 Semi-annual compilation. (a) The head of each agency shall collect and compile... committees. Such information shall not be available for public inspection. (e) The first...

  11. 12 CFR 411.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 12 Banks and Banking 5 2014-01-01 2014-01-01 false Semi-annual compilation. 411.600 Section 411... Reports § 411.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  12. 28 CFR 69.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 28 Judicial Administration 2 2014-07-01 2014-07-01 false Semi-annual compilation. 69.600 Section... Reports § 69.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the... committees. Such information shall not be available for public inspection. (e) The first...

  13. Semiannually alternating exchange of intermediate waters east of the Philippines

    NASA Astrophysics Data System (ADS)

    Wang, Fan; Song, Lina; Li, Yuanlong; Liu, Chuanyu; Wang, Jianing; Lin, Pengfei; Yang, Guang; Zhao, Jun; Diao, Xinyuan; Zhang, Dongxiao; Hu, Dunxin

    2016-07-01

    Intermediate water exchange in the northwest tropical Pacific is explored with the temperature, salinity, and current measurements of a mooring system deployed at 8°N, 127.05°E during 2010-2014. For the first time, prominent semiannual variability (SAV; with the maximum power at ~ 187 days) of subthermocline meridional flow along the Mindanao coast is revealed. A significant correlation between meridional flow and salinity is found at intermediate depths. This provides direct evidence for the alternating transports of South Pacific and North Pacific Intermediate Waters by northward and southward undercurrents, respectively. Further analysis with an eddy-resolving ocean general circulation model demonstrates that the SAV is generated locally near the western boundary, manifesting as large-scale subthermocline recirculation and leading to alternating northward and southward flows near the Mindanao coast, which plays an efficient role in the intermediate water exchange of the northwest tropical Pacific. Mechanisms underlying the observed SAV are discussed.

  14. Equatorial ionosphere semiannual oscillation investigated from Schumann resonance measurements on board the C/NOFS satellite

    NASA Astrophysics Data System (ADS)

    Simões, Fernando; Pfaff, Robert; Freudenreich, Henry; Klenzing, Jeffrey; Rowland, Douglas; Bromund, Kenneth; Kepko, Larry; Le, Guan; Liebrecht, Maria Carmen; Martin, Steven; Uribe, Paulo

    2013-11-01

    of Schumann resonance signatures in the equatorial ionosphere offers remote sensing capabilities for the investigation of tropospheric and space weather effects in the ionosphere. Schumann resonances are electromagnetic oscillations in the earth-ionosphere cavity produced by lightning activity. Analysis of AC electric field measurements gathered by the Communications/Navigation Outage Forecasting System satellite reveals a semiannual pattern in Schumann resonance data recorded during nighttime in the equatorial ionosphere. This pattern observed in the Schumann resonance amplitude is expected to help validate—or at least constrain—potential mechanisms proposed to explain the semiannual oscillation observed in different geophysical records, such as those reported in a variety of tropospheric, ionospheric/thermospheric, and magnetospheric observations.

  15. Identification of the impacts of maintenance and testing upon the safety of LWR power plants. Part II. Final report

    SciTech Connect

    Husseiny, A. A.; Sabri, Z. A.; Turnage, J. J.

    1980-04-01

    Information is presented concerning overview of literature relating to radiation exposure and operating experience; details of LWR-MTC3 classification system; histograms for individual BWR facilities depicting frequency of M and T mode and frequency of systems and components involved with M and T problems; histograms for individual PWR facilities depicting frequency of M and T mode and frequency of systems and components involved with M and T problems; and Fortran program for M and T data clustering.

  16. Semi-Annual Technical Progress Report of the Radioisotope Power System Materials Production and Technology Program Tasks for September 2000 through March 2001

    SciTech Connect

    Moore, J.P.

    2001-05-22

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) and weld shields (WS). This report has been divided into three sections to reflect program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2001. The first section deals primarily with maintenance of the capability to produce flight quality (FQ) CBCF insulator sets, iridium alloy blanks and foil, CVS, and WS. In all three cases, production maintenance is assured by the manufacture of limited quantities of FQ components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials. or to develop technologies for new radioisotope power systems. The last section is dedicated to studies related to the production of {sup 238}Pu.

  17. Semi-Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Program Tasks for April 1, 2002 Through September 20, 2002

    SciTech Connect

    Moore, J.P.

    2002-12-03

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS). This report has been divided into three sections to reflect program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2002. The first section deals primarily with maintenance of the capability to produce flight quality (FQ) CBCF insulator sets, iridium alloy blanks and foil, and CVS. In all three cases, production maintenance is assured by the manufacture of limited quantities of FQ components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for new radioisotope power systems. The last section is dedicated to studies related to the production of {sup 238}Pu.

  18. Semi-Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Program Tasks for October 1, 2001 Through March 31, 2002

    SciTech Connect

    J. P. Moore, JPM

    2002-05-22

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS). This report has been divided into three sections to reflect program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2002. The first section deals primarily with maintenance of the capability to produce flight quality (FQ) CBCF insulator sets, iridium alloy blanks and foil, and CVS. In all three cases, production maintenance is assured by the manufacture of limited quantities of FQ components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for new radioisotope power systems. The last section is dedicated to studies related to the production of {sup 238}Pu.

  19. Computational strategies for three-dimensional flow simulations on distributed computer systems. Ph.D. Thesis Semiannual Status Report, 15 Aug. 1993 - 15 Feb. 1994

    NASA Technical Reports Server (NTRS)

    Weed, Richard Allen; Sankar, L. N.

    1994-01-01

    An increasing amount of research activity in computational fluid dynamics has been devoted to the development of efficient algorithms for parallel computing systems. The increasing performance to price ratio of engineering workstations has led to research to development procedures for implementing a parallel computing system composed of distributed workstations. This thesis proposal outlines an ongoing research program to develop efficient strategies for performing three-dimensional flow analysis on distributed computing systems. The PVM parallel programming interface was used to modify an existing three-dimensional flow solver, the TEAM code developed by Lockheed for the Air Force, to function as a parallel flow solver on clusters of workstations. Steady flow solutions were generated for three different wing and body geometries to validate the code and evaluate code performance. The proposed research will extend the parallel code development to determine the most efficient strategies for unsteady flow simulations.

  20. SciDAC's Earth System Grid Center for Enabling Technologies Semi-Annual Progress Report for the Period October 1, 2009 through March 31, 2010

    SciTech Connect

    Williams, Dean N.; Foster, I. T.; Middleton, D. E.; Ananthakrishnan, R.; Siebenlist, F.; Shoshani, A.; Sim, A.; Bell, G.; Drach, R.; Ahrens, J.; Jones, P.; Brown, D.; Chastang, J.; Cinquini, L.; Fox, P.; Harper, D.; Hook, N.; Nienhouse, E.; Strand, G.; West, P.; Wilcox, H.; Wilhelmi, N.; Zednik, S.; Hankin, S.; Schweitzer, R.; Bernholdt, D.; Chen, M.; Miller, R.; Shipman, G.; Wang, F.; Bharathi, S.; Chervenak, A.; Schuler, R.; Su, M.

    2010-04-21

    This report summarizes work carried out by the ESG-CET during the period October 1, 2009 through March 31, 2009. It includes discussion of highlights, overall progress, period goals, collaborations, papers, and presentations. To learn more about our project, and to find previous reports, please visit the Earth System Grid Center for Enabling Technologies (ESG-CET) website. This report will be forwarded to the DOE SciDAC program management, the Office of Biological and Environmental Research (OBER) program management, national and international collaborators and stakeholders (e.g., the Community Climate System Model (CCSM), the Intergovernmental Panel on Climate Change (IPCC) 5th Assessment Report (AR5), the Climate Science Computational End Station (CCES), the SciDAC II: A Scalable and Extensible Earth System Model for Climate Change Science, the North American Regional Climate Change Assessment Program (NARCCAP), and other wide-ranging climate model evaluation activities).

  1. Fundamental quantitative analysis of microbial activity in aquifer bioreclamation; and Modeling the transport of biologically and chemically reactive solutes in a two-dimensional, heterogeneous intermediate scale system. Semi-annual progress report, August 1991--March 1992

    SciTech Connect

    Rittmann, B.E.; Valocchi, A.J.; Baveye, P.

    1992-12-31

    This report is the semi-annual progress report for the second half of the third year. The project has four primary areas: (1) biodegradation of poorly soluble organic contaminants; (2) dual-limitation kinetics of electron donors and acceptors; (3) two-dimensional modeling of biofilm reactions in nonhomogeneous porous media; and (4) biologically induced clogging in porous media. For each area, this report presents a brief summary of the previous progress, as well as reporting this period`s progress. In addition plans for future work are included.

  2. Thermal expansion coefficient of steels used in LWR vessels

    NASA Astrophysics Data System (ADS)

    Daw, J. E.; Rempe, J. L.; Knudson, D. L.; Crepeau, J. C.

    2008-05-01

    Because of the impact that melt relocation and vessel failure have on subsequent progression and associated consequences of a light water reactor (LWR) accident, it is important to accurately predict the heat-up and relocation of materials within the reactor vessel and heat transfer to and from the reactor vessel. Accurate predictions of such heat transfer phenomena require high temperature thermal properties. However, a review of vessel and structural steel material properties in severe accident analysis codes reveals that the required high temperature material properties are extrapolated with little, if any, data above 700 °C. To reduce uncertainties in predictions relying upon this extrapolated high temperature data, new thermal expansion data were obtained using pushrod dilatometry techniques for two steels used in LWR vessels: SA 533 Grade B, Class 1 (SA533B1) low alloy steel, which is used to fabricate most US LWR reactor vessels; and Type 304 stainless steel (SS304), which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data and compares it to existing, lower temperature data in the literature.

  3. High temperature thermal properties for metals used in LWR vessels

    NASA Astrophysics Data System (ADS)

    Rempe, J. L.; Knudson, D. L.

    2008-01-01

    Because of the impact that melt relocation and vessel failure has on subsequent progression and associated consequences of a light water reactor (LWR) accident, it is important to accurately predict the heatup and relocation of materials within the reactor vessel and heat transfer to and from the reactor vessel. Accurate predictions of such heat transfer phenomena require high temperature thermal properties. However, a review of vessel and structural steel material properties in severe accident analysis codes reveals that the required high temperature material properties are extrapolated with little, if any, data above 700 °C. To reduce uncertainties in predictions relying upon this extrapolated high temperature data, INL obtained data using laser-flash thermal diffusivity techniques for two metals used in LWR vessels: SA 533 Grade B, Class 1 (SA533B1) low alloy steel, which is used to fabricate most US LWR reactor vessels; and Type 304 Stainless Steel SS304, which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data, compares it to existing data in the literature, and provides recommended correlations for thermal properties based on this data.

  4. Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report

    SciTech Connect

    Lori Braase

    2013-01-01

    The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. The emphasis for these activities was on improving the fuel performance in terms of increased burnup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. After the events at the Fukushima Nuclear Power Plant in Japan in March 2011, enhancing the accident tolerance of LWRs became a topic of serious discussion. In the Consolidated Appropriations Act, 2012, Conference Report 112-75, the U.S. Congress directed DOE-NE to: • Give “priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or spent fuel pools.” • Give “special technical emphasis and funding priority…to activities aimed at the development and near-term qualification of meltdown-resistant, accident-tolerant nuclear fuels that would enhance the safety of present and future generations of light water reactors.” • Report “to the Committee, within 90 days of enactment of this act, on its plan for development of meltdown-resistant fuels leading to reactor testing and utilization by 2020.” Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, and operational transients, as well as design-basis and beyond design-basis events. The overall draft strategy for development and demonstration is comprised of three phases: Feasibility Assessment and Down-selection; Development and Qualification; and

  5. Site S-7 Representative Model and Application for the Vadose Zone Monitoring System (VZMS) McClellan AFB - 1998 Semi-Annual Report

    SciTech Connect

    James, A.L.; Oldenburg, C.M.

    1998-12-01

    Vadose zone data collection and enhanced data analysis are continuing for the Vadose Zone Monitoring System (VZMS) installed at site S-7 in IC 34 at McClellan MB. Data from core samples from boreholes drilled in 1998 and from VZMS continuous monitoring are evaluated and compared to previously collected data and analyses. The suite of data collected to date is used to develop and constrain a spatially averaged, one-dimensional site S-7 representative model that is implemented into T2VOC. Testing of the conceptual model under conditions of recharge of 100 mm/yr produces plausible moisture contents relative to data from several sources. Further scoping calculations involving gas-phase TCE transport in the representative model were undertaken. We investigate the role of recharge on TCE transport as well as the role of ion- and gas-phase flow driven by density and barometric pumping effects. This report provides the first example of the application of the site S-7 representative model in th e investigation of subsurface VOC movement.

  6. Survey of LWR environmental control technology performance and cost

    SciTech Connect

    Heeb, C.M.; Aaberg, R.L.; Cole, B.M.; Engel, R.L.; Kennedy, W.E. Jr.; Lewallen, M.A.

    1980-03-01

    This study attempts to establish a ranking for species that are routinely released to the environment for a projected nuclear power growth scenario. Unlike comparisons made to existing standards, which are subject to frequent revision, the ranking of releases can be used to form a more logical basis for identifying the areas where further development of control technology could be required. This report describes projections of releases for several fuel cycle scenarios, identifies areas where alternative control technologies may be implemented, and discusses the available alternative control technologies. The release factors were used in a computer code system called ENFORM, which calculates the annual release of any species from any part of the LWR nuclear fuel cycle given a projection of installed nuclear generation capacity. This survey of fuel cycle releases was performed for three reprocessing scenarios (stowaway, reprocessing without recycle of Pu and reprocessing with full recycle of U and Pu) for a 100-year period beginning in 1977. The radioactivity releases were ranked on the basis of a relative ranking factor. The relative ranking factor is based on the 100-year summation of the 50-year population dose commitment from an annual release of radioactive effluents. The nonradioactive releases were ranked on the basis of dilution factor. The twenty highest ranking radioactive releases were identified and each of these was analyzed in terms of the basis for calculating the release and a description of the currently employed control method. Alternative control technology is then discussed, along with the available capital and operating cost figures for alternative control methods.

  7. First Semiannual Report of the National Aeronautics and Space Administration

    NASA Technical Reports Server (NTRS)

    Glennan, T. Keith

    1959-01-01

    The First Semiannual Report of the National Aeronautics and Space Administration (NASA) is submitted to Congress pursuant to section 206 (a) of the National Aeronautics and Space Act of 1958 (Public Law 85-568) to provide for research into problems of flight within and outside the Earth's atmosphere, which states: The Administration shall submit to the President for transmittal to Congress, semiannually and at such other times as it deems desirable, a report on its activities and accomplishments.

  8. 34 CFR 82.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 34 Education 1 2010-07-01 2010-07-01 false Semi-annual compilation. 82.600 Section 82.600 Education Office of the Secretary, Department of Education NEW RESTRICTIONS ON LOBBYING Agency Reports § 82.600 Semi-annual compilation. (a) The head of each agency shall collect and compile the disclosure reports (see appendix B) and, on May 31 and...

  9. Federal Reserve System Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-20

    ...), to implement provisions of the Credit Card Act that became effective on August 20, 2009, 74 FR 36077... provisions of the Credit Card Act that became effective on February 22, 2010, 74 FR 54124. In January 2010... August 22, 1010 (75 FR 12334). The proposed rule would have required that penalty fees imposed by...

  10. 31 CFR 359.11 - What is the semiannual inflation rate?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false What is the semiannual inflation rate... BONDS, SERIES I General Information § 359.11 What is the semiannual inflation rate? The index used to determine the semiannual inflation rate is the non-seasonally adjusted CPI-U (the Consumer Price Index...

  11. 25 CFR 141.24 - Attendance at semi-annual meetings.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... THE NAVAJO, HOPI AND ZUNI RESERVATIONS General Business Practices § 141.24 Attendance at semi-annual... 25 Indians 1 2010-04-01 2010-04-01 false Attendance at semi-annual meetings. 141.24 Section 141.24... attend a semi-annual public meeting of a tribal governing body to respond to customer inquiries....

  12. 31 CFR Appendix B to Part 359 - Composite Semiannual Rate Period Table

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 31 Money and Finance:Treasury 2 2013-07-01 2013-07-01 false Composite Semiannual Rate Period Table... SAVINGS BONDS, SERIES I Pt. 359, App. B Appendix B to Part 359—Composite Semiannual Rate Period Table 1. What months make up the composite semiannual rate period? You may use the following table to find...

  13. 31 CFR Appendix B to Part 359 - Composite Semiannual Rate Period Table

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 31 Money and Finance:Treasury 2 2012-07-01 2012-07-01 false Composite Semiannual Rate Period Table... SAVINGS BONDS, SERIES I Pt. 359, App. B Appendix B to Part 359—Composite Semiannual Rate Period Table 1. What months make up the composite semiannual rate period? You may use the following table to find...

  14. 31 CFR Appendix B to Part 359 - Composite Semiannual Rate Period Table

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 31 Money and Finance: Treasury 2 2014-07-01 2014-07-01 false Composite Semiannual Rate Period... SAVINGS BONDS, SERIES I Pt. 359, App. B Appendix B to Part 359—Composite Semiannual Rate Period Table 1. What months make up the composite semiannual rate period? You may use the following table to find...

  15. Uranium mononitride as a potential commercial LWR fuel

    SciTech Connect

    Xu, P.; Yan, J.; Lahoda, E. J.; Ray, S.

    2012-07-01

    This paper evaluated uranium mononitride (UN) as a potential replacement for 5% enriched UO{sub 2} fuel in Generation III and III+ commercial light water reactors (LWRs). Significant improvement in LWR performance depends on developing and implementing changes in the nuclear fuel used in these reactors. Compared to UO{sub 2}, UN offers several advantages such as higher uranium loading and better thermal conductivity. In this paper, the thermal safety margin of UN was evaluated at both normal and accident conditions using a readily available coupled CFD model developed for the US DOE CASL program. One of the prime technical challenges in utilization of UN as LWR fuel is the water compatibility because pure phase UN is not stable in water at 350 deg. C. The water corrosion resistance of UN and the corrosion mechanism were reviewed and mitigation methods were proposed. (authors)

  16. Equipment designs for the spent LWR fuel dry storage demonstration

    SciTech Connect

    Steffen, R.J.; Kurasch, D.H.; Hardin, R.T.; Schmitten, P.F.

    1980-01-01

    In conjunction with the Spent Fuel Handling and Packaging Program (SFHPP) equipment has been designed, fabricated and successfully utilized to demonstrate the packaging and interim dry storage of spent LWR fuel. Surface and near surface storage configurations containing PWR fuel assemblies are currently on test and generating baseline data. Specific areas of hardware design focused upon include storage cell components and the support related equipment associated with encapsulation, leak testing, lag storage, and emplacement operations.

  17. Understanding EUV mask blank surface roughness induced LWR and associated roughness requirement

    SciTech Connect

    Yan, Pei-Yang; Zhang, Guojing; Gullickson, Eric M.; Goldberg, Kenneth A.; Benk, Markus P.

    2015-03-01

    Extreme ultraviolet lithography (EUVL) mask multi-layer (ML) blank surface roughness specification historically comes from blank defect inspection tool requirement. Later, new concerns on ML surface roughness induced wafer pattern line width roughness (LWR) arise. In this paper, we have studied wafer level pattern LWR as a function of EUVL mask surface roughness via High-NA Actinic Reticle Review Tool. We found that the blank surface roughness induced LWR at current blank roughness level is in the order of 0.5nm 3σ for NA=0.42 at the best focus. At defocus of ±40nm, the corresponding LWR will be 0.2nm higher. Further reducing EUVL mask blank surface roughness will increase the blank cost with limited benefit in improving the pattern LWR, provided that the intrinsic resist LWR is in the order of 1nm and above.

  18. LWR fuel rod bundle behavior under severe fuel damage conditions

    SciTech Connect

    Kuczera, B. Hagen, S.; Hofmann, P.

    1988-01-01

    Light water reactor (LWR) safety research and development activities conducted at Kernforschungszentrum Karlsruhe have recently been reorganized with a concentrated mission under the LWR safety project group. The topics treated relate mainly to severe-accident analysis research and source term assessment as well as to source term mitigation measures. A major part of the investigations concerns the early phase of a severe core meltdown accident, specifically LWR rod assembly behavior under sever fuel damage (SFD) conditions. To determine the extent of fuel rod damage, including the relocation behavior of molten reaction products, damage propagation, time-dependent H{sub 2} generation from clad oxidation, and fragmentation of oxygen-embrittled materials during cooldown and quenching, extensive out-of-pile rod bundle experiments have been initiated in the new CORA test facility. The bundle parameters, such as rod dimensions, rod pitch, and grid spacer, can be adjusted to both pressurized water reactor (PWR) and boiling water reactor (BWR) conditions. Currently, the test program consists of 15 experiments in which the influence of Inconel grid spacer, (Ag,In,Cd)-absorber rods (PWR) and of B{sub 4}C control blades (BWR) on fuel damage initiation and damage propagation are being investigated for different boundary conditions. As of June 1988, four bundle tests had been successfully carried out for PWR accident conditions.

  19. Assessment of LWR piping design loading based on plant operating experience

    SciTech Connect

    Svensson, P. O.

    1980-08-01

    The objective of this study has been to: (1) identify current Light Water Reactor (LWR) piping design load parameters, (2) identify significant actual LWR piping loads from plant operating experience, (3) perform a comparison of these two sets of data and determine the significance of any differences, and (4) make an evaluation of the load representation in current LWR piping design practice, in view of plant operating experience with respect to piping behavior and response to loading.

  20. Collation of monthly and semiannual reports covering instrumentation at the Decade 80 house in Tucson, Arizona

    NASA Technical Reports Server (NTRS)

    1978-01-01

    The Decade 80 solar house, located in Tucson, Arizona, was built to show the use of copper in home building and to demonstrate the use of solar energy to provide space heating and cooling and domestic hot water. The auxiliary energy sources are electrical resistance heating for the domestic hot water and a gas fired boiler for space heating and operation of the absorption air conditioning units. The Semi-Annual report gives an overview of the instrumentation effort with the back-up monthly reports reflecting more detail of the effort that went into the implementation of the data acquisition system.

  1. Surface-gasification materials program. Semiannual progress report for the period ending March 31, 1982

    SciTech Connect

    Not Available

    1982-08-01

    The objective of the Surface Gasification Materials Program is to conduct research and development on materials for application to the specific needs of coal gasification systems. The Program is divided into two subprograms: (1) the Gasification Systems Fabrication Technology Program and (2) the Materials Application and Development Program. The purpose of the Gasification Systems Fabrication Technology Program is to evaluate innovative fabrication methods which have the potential to lower costs and improve reliability and safety for gasifier vessels and components. The purpose of the Materials Application and Development Program is to conduct engineering-scale development and application of materials for coal gasification systems to ensure that the materials of construction for pilot plants and future large-scale plants can be properly selected and specified. The management of materials projects in support of surface gasification sponsored by the Headquarters DOE Gasification Division has been defined in an April 16, 1982 METC-sponsored agreement transmitted to DOE field offices and performing contractors. This agreement recognizes the lead role in fossil energy materials delegated by METC to the DOE Oak Ridge Operations Office and the Oak Ridge National Laboratory. The ORNL Fossil Energy Materials Program Office compiles and issues this combined semiannual progress report from camera-ready copies submitted by each of the participating organizations. Distribution is as shown on pages 59 to 63. Future reports will be issued on a semiannual basis to a similar distribution.

  2. Investigation of valve failure problems in LWR power plants

    SciTech Connect

    1980-04-01

    An analysis of component failures from information in the computerized Nuclear Safety Information Center (NSIC) data bank shows that for both PWR and BWR plants the component category most responsible for approximately 19.3% of light water reactor (LWR) power plant shutdowns. This investigation by Burns and Roe, Inc. shows that the greatest cause of shutdowns in LWRs due to valve failures is leakage from valve stem packing. Both BWR plants and PWR plants have stem leakage problems (BWRs, 21% and PWRs, 34%).

  3. 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.

  4. Fission product release from irradiated LWR fuel under accident conditions

    SciTech Connect

    Strain, R.V.; Sanecki, J.E.; Osborne, M.F.

    1984-01-01

    Fission product release from irradiated LWR fuel is being studied by heating fuel rod segments in flowing steam and an inert carrier gas to simulate accident conditions. Fuels with a range of irradiation histories are being subjected to several steam flow rates over a wide range of temperatures. Fission product release during each test is measured by gamma spectroscopy and by detailed examination of the collection apparatus after the test has been completed. These release results are complemented by a detailed posttest examination of samples of the fuel rod segment. Results of release measurements and fuel rod characterizations for tests at 1400 through 2000/sup 0/C are presented in this paper.

  5. LWR codes capability to address SFR BDBA scenarios: Modeling of the ABCOVE tests

    SciTech Connect

    Herranz, L. E.; Garcia, M.; Morandi, S.

    2012-07-01

    The sound background built-up in LWR source term analysis in case of a severe accident, make it worth to check the capability of LWR safety analysis codes to model accident SFR scenarios, at least in some areas. This paper gives a snapshot of such predictability in the area of aerosol behavior in containment. To do so, the AB-5 test of the ABCOVE program has been modeled with 3 LWR codes: ASTEC, ECART and MELCOR. Through the search of a best estimate scenario and its comparison to data, it is concluded that even in the specific case of in-containment aerosol behavior, some enhancements would be needed in the LWR codes and/or their application, particularly with respect to consideration of particle shape. Nonetheless, much of the modeling presently embodied in LWR codes might be applicable to SFR scenarios. These conclusions should be seen as preliminary as long as comparisons are not extended to more experimental scenarios. (authors)

  6. PRAISE-C. LWR Piping Reliability Assessment

    SciTech Connect

    Holman, G.S.

    1992-01-13

    PRAISE-C is a probabilistic fracture mechanics code used to estimate the probability of a double-ended guillotine break (DEGB) in light water reactor piping due to the growth of cracks at welded joints. Pipe failures are considered to occur as the result of crack-like defects either introduced during fabrication, or that initiate after plant operation has begun, and that escape detection during inspections. PRAISE was developed to estimate the influence of earthquakes on the probability of failure at a weld joint in the primary coolant system of a pressurized water reactor. An initial hydrostatic proof test, pre-service non-destructive inspection, and periodic in-service inspection can be simulated. PRAISE treats the inter-arrival times of operating transients, such as system heatup and cooldown, either as constant or exponentially distributed according to observed or postulated rates. Leak rate and leak detection models are also included. Earthquakes of varying intensity and arbitrary occurrence times can be modeled. PRAISE-C extends the capabilities of PRAISE-B to include a tearing instability failure criterion for carbon steels and an advanced probabilistic model of stress corrosion cracking in stainless steels (Type 304, Type 316NG nuclear grade) used for BWR reactor coolant piping. The stress corrosion model is semi-empirical in nature and is based on experimental and field data. The model considers crack initiation, including the number, time, and location of initiated cracks, in addition to the effect of stress corrosion on crack growth rates. Various phenomena are considered, including environment (i.e., coolant temperature, dissolved oxygen content, level of impurities), applied loads, residual stresses, material type, and degree of sensitization.

  7. PRAISE-C. LWR Piping Reliability Assessment

    SciTech Connect

    Eyberger, L.

    1992-01-13

    PRAISE-C is a probabilistic fracture mechanics code used to estimate the probability of a double-ended guillotine break (DEGB) in light water reactor piping due to the growth of cracks at welded joints. Pipe failures are considered to occur as the result of crack-like defects either introduced during fabrication, or that initiate after plant operation has begun, and that escape detection during inspections. PRAISE was developed to estimate the influence of earthquakes on the probability of failure at a weld joint in the primary coolant system of a pressurized water reactor. An initial hydrostatic proof test, pre-service non-destructive inspection, and periodic in-service inspection can be simulated. PRAISE treats the inter-arrival times of operating transients, such as system heatup and cooldown, either as constant or exponentially distributed according to observed or postulated rates. Leak rate and leak detection models are also included. Earthquakes of varying intensity and arbitrary occurrence times can be modeled. PRAISE-C extends the capabilities of PRAISE-B to include a tearing instability failure criterion for carbon steels (supplementing the original net section stress criterion used for austenitic materials), and an advanced probabilistic model of stress corrosion cracking in stainless steels (Type 304, Type 316NG nuclear grade) used for BWR reactor coolant piping. The stress corrosion model is semi-empirical in nature and is based on experimental and field data. The model considers crack initiation, including the number, time, and location of initiated cracks, in addition to the effect of stress corrosion on crack growth rates. Various phenomena are considered, including environment, applied loads, residual stresses, material type, and degree of sensitization. By allowing cracks to initiate after reactor operation has begun, the simulation is not restricted to the original single crack assumption.

  8. A classification scheme for LWR fuel assemblies

    SciTech Connect

    Moore, R.S.; Williamson, D.A.; Notz, K.J.

    1988-11-01

    With over 100 light water nuclear reactors operating nationwide, representing designs by four primary vendors, and with reload fuel manufactured by these vendors and additional suppliers, a wide variety of fuel assembly types are in existence. At Oak Ridge National Laboratory, both the Systems Integration Program and the Characteristics Data Base project required a classification scheme for these fuels. This scheme can be applied to other areas and is expected to be of value to many Office of Civilian Radioactive Waste Management programs. To develop the classification scheme, extensive information on the fuel assemblies that have been and are being manufactured by the various nuclear fuel vendors was compiled, reviewed, and evaluated. It was determined that it is possible to characterize assemblies in a systematic manner, using a combination of physical factors. A two-stage scheme was developed consisting of 79 assembly types, which are grouped into 22 assembly classes. The assembly classes are determined by the general design of the reactor cores in which the assemblies are, or were, used. The general BWR and PWR classes are divided differently but both are based on reactor core configuration. 2 refs., 15 tabs.

  9. Effects of cooling time on a closed LWR fuel cycle

    SciTech Connect

    Arnold, R. P.; Forsberg, C. W.; Shwageraus, E.

    2012-07-01

    In this study, the effects of cooling time prior to reprocessing spent LWR fuel has on the reactor physics characteristics of a PWR fully loaded with homogeneously mixed U-Pu or U-TRU oxide (MOX) fuel is examined. A reactor physics analysis was completed using the CASM04e code. A void reactivity feedback coefficient analysis was also completed for an infinite lattice of fresh fuel assemblies. Some useful conclusions can be made regarding the effect that cooling time prior to reprocessing spent LWR fuel has on a closed homogeneous MOX fuel cycle. The computational analysis shows that it is more neutronically efficient to reprocess cooled spent fuel into homogeneous MOX fuel rods earlier rather than later as the fissile fuel content decreases with time. Also, the number of spent fuel rods needed to fabricate one MOX fuel rod increases as cooling time increases. In the case of TRU MOX fuel, with time, there is an economic tradeoff between fuel handling difficulty and higher throughput of fuel to be reprocessed. The void coefficient analysis shows that the void coefficient becomes progressively more restrictive on fuel Pu content with increasing spent fuel cooling time before reprocessing. (authors)

  10. FMDP reactor alternative summary report: Volume 4, Evolutionary LWR alternative

    SciTech Connect

    1996-09-01

    Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] have become surplus to national defense needs both in the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. The purpose of this report is to provide schedule, cost, and technical information that will be used to support the Record of Process (ROD). Following the screening process, DOE/MD via its national laboratories initiated a more detailed analysis activity to further evaluate each of the ten plutonium disposition alternatives that survived the screening process. Three ``Alternative Teams,`` chartered by DOE and comprised of technical experts from across the DOE national laboratory complex, conducted these analyses. One team was chartered for each of the major disposition classes (borehole, immobilization, and reactors). During the last year and a half, the Fissile Materials Disposition Program (FMDP) Reactor Alternative Team (RxAT) has conducted extensive analyses of the cost, schedule, technical maturity, S&S, and other characteristics of reactor-based plutonium disposition. The results of the RxAT`s analyses of the existing LWR, CANDU, and partially complete LWR alternatives are documented in Volumes 1-3 of this report. This document (Volume 4) summarizes the results of these analyses for the ELWR-based plutonium disposition option.

  11. NRC regualtory agenda. Semiannual report, July 1997--December 1997

    SciTech Connect

    1998-02-01

    The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition.

  12. 13 CFR 146.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Semi-annual compilation. 146.600 Section 146.600 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION NEW RESTRICTIONS ON LOBBYING.... (c) Information that involves intelligence matters shall be reported only to the Select Committee...

  13. 78 FR 44287 - Department Regulatory Agenda; Semiannual Summary

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-23

    ... Planning and Review,'' (58 FR 51735; Oct. 4, 1993) and the Department's Regulatory Policies and Procedures (44 FR 11034; Feb. 26, 1979), the Department prepares a semiannual regulatory agenda. It summarizes... CFR part 218--Lease by Foreign Air Carrier or Other Foreign Person of Aircraft With Crew 14 CFR...

  14. Semiannual Report to Congress, October 1, 2002-March 31, 2003.

    ERIC Educational Resources Information Center

    Office of Inspector General (ED), Washington, DC.

    This semiannual report to Congress by the Office of Inspector General (OIG), U.S. Department of Education, covers the actions of the OIG from October 1, 2002, through March 31, 2003. The report discusses four goals of the President's Management Agenda: (1) improved financial performance: includes information on financial statement audits,…

  15. 45 CFR 1168.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 45 Public Welfare 3 2011-10-01 2011-10-01 false Semi-annual compilation. 1168.600 Section 1168.600 Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES NATIONAL ENDOWMENT FOR THE HUMANITIES NEW RESTRICTIONS ON LOBBYING Agency Reports § 1168.600...

  16. 45 CFR 1168.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 45 Public Welfare 3 2012-10-01 2012-10-01 false Semi-annual compilation. 1168.600 Section 1168.600 Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES NATIONAL ENDOWMENT FOR THE HUMANITIES NEW RESTRICTIONS ON LOBBYING Agency Reports § 1168.600...

  17. 45 CFR 1168.600 - Semi-annual compilation.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 45 Public Welfare 3 2010-10-01 2010-10-01 false Semi-annual compilation. 1168.600 Section 1168.600 Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES NATIONAL ENDOWMENT FOR THE HUMANITIES NEW RESTRICTIONS ON LOBBYING Agency Reports § 1168.600...

  18. 45 CFR 1168.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 45 Public Welfare 3 2014-10-01 2014-10-01 false Semi-annual compilation. 1168.600 Section 1168.600 Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES NATIONAL ENDOWMENT FOR THE HUMANITIES NEW RESTRICTIONS ON LOBBYING Agency Reports § 1168.600...

  19. 45 CFR 1168.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 45 Public Welfare 3 2013-10-01 2013-10-01 false Semi-annual compilation. 1168.600 Section 1168.600 Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL FOUNDATION ON THE ARTS AND THE HUMANITIES NATIONAL ENDOWMENT FOR THE HUMANITIES NEW RESTRICTIONS ON LOBBYING Agency Reports § 1168.600...

  20. 13 CFR 146.600 - Semi-annual compilation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 13 Business Credit and Assistance 1 2014-01-01 2014-01-01 false Semi-annual compilation. 146.600 Section 146.600 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION NEW RESTRICTIONS ON LOBBYING.... (c) Information that involves intelligence matters shall be reported only to the Select Committee...

  1. 13 CFR 146.600 - Semi-annual compilation.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 13 Business Credit and Assistance 1 2012-01-01 2012-01-01 false Semi-annual compilation. 146.600 Section 146.600 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION NEW RESTRICTIONS ON LOBBYING.... (c) Information that involves intelligence matters shall be reported only to the Select Committee...

  2. 13 CFR 146.600 - Semi-annual compilation.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 13 Business Credit and Assistance 1 2013-01-01 2013-01-01 false Semi-annual compilation. 146.600 Section 146.600 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION NEW RESTRICTIONS ON LOBBYING.... (c) Information that involves intelligence matters shall be reported only to the Select Committee...

  3. 13 CFR 146.600 - Semi-annual compilation.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 13 Business Credit and Assistance 1 2011-01-01 2011-01-01 false Semi-annual compilation. 146.600 Section 146.600 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION NEW RESTRICTIONS ON LOBBYING.... (c) Information that involves intelligence matters shall be reported only to the Select Committee...

  4. Mountains versus valleys: Semiannual variation of geomagnetic activity

    NASA Astrophysics Data System (ADS)

    Cliver, E. W.; Kamide, Y.; Ling, A. G.

    2000-02-01

    The semiannual variation in geomagnetic activity is generally attributed to the Russell-McPherron effect. In that picture, enhancements of southward field Bs near the equinoxes account for the observed higher geomagnetic activity in March and September. In a contrary point of view, we argue that the bulk of the semiannual variation results from an equinoctial effect (based on the ψ angle between the solar wind flow direction and Earth's dipole axis) that makes Bs coupling less effective (by ~25% on average) at the solstices. Thus the semiannual variation is not simply due to ``mountain building'' (creation of Bs) at the equinoxes but results primarily from ``valley digging'' (loss of coupling efficiency) at the solstices. We estimate that this latter effect, which clearly reveals itself in the diurnal variation of the am index, is responsible for ~65% of the semiannual modulation. The characteristic imprint of the equinoctial hypothesis is also apparent in hourly/monthly averages of the time-differential Dst index and the AE index.

  5. Proposed geomagnetic control of semiannual waves in the mesospheric zonal wind

    NASA Technical Reports Server (NTRS)

    Belmont, A. D.; Nastrom, G. D.; Mayr, H. G.

    1974-01-01

    The polar semiannual oscillation in zonal wind can explain midwinter weakening of the polar vortex and the relatively short stratospheric and mesospheric summar easterlies. The phase of the wind oscillation is equinoctial, as is the phase of the semiannual component in magnetic storm activity. For a given altitude, the contours of amplitude of the semiannual wind oscillation have less variability in geomagnetic than in geographic coordinates. It is suggested that polar wind oscillations are caused by the semiannual maxima in magnetic storm activity which lead to electron dissociation of O2 into O, in turn increasing ozone more rapidly than the dissociation of N2 destroys ozone, and thereby inducing a semiannual variation in the thermal and wind fields. This implies that geomagnetic processes may cause or affect the development of sudden warmings. As the tropical semiannual wind oscillation is symmetric about the geomagnetic equator, the same processes may also influence the location of the tropical wind wave.

  6. Proposed geomagnetic control of semiannual waves in the mesospheric zonal wind

    NASA Technical Reports Server (NTRS)

    Belmont, A. D.; Nastrom, G. D.; Mayr, H. G.

    1975-01-01

    The polar semiannual oscillation in zonal wind explains midwinter weakening of the polar vortex and the relatively short stratospheric and mesospheric summer easterlies. The phase of the wind oscillation is equinoctial, as is the phase of the semiannual component in magnetic storm activity. For a given altitude, the contours of amplitude of the semiannual wind oscillation have less variability in geomagnetic than in geographic coordinates. It is suggested that the polar wind oscillations are caused by the semiannual maxima in magnetic storm activity, which lead to electron dissociation of O2 into O, in turn increasing ozone more rapidly than the dissociation of N2 destroys ozone, and inducing a semiannual variation in the thermal and wind fields. This implies that geomagnetic processes may cause or affect the development of sudden warmings. As the tropical semiannual wind oscillation is symmetric about the geomagnetic equator, the same processes may also influence the location of the tropical wind wave.

  7. Assessment of nitrogen as an atmosphere for dry storage of spent LWR fuel

    SciTech Connect

    Gilbert, E.R.; Knox, C.A.; White, G.D.

    1985-09-01

    Interim dry storage of spent light-water reactor (LWR) fuel is being developed as a licensed technology in the United States. Because it is anticipated that license agreements will specify dry storage atmospheres, the behavior of spent LWR fuel in a nitrogen atmosphere during dry storage was investigated. In particular, the thermodynamics of reaction of nitrogen compounds (expected to form in the cover gas during dry storage) and residual impurities (such as moisture and oxygen) with Zircaloy cladding and with spent fuel at sites of cladding breaches were examined. The kinetics of reaction were not considered it was assumed that the 20 to 40 years of interim dry storage would be sufficient for reactions to proceed to completion. The primary thermodynamics reactants were found to be NO/sub 2/, N/sub 2/O, H/sub 2/O/sub 2/, and O/sub 2/. The evaluation revealed that the limited inventories of these reactants produced by the source terms in hermetically sealed dry storage systems would be too low to cause significant spent fuel degradation. Furthermore, the oxidation of spent fuel to degrading O/U ratios is unlikely because the oxidation potential in moist nitrogen limits O/U ratios to values less than UO/sub 2.006/ (the equilibrium stoichiometric form in equilibrium with moist nitrogen). Tests were performed with bare spent UO/sub 2/ fuel and nonirradiated UO/sub 2/ pellets (with no Zircaloy cladding) in a nitrogen atmosphere containing moisture concentrations greater than encountered under dry storage conditions. These tests were performed for at least 1100 h at temperatures as high as 380/sup 0/C, where oxidation reactions proceed in a matter of minutes. No visible degradation was detected, and weight changes were negligible.

  8. Platoon Interactions and Real-World Traffic Simulation and Validation Based on the LWR-IM.

    PubMed

    Ng, Kok Mun; Reaz, Mamun Bin Ibne

    2016-01-01

    Platoon based traffic flow models form the underlying theoretical framework in traffic simulation tools. They are essentially important in facilitating efficient performance calculation and evaluation in urban traffic networks. For this purpose, a new platoon-based macroscopic model called the LWR-IM has been developed in [1]. Preliminary analytical validation conducted previously has proven the feasibility of the model. In this paper, the LWR-IM is further enhanced with algorithms that describe platoon interactions in urban arterials. The LWR-IM and the proposed platoon interaction algorithms are implemented in the real-world class I and class II urban arterials. Another purpose of the work is to perform quantitative validation to investigate the validity and ability of the LWR-IM and its underlying algorithms to describe platoon interactions and simulate performance indices that closely resemble the real traffic situations. The quantitative validation of the LWR-IM is achieved by performing a two-sampled t-test on queues simulated by the LWR-IM and real queues observed at these real-world locations. The results reveal insignificant differences of simulated queues with real queues where the p-values produced concluded that the null hypothesis cannot be rejected. Thus, the quantitative validation further proved the validity of the LWR-IM and the embedded platoon interactions algorithm for the intended purpose. PMID:26731745

  9. Platoon Interactions and Real-World Traffic Simulation and Validation Based on the LWR-IM

    PubMed Central

    Ng, Kok Mun; Reaz, Mamun Bin Ibne

    2016-01-01

    Platoon based traffic flow models form the underlying theoretical framework in traffic simulation tools. They are essentially important in facilitating efficient performance calculation and evaluation in urban traffic networks. For this purpose, a new platoon-based macroscopic model called the LWR-IM has been developed in [1]. Preliminary analytical validation conducted previously has proven the feasibility of the model. In this paper, the LWR-IM is further enhanced with algorithms that describe platoon interactions in urban arterials. The LWR-IM and the proposed platoon interaction algorithms are implemented in the real-world class I and class II urban arterials. Another purpose of the work is to perform quantitative validation to investigate the validity and ability of the LWR-IM and its underlying algorithms to describe platoon interactions and simulate performance indices that closely resemble the real traffic situations. The quantitative validation of the LWR-IM is achieved by performing a two-sampled t-test on queues simulated by the LWR-IM and real queues observed at these real-world locations. The results reveal insignificant differences of simulated queues with real queues where the p-values produced concluded that the null hypothesis cannot be rejected. Thus, the quantitative validation further proved the validity of the LWR-IM and the embedded platoon interactions algorithm for the intended purpose. PMID:26731745

  10. Semiannual behaviour of monthly mean of Bz component of geoeffective (Kp>3) coronal mass ejections

    NASA Astrophysics Data System (ADS)

    Baranyi, T.; Ludmány, A.

    2003-09-01

    The annual/semiannual behaviour of montly mean IMF Bz component as well as the number of hours spent by the Earth in domains of either positive or negative GSE/GSM By component were studied in the case of geoeffective (Kp>3) CMEs. The consecutive solar dipole cycles were separated, and definite differences were found between the annual variations of the mean values. When the solar dipole is opposite to the terrestrial one, the manifestation of the Russell-McPherron effect in the annual variation of mean GSM Bz is weak because there are strong inverse annual variations in the GSE system. However, the Russell-McPherron effect can be detected in the occurrence of the negative and positive By values. The case is opposite in those years when the solar and terrestrial dipoles are parallel: the Russell-McPherron effect is well detectable in the opposite annual variations of the mean GSM Bz but the occurrence of By directions shows polarity-independent semiannual variation.

  11. A Review and Analysis of European Industrial Experience in Handling LWR Spent Fuel and Vitrified High-Level Waste

    SciTech Connect

    Blomeke, J.O.

    2001-07-10

    The industrial facilities that have been built or are under construction in France, the United Kingdom, Sweden, and West Germany to handle light-water reactor (LWR) spent fuel and canisters of vitrified high-level waste before ultimate disposal are described and illustrated with drawings and photographs. Published information on the operating performance of these facilities is also given. This information was assembled for consideration in planning and design of similar equipment and facilities needed for the Federal Waste Management System in the United States.

  12. Characteristics Data Base: Programmer's guide to the LWR Quantities Data Base

    SciTech Connect

    Jones, K.E. ); Moore, R.S. )

    1990-08-01

    The LWR Quantities Data Base is a menu-driven PC data base developed as part of OCRWM's waste, technical data base on the characteristics of potential repository wastes, which also includes non-LWR spent fuel, high-level and other materials. This programmer's guide completes the documentation for the LWR Quantities Data Base, the user's guide having been published previously. The PC data base itself may be requested from the Oak Ridge National Laboratory, using the order form provided in Volume 1 of publication DOE/RW-0184.

  13. ORNL studies of fission product release under LWR accident conditions

    SciTech Connect

    Osborne, M.F.; Lorenz, R.A.; Collins, J.L.

    1991-01-01

    High burnup Zircaloy-clad UO{sub 2} fuel specimens have been heated to study the release of fission products in tests simulating LWR accident conditions. The dominant variable was found to be temperature, with atmosphere, time, and burnup also being significant variables. Comparison of data from tests in steam and hydrogen, at temperatures of 2000 to 2700 K, have shown that the releases of the most volatile species (Kr, Xe, I, and Cs) are relatively insensitive to atmosphere. The releases of the less-volatile species (Sr, Mo, Ru, Sb, Te, Ba, and Eu), however, may vary by orders of magnitude depending on atmosphere. In addition, the atmosphere may drastically affect the mode and extent of fuel destruction.

  14. Feasibility of performing criticality experiments with spent LWR fuel

    SciTech Connect

    Bierman, S.R.

    1988-02-01

    Criticality experiments can be performed with irradiated LWR fuel under very well defined and controlled conditions to provide data sutiable for verifying calculational models. Two facilities currently exist in which such experiments could be performed. Furthermore, the experiments can be performed in a timely manner and for a relatively reasonable cost. It is expected the cost will be greater than those normally incurred for similar experiments with unirradiated fuel because of the handling problems created by the high radiation fields. Although the cost will of course depend on the scoper of the experimental programs, current estimates indicate the costs will be less or comparable to a similar level of effort in other activities with irradiated fuel (e.g., Dry Rod Consolation Project). 2 figs.

  15. Ventilation systems for a spent LWR fuel recycle complex

    SciTech Connect

    Not Available

    1981-01-01

    A conceptual design study has been made of a facility to recycle spent Light Water Reactor fuel. This study was based on coprocessing of plutonium and uranium where plutonium is never available as a separate material. The design of the fuel reprocessing facilities is based on remote operation and remote maintenance. The experience of many years of safe and dependable operation of government fuel processing facilities at Savannah River and Hanford was used in the design. A requirement of the study was that the facilities be licensable under Title 10 and Title 40 of the Code of Federal Regulations.

  16. Code System For Calculating Reactivity Transients In a LWR.

    Energy Science and Technology Software Center (ESTSC)

    1999-03-16

    Version 00 RETRANS is appropriate to calculate power excursions in light water reactors initiated by reactivity insertions due to withdrawal of control elements. The neutron physical model is based on the time-dependent two-group neutron diffusion equations. The equation of state of the coolant is approximated by a table built into the code. RETRANS solves the heat conduction equation and calculates the heat transfer coefficient for representative fuel rods at each time-step.

  17. Code System to Predict LWR Reflood Heat Transfer.

    Energy Science and Technology Software Center (ESTSC)

    1999-04-27

    Version: 00 REFLUX calculates the temperature-time history of a representative fuel rod during the reflood stage of a hypothetical loss-of-coolant accident (LOCA). The logic used fo selection of the appropriate flow regime for analysis of the cladding temperature transient is based on the axial position with regard to the continuous liquid level (based on a mass balance), a liquid carry-over criterion (derived from a force balance on a drop suspended in a vapor stream), andmore » the local cladding surface temperature. A generalized boiling curve is constructed, and the local flow and clad conditions determine the applicable heat transfer coefficient.« less

  18. LWR fuel assembly designs for the transmutation of LWR Spent Fuel TRU with FCM and UO{sub 2}-ThO{sub 2} Fuels

    SciTech Connect

    Bae, G.; Hong, S. G.

    2013-07-01

    In this paper, transmutation of transuranic (TRU) nuclides from LWR spent fuels is studied by using LWR fuel assemblies which consist of UO{sub 2}-ThO{sub 2} fuel pins and FCM (Fully Ceramic Microencapsulated) fuel pins. TRU from LWR spent fuel is loaded in the kernels of the TRISO particle fuels of FCM fuel pins. In the FCM fuel pins, the TRISO particle fuels are distributed in SiC matrix having high thermal conductivity. The loading patterns of fuel pins and the fuel compositions are searched to have high transmutation rate and feasible neutronic parameters including pin power peaking, temperature reactivity coefficients, and cycle length. All studies are done only in fuel assembly calculation level. The results show that our fuel assembly designs have good transmutation performances without multi-recycling and without degradation of the safety-related neutronic parameters. (authors)

  19. Metholology for the selection of LWR safety R and D projects. Phase I, status report

    SciTech Connect

    El-Sheikh, K. A.

    1980-03-01

    The objective of the LWR R and D Selection Methodology Program is to develop and demonstrate an R and D selection methodology appropriate for LWR safety technology. This report documents the development work from the program beginning in April, 1979 to the end of Fiscal Year 1979. The scope of work for this period included three tasks; methodology review (Task 1), measures development (Task 2), and methodology development for the first phase of application (Task 3). The accomplishments of these tasks are presented.

  20. 31 CFR Appendix B to Part 359 - Composite Semiannual Rate Period Table

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 31 Money and Finance:Treasury 2 2011-07-01 2011-07-01 false Composite Semiannual Rate Period Table B Appendix B to Part 359 Money and Finance: Treasury Regulations Relating to Money and Finance... SAVINGS BONDS, SERIES I Pt. 359, App. B Appendix B to Part 359—Composite Semiannual Rate Period Table...

  1. 40 CFR 62.15350 - If a semiannual report is required, when must I submit it?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 9 2013-07-01 2013-07-01 false If a semiannual report is required, when must I submit it? 62.15350 Section 62.15350 Protection of Environment ENVIRONMENTAL PROTECTION... it? (a) For data collected during the first half of a calendar year, submit your semiannual report...

  2. 40 CFR 60.1420 - If a semiannual report is required, when must I submit it?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 6 2011-07-01 2011-07-01 false If a semiannual report is required, when must I submit it? 60.1420 Section 60.1420 Protection of Environment ENVIRONMENTAL PROTECTION... § 60.1420 If a semiannual report is required, when must I submit it? (a) For data collected during...

  3. 40 CFR 60.1895 - If a semiannual report is required, when must I submit it?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 6 2011-07-01 2011-07-01 false If a semiannual report is required, when must I submit it? 60.1895 Section 60.1895 Protection of Environment ENVIRONMENTAL PROTECTION..., 1999 Model Rule-Reporting § 60.1895 If a semiannual report is required, when must I submit it? (a)...

  4. Federal Energy Resources Modernization Coordinating Committee. Semiannual Report, October 1, 1991 Through March 31, 1992

    SciTech Connect

    Parker, G B

    1992-07-01

    This report summarizes the broad range of activities supported by Federal Energy Management Program (FEMP) and other federal agencies focused on meeting the President`s Executive Order on Federal Energy Management promulgated to meet energy savings goals and encourage more efficient management of all federal energy resources. These activities are reported semiannually under the auspices of the FERM Coordinating Committee, and as such include activities undertaken from October 1, 1991, through March 31, 1992. The activities reported are classified into four major categories: (1) technology-base support, which includes development of processes, software, metering and monitoring equipment and strategies, and other tools for the federal energy manager to better understand and characterize their energy resources; (2) federal energy systems testing and monitoring; (3) federal energy systems modernization projects at federal installations in cooperation with the utilities serving the sites; and (4) energy supply, distribution and end-use conservation assessment for federal agencies and/or facilities.

  5. Isotope separation and advanced manufacturing technology. Volume 2, No. 2, Semiannual report, April--September 1993

    SciTech Connect

    Kan, Tehmanu; Carpenter, J.

    1993-12-31

    This is the second issue of a semiannual report for the Isotope Separation and Advanced Manufacturing (ISAM) Technology Program at Lawrence Livermore National Laboratory. Primary objectives of the ISAM Program include: the Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) process, and advanced manufacturing technologies which include industrial laser materials processing and new manufacturing technologies for uranium, plutonium, and other strategically important materials in support of DOE and other national applications. Topics included in this issue are: production plant product system conceptual design, development and operation of a solid-state switch for thyratron replacement, high-performance optical components for high average power laser systems, use of diode laser absorption spectroscopy for control of uranium vaporization rates, a two-dimensional time dependent hydrodynamical ion extraction model, and design of a formaldehyde photodissociation process for carbon and oxygen isotope separation.

  6. Surface Gasification Materials Program: Semiannual progress report for the period ending September 30, 1986. [Iron aluminide

    SciTech Connect

    Not Available

    1987-01-01

    The objective of the Surface Gasification Materials Program is to conduct research and development on materials for application to the specific needs of coal gasification systems. One of the goals of the program is to evaluate innovative fabrication methods which have the potential to lower costs and improve reliability and safety for gasifier vessels and components. Another goal is to conduct engineering-scale development and application of materials for coal gasification systems to ensure that the materials of construction for pilot plants and future large-scale plants can be properly selected and specified. This semiannual progress report covers: (1) protective coatings and claddings - application/evaluation; (2) electroslag component casting; (3) materials development for solid oxide oxygen production unit; and (4) development of iron aluminides.

  7. Advanced multiphysics coupling for LWR fuel performance analysis

    SciTech Connect

    Hales, J. D.; Tonks, M. R.; Gleicher, F. N.; Spencer, B. W.; Novascone, S. R.; Williamson, R. L.; Pastore, G.; Perez, D. M.

    2015-10-01

    Even the most basic nuclear fuel analysis is a multiphysics undertaking, as a credible simulation must consider at a minimum coupled heat conduction and mechanical deformation. The need for more realistic fuel modeling under a variety of conditions invariably leads to a desire to include coupling between a more complete set of the physical phenomena influencing fuel behavior, including neutronics, thermal hydraulics, and mechanisms occurring at lower length scales. This paper covers current efforts toward coupled multiphysics LWR fuel modeling in three main areas. The first area covered in this paper concerns thermomechanical coupling. The interaction of these two physics, particularly related to the feedback effect associated with heat transfer and mechanical contact at the fuel/clad gap, provides numerous computational challenges. An outline is provided of an effective approach used to manage the nonlinearities associated with an evolving gap in BISON, a nuclear fuel performance application. A second type of multiphysics coupling described here is that of coupling neutronics with thermomechanical LWR fuel performance. DeCART, a high-fidelity core analysis program based on the method of characteristics, has been coupled to BISON. DeCART provides sub-pin level resolution of the multigroup neutron flux, with resonance treatment, during a depletion or a fast transient simulation. Two-way coupling between these codes was achieved by mapping fission rate density and fast neutron flux fields from DeCART to BISON and the temperature field from BISON to DeCART while employing a Picard iterative algorithm. Finally, the need for multiscale coupling is considered. Fission gas production and evolution significantly impact fuel performance by causing swelling, a reduction in the thermal conductivity, and fission gas release. The mechanisms involved occur at the atomistic and grain scale and are therefore not the domain of a fuel performance code. However, it is possible to use

  8. Advanced multiphysics coupling for LWR fuel performance analysis

    DOE PAGESBeta

    Hales, J. D.; Tonks, M. R.; Gleicher, F. N.; Spencer, B. W.; Novascone, S. R.; Williamson, R. L.; Pastore, G.; Perez, D. M.

    2015-10-01

    Even the most basic nuclear fuel analysis is a multiphysics undertaking, as a credible simulation must consider at a minimum coupled heat conduction and mechanical deformation. The need for more realistic fuel modeling under a variety of conditions invariably leads to a desire to include coupling between a more complete set of the physical phenomena influencing fuel behavior, including neutronics, thermal hydraulics, and mechanisms occurring at lower length scales. This paper covers current efforts toward coupled multiphysics LWR fuel modeling in three main areas. The first area covered in this paper concerns thermomechanical coupling. The interaction of these two physics,more » particularly related to the feedback effect associated with heat transfer and mechanical contact at the fuel/clad gap, provides numerous computational challenges. An outline is provided of an effective approach used to manage the nonlinearities associated with an evolving gap in BISON, a nuclear fuel performance application. A second type of multiphysics coupling described here is that of coupling neutronics with thermomechanical LWR fuel performance. DeCART, a high-fidelity core analysis program based on the method of characteristics, has been coupled to BISON. DeCART provides sub-pin level resolution of the multigroup neutron flux, with resonance treatment, during a depletion or a fast transient simulation. Two-way coupling between these codes was achieved by mapping fission rate density and fast neutron flux fields from DeCART to BISON and the temperature field from BISON to DeCART while employing a Picard iterative algorithm. Finally, the need for multiscale coupling is considered. Fission gas production and evolution significantly impact fuel performance by causing swelling, a reduction in the thermal conductivity, and fission gas release. The mechanisms involved occur at the atomistic and grain scale and are therefore not the domain of a fuel performance code. However, it is

  9. Uranium Nitride as LWR TRISO Fuel: Thermodynamic Modeling of U-C-N

    SciTech Connect

    Besmann, Theodore M; Shin, Dongwon

    2012-01-01

    TRISO coated particle fuel is envisioned as a next generation replacement for current urania pellet fuel in LWR applications. To obtain adequate fissile loading the kernel of the TRISO particle will need to be UN. In support of the fuel development effort, an assessment of phase regions of interest in the U-C-N system was undertaken as the fuel will be prepared by the carbothermic reduction of the oxide and it will be in equilibrium with carbon within the TRISO particle. The phase equilibria and thermochemistry of the U-C-N system is reviewed, including nitrogen pressure measurements above various phase fields. Selected measurements were used to fit a first order model of the UC1-xNx phase, represented by the inter-solution of UN and UC. Fit to the data was significantly improved by also adjusting the heat of formation for UN by ~12 kJ/mol and the phase equilbria was best reproduced by also adjusting the heat for U2N3 by +XXX. The determined interaction parameters yielded a slightly positive deviation from ideality, which agrees with lattice parameter measurements which show positive deviation from Vegard s law. The resultant model together with reported values for other phases in the system were used to generate isothermal sections of the U-C-N phase diagram. Nitrogen partial pressures were also computed for regions of interest.

  10. Automated solar cell assembly teamed process research. Semiannual subcontract report, December 6, 1993--June 30, 1994

    SciTech Connect

    Nowlan, M.

    1995-01-01

    This is the second Semiannual Technical Progress Report for the program titled `Automated Solar Cell Assembly Teamed Process Research` funded under National Renewable Energy Laboratory (NREL) subcontract No. ZAG-3-11219-01. This report describes the work done on Phase II of the program in the period from December 6, 1993 to June 30, 1994. Spire`s objective in this program is to develop high throughput (5 MW/yr) automated processes for interconnecting thin (200 {mu}m) silicon solar cells. High yield will be achieved with these fragile cells through the development of low mechanical stress and low thermal stress processes. For example, a machine vision system is being developed for cell alignment without mechanically contacting the cell edges, while a new soldering process is being developed to solder metal interconnect ribbons simultaneously to a cells` front and back contacts, eliminating one of the two heating steps normally used for soldering each cell.

  11. Program for the improvement of downhole drilling motor bearings and seals. Phase IV. Semi-annual report

    SciTech Connect

    Tibbitts, G.A.; DeLafosse, P.H.; Black, A.; Green, S.J.

    1980-07-01

    Four main areas of development for the project are covered: design and fabrication of a dynamometer and a mud cooling system for the Bearing-Seal Package Test Facility; modification of the Bearing-Seal Package Test Facility based on test results; testing of new lubricant samples from Pacer Lubricants, Inc., in the Terra Tek High Temperature Lubricant Tester; and testing of new seal types in the Terra Tek Sea Tester. The Maurer Engineering Report, Semi-Annual Progress Report on Improvement of Downhole Motor Bearings and Seals by Jeff L. Barnwell, has been included as Appendix B.

  12. Robot Kinematics Identification: KUKA LWR4+ Redundant Manipulator Example

    NASA Astrophysics Data System (ADS)

    Kolyubin, Sergey; Paramonov, Leonid; Shiriaev, Anton

    2015-11-01

    This work is aimed at a comprehensive discussion of algorithms for the kinematic parameters identification of robotic manipulators. We deal with an open-loop geometric calibration task, when a full 6D robot's end-effector pose is measured. Effective solutions of such a task is of high interest in many practical applications, because it can dramatically improve key robot characteristics. On the first step, we select optimal calibration configurations. A comparative analysis of three different algorithms and two observability indexes used for numerical optimization is provided. Afterwards, using the acquired and pre-processed experimental data we identify modified Denavit-Hartenberg parameters of the manipulator. Estimates are obtained resolving original nonlinear forward kinematics relations. Finally, we compare nominal and calibrated geometric parameters and show how much deviations in these parameters affect robot positioning accuracy. To the best of our knowledge, such integrated efforts are new for the KUKA LWR4+ robot and Nikon K610 optical coordinate measuring machine (CMM), which were used in the study. Discussion of practical issues on how to organise the experiment is an additional contribution of this work. The proposed procedure is highly automated and can be implemented to improve manipulator's performance on a periodic basis.

  13. Annual and semiannual variations of the geomagnetic field at equatorial locations

    USGS Publications Warehouse

    Campbell, W.H.

    1981-01-01

    For a year of quiet solar-activity level, geomagnetic records from American hemisphere observatories located between about 0?? and 30?? north geomagnetic latitude were used to compare the annual and semiannual variations of the geomagnetic field associated with three separate contributions: (a) the quiet-day midnight level, MDT; (b) the solar-quiet daily variation, Sq; (c) the quiet-time lunar semidiurnal tidal variation, L(12). Four Fourier spectral constituents (24, 12, 8, 6 h periods) of Sq were individually treated. All three orthogonal elements (H, D and Z) were included in the study. The MDT changes show a dominant semiannual variation having a range of about 7 gammas in H and a dominant annual variation in Z having a range of over 8 gammas. These changes seem to be a seasonal response to the nightside distortions by magnetospheric currents. There is a slow decrease in MDT amplitudes with increasing latitude. The Sq changes follow the patterns expected from an equatorial ionospheric dynamo electrojet current system. The dominant seasonal variations occur in H having a range of over 21 gammas for the 24 h period and over 12 gammas for the 12 h period spectral components. The higher-order components are relatively smaller in size. The Sq(H) amplitudes decrease rapidly with increasing latitude. Magnetospheric contributions to the equatorial Sq must be less than a few per cent of the observed magnitude. The L(12) variation shows the ionospheric electrojet features by the dominance of H and the rapid decrease in amplitude with latitude away from the equator. However, the seasonal variation range of over 7 gammas has a maximum in early February and minimum in late June that is not presently explainable by the known ionospheric conductivity and tidal behavior. ?? 1981.

  14. Methods for incorporating effects of LWR coolant environment into ASME code fatigue evaluations.

    SciTech Connect

    Chopra, O. K.

    1999-04-15

    The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Appendix I to Section HI of the Code specifies design fatigue curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Recent test data illustrate potentially significant effects of LWR environments on the fatigue resistance of carbon and low-alloy steels and austenitic stainless steels (SSs). Under certain loading and environmental conditions, fatigue lives of carbon and low-alloy steels can be a factor of {approx}70 lower in an LWR environment than in air. These results raise the issue of whether the design fatigue curves in Section III are appropriate for the intended purpose. This paper presents the two methods that have been proposed for incorporating the effects of LWR coolant environments into the ASME Code fatigue evaluations. The mechanisms of fatigue crack initiation in carbon and low-alloy steels and austenitic SSs in LWR environments are discussed.

  15. Improved LWR Cladding Performance by EPD Surface Modification Technique

    SciTech Connect

    Corradini, Michael; Sridharan, Kumar

    2012-11-26

    This project will utilize the electro-phoretic deposition technique (EPD) in conjunction with nanofluids to deposit oxide coatings on prototypic zirconium alloy cladding surfaces. After demonstrating that this surface modification is reproducible and robust, the team will subject the modified surface to boiling and corrosion tests to characterize the improved nucleate boiling behavior and superior corrosion performance. The scope of work consists of the following three tasks: The first task will employ the EPD surface modification technique to coat the surface of a prototypic set of zirconium alloy cladding tube materials (e.g. Zircaloy and advanced alloys such as M5) with a micron-thick layer of zirconium oxide nanoparticles. The team will characterize the modified surface for uniformity using optical microscopy and scanning-electron microscopy, and for robustness using standard hardness measurements. After zirconium alloy cladding samples have been prepared and characterized using the EPD technique, the team will begin a set of boiling experiments to measure the heat transfer coefficient and critical heat flux (CHF) limit for each prepared sample and its control sample. This work will provide a relative comparison of the heat transfer performance for each alloy and the surface modification technique employed. As the boiling heat transfer experiments begin, the team will also begin corrosion tests for these zirconium alloy samples using a water corrosion test loop that can mimic light water reactor (LWR) operational environments. They will perform extended corrosion tests on the surface-modified zirconium alloy samples and control samples to examine the robustness of the modified surface, as well as the effect on surface oxidation

  16. Preparation of nuclear libraries with deterministic and stochastic methods for LWR reflectors

    SciTech Connect

    Canepa, S.; Hursin, M.; Ferroukhi, H.; Pautz, A.

    2013-07-01

    The explicit reflector methodology is used in the system of codes CASMO-5 / SIMULATE-3 to include the reflector around the active core into the computational region and avoid adopting any ad-hoc or experimental albedo coefficients as boundary conditions. However, to complete the core calculation, a set of cross sections and discontinuity factors is needed for the reflector nodes and the accuracy of these nuclear parameters influences the final results, in particular along the peripheral regions of the core. In this paper the explicit reflector methodology of CASMO-5 is adopted to evaluate the few-group cross sections and discontinuity factors of the different reflector cases, based on the design of Generation II and III LWR reactors. In addition, in the perspective of using Monte-Carlo codes as a complementary option for lattice calculations of reflector configurations, the stochastic SERPENT code is also included as part of this benchmark. With the latter, the impact of applying 2-D reflector models with homogenized materials instead of explicit representation of the real geometrical structures is moreover evaluated and shown to be limited. (authors)

  17. Mass spectrometric study of the release of volatile fission products from irradiated LWR fuel

    SciTech Connect

    Johnson, I.; Steidl, D.V.; Johnson, C.E.

    1984-01-01

    The objective of these studies is to experimentally determine the chemical form and the rate of release of volatile fission product species from defected irradiated LWR reactor fuel pins. After release from the defected fuel pin the gaseous species immediately enters the ionizer of a quadrupole mass spectrometer thus ensuring that their chemical form is not likely to be changed prior to identification and measurement. These studies differ from prior studies in that: (1) the chemical form of the volatile fission products will be determined; and (2) the detection and measurement method does not depend on the radioactivity of the fission product element. Information on the chemical form of the released fission product species will enable a more accurate description of their transport and reaction in the primary system. These studies are also expected to yield information on the reaction of fission products after release from the fuel oxide with the zircaloy cladding. The results of these studies are expected to increase the understanding of the first step in the release of fission products by irradiated fuel and therefore help in the accurate prediction of source terms.

  18. Technical Development on Burn-up Credit for Spent LWR Fuel

    SciTech Connect

    Gauld, I.C.

    2001-12-26

    Technical development on burn-up credit for spent LWR fuels had been performed at JAERI since 1990 under the contract with Science and Technology Agency of Japan entitled ''Technical Development on Criticality Safety Management for Spent LWR Fuels.'' Main purposes of this work are to obtain the experimental data on criticality properties and isotopic compositions of spent LWR fuels and to verify burnup and criticality calculation codes. In this work three major experiments of exponential experiments for spent fuel assemblies to obtain criticality data, non-destructive gamma-ray measurement of spent fuel rods for evaluating axial burn-up profiles, and destructive analyses of spent fuel samples for determining precise burn-up and isotopic compositions were carried out. The measured data obtained were used for validating calculation codes as well as an examination of criticality safety analyses. Details of the work are described in this report.

  19. A review of irradiation effects on LWR core internal materials - neutron embrittlement.

    SciTech Connect

    Chopra, O. K.; Rao, A. S.

    2011-05-01

    Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of light water reactor (LWR) pressure vessels because of their relatively high strength, ductility, and fracture toughness. However, exposure to neutron irradiation for extended periods not only changes the microstructure and microchemistry of these steels, but also degrades their fracture properties. The existing data on irradiated austenitic SSs are reviewed to determine the effects of key parameters such as material type and condition and irradiation temperature, dose, and dose rate on neutron embrittlement. Differences in the radiation-induced degradation of fracture properties between LWR and fast-reactor irradiations are also discussed. The results are used to (a) define a threshold fluence above which irradiation effects on fracture toughness of the material are significant, (b) evaluate the potential of neutron embrittlement under LWR operating conditions, and (c) assess the potential effects of voids on fracture toughness.

  20. A review of irradiation effects on LWR core internal materials - Neutron embrittlement

    NASA Astrophysics Data System (ADS)

    Chopra, O. K.; Rao, A. S.

    2011-05-01

    Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of light water reactor (LWR) pressure vessels because of their relatively high strength, ductility, and fracture toughness. However, exposure to neutron irradiation for extended periods not only changes the microstructure and microchemistry of these steels, but also degrades their fracture properties. The existing data on irradiated austenitic SSs are reviewed to determine the effects of key parameters such as material type and condition and irradiation temperature, dose, and dose rate on neutron embrittlement. Differences in the radiation-induced degradation of fracture properties between LWR and fast-reactor irradiations are also discussed. The results are used to (a) define a threshold fluence above which irradiation effects on fracture toughness of the material are significant, (b) evaluate the potential of neutron embrittlement under LWR operating conditions, and (c) assess the potential effects of voids on fracture toughness.

  1. Review of literature on the TMI accident and correlation to the LWR Safety Technology Program

    SciTech Connect

    Miller, W.J.

    1980-05-01

    This report is the result of approximately two man-months of effort devoted to assimilating and comprehending significant publicly available material related to Three Mile Island Unit 2 and events during and subsequent to the accident experienced on March 28, 1979. Those events were then correlated with the Preliminary LWR Safety Technology Program Plan (Preliminary Program Plan) prepared for the US Department of Energy by Sandia National Lab. This report is being submitted simultaneously with the SAI report entitled Preliminary Prioritization of Tasks in the Draft LWR Safety Technology Program Plan.

  2. Improvements and applications of COBRA-TF for stand-alone and coupled LWR safety analyses

    SciTech Connect

    Avramova, M.; Cuervo, D.

    2006-07-01

    The advanced thermal-hydraulic subchannel code COBRA-TF has been recently improved and applied for stand-alone and coupled LWR core calculations at the Pennsylvania State Univ. in cooperation with AREVA NP GmbH (Germany)) and the Technical Univ. of Madrid. To enable COBRA-TF for academic and industrial applications including safety margins evaluations and LWR core design analyses, the code programming, numerics, and basic models were revised and substantially improved. The code has undergone through an extensive validation, verification, and qualification program. (authors)

  3. 40 CFR Table 8 to Subpart Vvvvvv... - Emission Limits and Compliance Requirements for Heat Exchange Systems

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Requirements for Heat Exchange Systems 8 Table 8 to Subpart VVVVVV of Part 63 Protection of Environment... Pollutants for Chemical Manufacturing Area Sources Pt. 63, Subpt. VVVVVV, Table 8 Table 8 to Subpart VVVVVV... next semi-annual periodic report required by § 63.152(c)” means the next semi-annual compliance...

  4. 40 CFR Table 8 to Subpart Vvvvvv... - Emission Limits and Compliance Requirements for Heat Exchange Systems

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Requirements for Heat Exchange Systems 8 Table 8 to Subpart VVVVVV of Part 63 Protection of Environment... Pollutants for Chemical Manufacturing Area Sources Pt. 63, Subpt. VVVVVV, Table 8 Table 8 to Subpart VVVVVV... next semi-annual periodic report required by § 63.152(c)” means the next semi-annual compliance...

  5. Magnetospheric and auroral processes. Semiannual progress report, 1 March-31 August 1990

    SciTech Connect

    Reiff, P.H.

    1990-08-01

    Progress was made on the following two projects within the semiannual period: (1) simulations of the magnetic storm of April 1988 using the Magnetospheric Specification Model; and (2) improvement of a user-oriented electric-field model.

  6. Extending dry storage of spent LWR fuel for 100 years.

    SciTech Connect

    Einziger, R. E.

    1998-12-16

    Because of delays in closing the back end of the fuel cycle in the U.S., there is a need to extend dry inert storage of spent fuel beyond its originally anticipated 20-year duration. Many of the methodologies developed to support initial licensing for 20-year storage should be able to support the longer storage periods envisioned. This paper evaluates the applicability of existing information and methodologies to support dry storage up to 100 years. The thrust of the analysis is the potential behavior of the spent fuel. In the USA, the criteria for dry storage of LWR spent fuel are delineated in 10 CFR 72 [1]. The criteria fall into four general categories: maintain subcriticality, prevent the release of radioactive material above acceptable limits, ensure that radiation rates and doses do not exceed acceptable levels, and maintain retrievability of the stored radioactive material. These criteria need to be considered for normal, off-normal, and postulated accident conditions. The initial safety analysis report submitted for licensing evaluated the fuel's ability to meet the requirements for 20 years. It is not the intent to repeat these calculations, but to look at expected behavior over the additional 80 years, during which the temperatures and radiation fields are lower. During the first 20 years, the properties of the components may change because of elevated temperatures, presence of moisture, effects of radiation, etc. During normal storage in an inert atmosphere, there is potential for the cladding mechanical properties to change due to annealing or interaction with cask materials. The emissivity of the cladding could also change due to storage conditions. If there is air leakage into the cask, additional degradation could occur through oxidation in breached rods, which could lead to additional fission gas release and enlargement of cladding breaches. Air in-leakage could also affect cover gas conductivity, cladding oxidation, emissivity changes, and

  7. A model for the temperature and composition effects in the semiannual variations of the thermospheric density

    NASA Technical Reports Server (NTRS)

    Mayr, H. G.; Volland, H.

    1971-01-01

    A model is proposed in which latitudinal variations in composition and temperature are used to interpret the semiannual effect in the thermospheric density. Two heat sources are postulated for the semiannual circulation: one at high latitudes associated with the semiannual component in the occurance of magnetic storms and a second weaker one that peaks at the equator associated with the semiannual migration between both hemispheres. Depending on the relative magnitude of these sources, the latitude regions in which composition and temperature effects dominate vary. The temperature effects however should be expected weakest at low to mid latitudes where the relative concentration of atomic oxygen is enriched during equinox. At high latitudes the semiannual temperature component would peak, associated with an oxygen depletion in the lower thermosphere during equinox. In combining these features it is shown that the total atmospheric density could still exhibit a relatively small latitude dependence in the semiannual component with the tendency to decrease at high latitudes, in agreement with observations.

  8. 78 FR 1594 - Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-08

    ... Regulation Sequence No. Title Identifier No. 326 National Wildlife Refuge 1018-AX36 System; Oil and Gas... System; Oil and Gas Regulations Legal Authority: 16 U.S.C. 668dd-ee; 42 U.S.C. 7401 et seq.; 16 U.S.C... of the Secretary 25 CFR Ch. I 30 CFR Chs. II and VII 36 CFR Ch. I 43 CFR Subtitle A, Chs. I and II...

  9. A review of the effects of coolant environments on the fatigue life of LWR structural materials.

    SciTech Connect

    Chopra, O. K.; Shack, W. J.

    2009-04-01

    The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code specifies design curves for the fatigue life of structural materials in nuclear power plants. However, the effects of light water reactor (LWR) coolant environments were not explicitly considered in the development of the design curves. The existing fatigue-strain-versus-life ({var_epsilon}-N) data indicate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. Under certain environmental and loading conditions, fatigue lives in water relative to those in air can be a factor of 15 lower for austenitic stainless steels and a factor of {approx}30 lower for carbon and low-alloy steels. This paper reviews the current technical basis for the understanding of the fatigue of piping and pressure vessel steels in LWR environments. The existing fatigue {var_epsilon}-N data have been evaluated to identify the various material, environmental, and loading parameters that influence fatigue crack initiation and to establish the effects of key parameters on the fatigue life of these steels. Statistical models are presented for estimating fatigue life as a function of material, loading, and environmental conditions. An environmental fatigue correction factor for incorporating the effects of LWR environments into ASME Code fatigue evaluations is described. This paper also presents a critical review of the ASME Code fatigue design margins of 2 on stress (or strain) and 20 on life and assesses the possible conservatism in the current choice of design margins.

  10. HIGH TEMPERATURE THERMAL AND STRUCTURAL MATERIAL PROPERTIES FOR METALS USED IN LWR VESSELS

    SciTech Connect

    J.L. Rempe; D.L. Knudson; J. E. Daw; J. C. Crepeau

    2008-06-01

    Because of the impact that melt relocation and vessel failure may have on subsequent progression and associated consequences of a Light Water Reactor (LWR) accident, it is important to accurately predict heating and relocation of materials within the reactor vessel, heat transfer to and from the reactor vessel, and the potential for failure of the vessel and structures within it. Accurate predictions of such phenomena require high temperature thermal and structural properties. However, a review of vessel and structural steel material properties used in severe accident analysis codes reveals that the required high temperature material properties are extrapolated with little, if any, data above 1000 K. To reduce uncertainties in predictions relying upon extrapolated high temperature data, Idaho National Laboratory (INL) obtained high data for two metals used in LWR vessels: SA 533 Grade B, Class 1 (SA533B1) low alloy steel, which is used to fabricate most US LWR reactor vessels; and Type 304 Stainless Steel SS304, which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data, and compares it to existing data.

  11. FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative

    SciTech Connect

    Greene, S.R.; Fisher, S.E.; Bevard, B.B.

    1996-09-01

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 3 of a four volume report summarizes the results of these analyses for the partially complete LWR (PCLWR) reactor based plutonium disposition alternative.

  12. Effect of material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments.

    SciTech Connect

    Chopra, O. K.; Alexandreanu, B.; Shack, W. J.; Energy Technology

    2005-07-31

    The ASME Boiler and Pressure Vessel Code provides rules for the design of Class 1 components of nuclear power plants. Figures I-9.1 through I-9.6 of Appendix I to Section III of the Code specify design curves for applicable structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. The existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. Under certain environmental and loading conditions, fatigue lives of austenitic stainless steels (SSs) can be a factor of 20 lower in water than in air. This report presents experimental data on the effect of heat treatment on fatigue crack initiation in austenitic Type 304 SS in LWR coolant environments. A detailed metallographic examination of fatigue test specimens was performed to characterize the crack morphology and fracture morphology. The key material, loading, and environmental parameters and their effect on the fatigue life of these steels are also described. Statistical models are presented for estimating the fatigue {var_epsilon}-N curves for austenitic SSs as a function of material, loading, and environmental parameters. Two methods for incorporating the effects of LWR coolant environments into the ASME Code fatigue evaluations are presented.

  13. Surface Gasification Materials Program. Semiannual progress report for the period ending September 30, 1982

    SciTech Connect

    Not Available

    1982-12-01

    The objective of the Surface Gasification Materials Program is to conduct research and development on materials for application to the specific needs of coal gasification systems. The Program is divided into two subprograms: (1) the Gasification Systems Fabrication Technology Program and (2) the Materials Application and Development Program. The purpose of the Gasification Systems Fabrication Technology Program is to evaluate innovative fabrication methods which have the potential to lower costs and improve reliability and safety for gasifier vessels and components. The purpose of the Materials Application and Development Program is to conduct engineering-scale development and application of materials for coal gasification systems to ensure that the materials of construction for pilot plants and future large-scale plants can be properly selected and specified. The Morgantown Energy Technology Center (METC), in its lead role for gasification projects, is responsible for ensuring that the Surface Gasification Materials Program is responsive to the needs for gasification systems. Under its lead role for fossil energy materials, the Oak Ridge Operations Office (ORO), is responsible for the planning, implementation, and management of the program in accordance with guidance received from METC. The ORNL Fossil Energy Materials Program Office compiles and issues this combined semiannual progress report from camera-ready copies submitted by each of the participating organizations.

  14. Evaluation of measured LWR spent fuel composition data for use in code validation

    SciTech Connect

    Hermann, O.W.; DeHart, M.D.; Murphy, B.D.

    1998-02-01

    Burnup credit (BUC) is a concept applied in the criticality safety analysis of spent nuclear fuel in which credit or partial credit is taken for the reduced reactivity worth of the fuel due to both fissile depletion and the buildup of actinides and fission products that act as net neutron absorbers. Typically, a two-step process is applied in BUC analysis: first, depletion calculations are performed to estimate the isotopic content of spent fuel based on its burnup history; second, three-dimensional (3-D) criticality calculations are performed based on specific spent fuel packaging configurations. In seeking licensing approval of any BUC approach (e.g., disposal, transportation, or storage) both of these two computational procedures must be validated. This report was prepared in support of the validation process for depletion methods applied in the analysis of spent fuel from commercial light-water-reactor (LWR) designs. Such validation requires the comparison of computed isotopic compositions with those measured via radiochemical assay to assess the ability of a computer code to predict the contents of spent fuel samples. The purpose of this report is to address the availability and appropriateness of measured data for use in the validation of isotopic depletion methods. Although validation efforts to date at ORNL have been based on calculations using the SAS2H depletion sequence of the SCALE code system, this report has been prepared as an overview of potential sources of validation data independent of the code system used. However, data that are identified as in use in this report refer to earlier validation work performed using SAS2H in support of BUC. This report is the result of a study of available assay data, using the experience gained in spent fuel isotopic validation and with a consideration of the validation issues described earlier. This report recommends the suitability of each set of data for validation work similar in scope to the earlier work.

  15. Stability of SiC-matrix microencapsulated fuel constituents at relevant LWR conditions

    NASA Astrophysics Data System (ADS)

    Snead, L. L.; Terrani, K. A.; Katoh, Y.; Silva, C.; Leonard, K. J.; Perez-Bergquist, A. G.

    2014-05-01

    This paper addresses certain key feasibility issues facing the application of SiC-matrix microencapsulated fuels for light water reactor application. Issues addressed are the irradiation stability of the SiC-based nano-powder ceramic matrix under LWR-relevant irradiation conditions, the presence or extent of reaction of the SiC matrix with zirconium-based cladding, the stability of the inner and outer pyrolytic graphite layers of the TRISO coating system at this uncharacteristically low irradiation temperature, and the state of the particle-matrix interface following irradiation which could possibly affect thermal transport. In the process of determining these feasibility issues microstructural evolution and change in dimension and thermal conductivity was studied. As a general finding the SiC matrix was found to be quite stable with behavior similar to that of CVD SiC. In magnitude the irradiation-induced swelling of the matrix material was slightly higher and irradiation-degraded thermal conductivity was slightly lower as compared to CVD SiC. No significant reaction of this SiC-based nano-powder ceramic matrix material with Zircaloy was observed. Irradiation of the sample in the 320-360 °C range to a maximum dose of 7.7 × 1025 n/m2 (E > 0.1 MeV) did not have significant negative impact on the constituent layers of the TRISO coating system. At the highest dose studied, layer structure and interface integrity remained essentially unchanged with good apparent thermal transport through the microsphere to the surrounding matrix.

  16. Federal Communications Commission Semiannual Regulatory Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-26

    ... 3060-AI78 Communications Networks 366 Stolen Vehicle Recovery System (SVRS) 3060-AJ01 367 Commercial...... 3060-AF85 397 Telecommunications Carriers' Use of Customer Proprietary Network Information and Other... Telecommunications Act of 3060-AG50 1996 399 Local Telephone Networks That LECs Must Make Available to...

  17. 75 FR 79925 - Semiannual Regulatory Flexibility Agenda

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-20

    ... Federal Reserve System, Washington, DC 20551. FOR FURTHER INFORMATION CONTACT: A staff contact for each item is indicated with the regulatory description below. SUPPLEMENTARY INFORMATION: The Board is... Deregulatory Actions, which is coordinated by the Office of Management and Budget under Executive Order...

  18. Semiannual report for the period October 1, 1979-March 31, 1980 of work on: (1) superconducting power transmission system development; (2) cable insulation development. Power Transmission Project Technical Note No. 106

    SciTech Connect

    Not Available

    1980-07-07

    Progress is reported in a program whose objective is to develop an underground superconducting power transmission system which is economical and technically attractive to the utility industry. The system would be capable of carrying very large blocks of electric power, and would supplant overhead lines in urban and suburban areas and regions of natural beauty. The program consisted initially of work in the laboratory to develop suitable materials, cryostats, and cable concepts. The materials work covers the development and testing of suitable superconductors and dielectric insulation. The laboratory work has now been extended to an outside test facility which represents an intermediate step between the laboratory scale and a full-scale system. The facility will allow cables several hundred feet long to be tested under realistic conditions. In addition, the refrigerator has been designed for optimum service for utility applications.

  19. Comparative analysis of LWR and FBR spent fuels for nuclear forensics evaluation

    NASA Astrophysics Data System (ADS)

    Permana, Sidik; Suzuki, Mitsutoshi; Su'ud, Zaki

    2012-06-01

    Some interesting issues are attributed to nuclide compositions of spent fuels from thermal reactors as well as fast reactors such as a potential to reuse as recycled fuel, and a possible capability to be manage as a fuel for destructive devices. In addition, analysis on nuclear forensics which is related to spent fuel compositions becomes one of the interesting topics to evaluate the origin and the composition of spent fuels from the spent fuel foot-prints. Spent fuel compositions of different fuel types give some typical spent fuel foot prints and can be estimated the origin of source of those spent fuel compositions. Some technics or methods have been developing based on some science and technological capability including experimental and modeling or theoretical aspects of analyses. Some foot-print of nuclear forensics will identify the typical information of spent fuel compositions such as enrichment information, burnup or irradiation time, reactor types as well as the cooling time which is related to the age of spent fuels. This paper intends to evaluate the typical spent fuel compositions of light water (LWR) and fast breeder reactors (FBR) from the view point of some foot prints of nuclear forensics. An established depletion code of ORIGEN is adopted to analyze LWR spent fuel (SF) for several burnup constants and decay times. For analyzing some spent fuel compositions of FBR, some coupling codes such as SLAROM code, JOINT and CITATION codes including JFS-3-J-3.2R as nuclear data library have been adopted. Enriched U-235 fuel composition of oxide type is used for fresh fuel of LWR and a mixed oxide fuel (MOX) for FBR fresh fuel. Those MOX fuels of FBR come from the spent fuels of LWR. Some typical spent fuels from both LWR and FBR will be compared to distinguish some typical foot-prints of SF based on nuclear forensic analysis.

  20. Comparative analysis of LWR and FBR spent fuels for nuclear forensics evaluation

    SciTech Connect

    Permana, Sidik; Suzuki, Mitsutoshi; Su'ud, Zaki

    2012-06-06

    Some interesting issues are attributed to nuclide compositions of spent fuels from thermal reactors as well as fast reactors such as a potential to reuse as recycled fuel, and a possible capability to be manage as a fuel for destructive devices. In addition, analysis on nuclear forensics which is related to spent fuel compositions becomes one of the interesting topics to evaluate the origin and the composition of spent fuels from the spent fuel foot-prints. Spent fuel compositions of different fuel types give some typical spent fuel foot prints and can be estimated the origin of source of those spent fuel compositions. Some technics or methods have been developing based on some science and technological capability including experimental and modeling or theoretical aspects of analyses. Some foot-print of nuclear forensics will identify the typical information of spent fuel compositions such as enrichment information, burnup or irradiation time, reactor types as well as the cooling time which is related to the age of spent fuels. This paper intends to evaluate the typical spent fuel compositions of light water (LWR) and fast breeder reactors (FBR) from the view point of some foot prints of nuclear forensics. An established depletion code of ORIGEN is adopted to analyze LWR spent fuel (SF) for several burnup constants and decay times. For analyzing some spent fuel compositions of FBR, some coupling codes such as SLAROM code, JOINT and CITATION codes including JFS-3-J-3.2R as nuclear data library have been adopted. Enriched U-235 fuel composition of oxide type is used for fresh fuel of LWR and a mixed oxide fuel (MOX) for FBR fresh fuel. Those MOX fuels of FBR come from the spent fuels of LWR. Some typical spent fuels from both LWR and FBR will be compared to distinguish some typical foot-prints of SF based on nuclear forensic analysis.

  1. Semiannual report, 1 April - 30 September 1991

    NASA Technical Reports Server (NTRS)

    1991-01-01

    The major categories of the current Institute for Computer Applications in Science and Engineering (ICASE) research program are: (1) numerical methods, with particular emphasis on the development and analysis of basic numerical algorithms; (2) control and parameter identification problems, with emphasis on effective numerical methods; (3) computational problems in engineering and the physical sciences, particularly fluid dynamics, acoustics, and structural analysis; and (4) computer systems and software for parallel computers. Research in these areas is discussed.

  2. Semiannual report to Congress, October 1, 1994--March 31, 1995

    SciTech Connect

    1995-04-01

    The Office of Inspector General Semiannual Report to the Congress covers the period October 1, 1994, through March 31, 1995. The report summarizes significant audit, inspection and investigative accomplishments for the reporting period, a large number of which facilitated Department management`s efforts to improve management controls and ensure efficient and effective operation. Narratives of the most significant reports are grouped by six primary performance measures: (1) Recommendations accepted by management, (2) Audit/inspection savings, recoveries, and funds identified for better use, (3) Legislative/regulatory compliance to recommendations, (4) Positive impacts on the Department after implementation of recommendations, (5) Complaints resolved, and (6) Investigation recoveries, fines, and funds identified for better use.

  3. MODIS Science Team Member Semi-annual Report

    NASA Technical Reports Server (NTRS)

    Vermote, Eric; ElSaleous, Nazmi; Fisher, Paul; Karakos, Damianos; Ray, James; Vermeulen, Anne

    1998-01-01

    This paper presents a semi-annual report of the MODerate resolution imaging Spectroradiometer (MODIS) Science Team Members. The most important activities undertaken during this reporting period are the following: 1) Versions 2.1 and 2.2 surface reflectance L2/L3 DAAC/SDST delivery; 2) Version 2.0 1km and 250m VI product delivery (assist Arizona); 3) Version 2.1 surface reflectance L2 testing; 4) Land Synthetic data set generator improvements; 5) QA; 6) Surface reflectance error budget generation (SWAMP request); 7) SCF Hardware; 8) Aerosol transport modeling; 9) Aerosol optical depth retrieval from AVHRR data; 10) Aerosol characteristics retrieval from SeaWIFS/AVHRR fusioned data; 11) Validation activities; 12) Aerosol climatology; and 13) 6S code. The report includes summaries of the topics above.

  4. Semiannual variation of the geomagnetic activity and solar wind parameters

    NASA Astrophysics Data System (ADS)

    Orlando, M.; Moreno, G.; Parisi, M.; Storini, M.

    1993-10-01

    The semiannual variation of the geomagnetic activity is investigated in connection with a large set of solar wind and interplanetary magnetic field data (4494 daily averages from 1965 to 1987). Our analysis confirms that the geomagnetic activity (described by the aa index), is mainly modulated by the southward component of the magnetic field (BS), as suggested by Russell and McPherron. On the other hand, it is also found that the solar wind velocity (V) has a relevant role in this phenomenon. In fact, the amplitude of the aa modulation is best correlated with the function BSV2. We also explore the linkage between the annual trend of aa and the sunspot activity (1868-1989), showing that the modulation of the geomagnetic activity follows a more regular pattern during the descending phase of the solar cycle than during the rising and maximum parts.

  5. Methods for environmental monitoring of DOE waste disposal and storage sites: Proposal for optimizing a biological treatment system for denitrification of Y-12 waste streams. Semiannual progress report, November 1, 1987--March 31, 1988

    SciTech Connect

    Hicks, G.M.; Revis, N.

    1988-12-31

    The denitrification process at Y-12 involves the use of sludge to denitrify aqueous plating waste containing relatively high levels of NO{sub 3}. The process from time to time does not denitrify. The factors associated with the failure of the process remains to be resolved. The authors propose to resolve those factors by taking the following research approaches: (1) isolation and identification of microorganisms originating from sewage sludge which are associated with denitrification; (2) define physiological factors required for denitrification in this process system; and (3) define toxic factors associated with the aqueous waste that may affect the process of denitrification.

  6. 49 CFR Appendix B to Part 40 - DOT Drug Testing Semi-Annual Laboratory Report to Employers

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 1 2012-10-01 2012-10-01 false DOT Drug Testing Semi-Annual Laboratory Report to Employers B Appendix B to Part 40 Transportation Office of the Secretary of Transportation PROCEDURES FOR TRANSPORTATION WORKPLACE DRUG AND ALCOHOL TESTING PROGRAMS Pt. 40, App. B Appendix B to Part 40—DOT Drug Testing Semi-Annual Laboratory...

  7. 49 CFR Appendix C to Part 40 - DOT Drug Testing Semi-Annual Laboratory Report to DOT

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... Semi-Annual Laboratory Report to DOT Mail, fax, or e-mail to: U.S. Department of Transportation, Office of Drug and Alcohol Policy and Compliance, W62-300, 1200 New Jersey Avenue, SE., Washington, DC 20590... 49 Transportation 1 2012-10-01 2012-10-01 false DOT Drug Testing Semi-Annual Laboratory Report...

  8. 49 CFR Appendix C to Part 40 - DOT Drug Testing Semi-Annual Laboratory Report to DOT

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... Semi-Annual Laboratory Report to DOT Mail, fax, or e-mail to: U.S. Department of Transportation, Office of Drug and Alcohol Policy and Compliance, W62-300, 1200 New Jersey Avenue, SE., Washington, DC 20590... 49 Transportation 1 2014-10-01 2014-10-01 false DOT Drug Testing Semi-Annual Laboratory Report...

  9. 49 CFR Appendix C to Part 40 - DOT Drug Testing Semi-Annual Laboratory Report to DOT

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... Semi-Annual Laboratory Report to DOT Mail, fax, or e-mail to: U.S. Department of Transportation, Office of Drug and Alcohol Policy and Compliance, W62-300, 1200 New Jersey Avenue, SE., Washington, DC 20590... 49 Transportation 1 2011-10-01 2011-10-01 false DOT Drug Testing Semi-Annual Laboratory Report...

  10. 49 CFR Appendix C to Part 40 - DOT Drug Testing Semi-Annual Laboratory Report to DOT

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... Semi-Annual Laboratory Report to DOT Mail, fax, or e-mail to: U.S. Department of Transportation, Office of Drug and Alcohol Policy and Compliance, W62-300, 1200 New Jersey Avenue, SE., Washington, DC 20590... 49 Transportation 1 2013-10-01 2013-10-01 false DOT Drug Testing Semi-Annual Laboratory Report...

  11. 49 CFR Appendix C to Part 40 - DOT Drug Testing Semi-Annual Laboratory Report to DOT

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... Semi-Annual Laboratory Report to DOT Mail, fax, or e-mail to: U.S. Department of Transportation, Office of Drug and Alcohol Policy and Compliance, W62-300, 1200 New Jersey Avenue, SE., Washington, DC 20590... 49 Transportation 1 2010-10-01 2010-10-01 false DOT Drug Testing Semi-Annual Laboratory Report...

  12. A review of irradiation effects on LWR core internal materials - IASCC susceptibility and crack growth rates of austenitic stainless steels

    NASA Astrophysics Data System (ADS)

    Chopra, O. K.; Rao, A. S.

    2011-02-01

    Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of light water reactor (LWR) pressure vessels because of their relatively high strength, ductility, and fracture toughness. However, exposure to neutron irradiation for extended periods changes the microstructure (radiation hardening) and microchemistry (radiation-induced segregation) of these steels, and degrades their fracture properties. Irradiation-assisted stress corrosion cracking (IASCC) is another degradation process that affects LWR internal components exposed to neutron radiation. The existing data on irradiated austenitic SSs were reviewed to evaluate the effects of key parameters such as material composition, irradiation dose, and water chemistry on IASCC susceptibility and crack growth rates of these materials in LWR environments. The significance of microstructural and microchemistry changes in the material on IASCC susceptibility is also discussed. The results are used to determine (a) the threshold fluence for IASCC and (b) the disposition curves for cyclic and IASCC growth rates for irradiated SSs in LWR environments.

  13. Surface Gasification Materials Program. Semiannual progress report for the period ending March 31, 1985

    SciTech Connect

    Bradley, R.A.

    1985-06-01

    The objective of the Surface Gasification Materials Program is to conduct research and development on materials for application to the specific needs of coal gasification systems. One of the goals of the program is to evaluate innovative fabrication methods which have the potential to lower costs and improve reliability and safety for gasifier vessels and components. Another goal is to conduct engineering-scale development and application of materials for coal gasification systems to ensure that the materials of construction for pilot plants and future large-scale plants can be properly selected and specified. Contents of this semiannual progress report include: (1) corrosion studies of plant materials surveillance tests; (2) slagging gasifier refractories - application/evaluation; (3) protective coatings and claddings - application/evaluation; (4) corrosion of structural ceramics in coal gasification environments; (5) advanced pressure vessel materials technology; (6) electroslag component casting; (7) production and evaluation of electroslag castings; (8) cost reduction of electroslag casting manufacturing process; and (9) quantitative microstructural characterization of steel casting.

  14. Challenges in the development of high-fidelity LWR core neutronics tools

    SciTech Connect

    Smith, K.; Forget, B.

    2013-07-01

    Modern computing has made possible the solution of extremely large-scale reactor simulations, and the literature has numerous examples of high-resolution methods (often Monte Carlo) applied to full-core reactor problems. However, there are currently no examples in the literature of application of such 'High-Fidelity' or 'First Principles' methods to operating Light Water Reactor (LWR) analysis. This paper seeks to remind code developers, project managers, and analysts of the many important aspects of LWR simulation that must be incorporated to produce truly high-fidelity analysis tools. The authors offer a monetary prize to the first person (or group) that successfully solves a new two-cycle operational PWR depletion benchmark problem using high-fidelity tools and demonstrates acceptable accuracy by comparison with measured operational plant data (open source) provided to the reactor analysis community. (authors)

  15. Evaluation of methods for decladding LWR fuel for a pyroprocessing-based reprocessing plant

    SciTech Connect

    Bond, W.D.; Mailen, J.C.; Michaels, G.E.

    1992-10-01

    The first step in reprocessing disassembled light-water reactor (LWR) spent fuel is to separate the zirconium-based cladding from the UO[sub 2] fuel. A survey of decladding technologies has been performed to identify candidate decladding processes suitable for LWR fuel and compatible with downstream pyropr for separation of actinides and fission products. Technologies for the primary separation of Zircaloy cladding from oxide fuel and for secondary separations (in most cases, a further decontamination of the cladding) were reviewed. Because cutting of the fuel cladding is a necessary step in all flowsheet options, metal cutting technologies were also briefly evaluated. The assessment of decladding processes resulted in the identification of the three or four potentially attractive options that may warrant additional near-term evaluation. These options are summarized, and major strengths and issues of each option are discussed.

  16. Evaluation of methods for decladding LWR fuel for a pyroprocessing-based reprocessing plant

    SciTech Connect

    Bond, W.D.; Mailen, J.C.; Michaels, G.E.

    1992-10-01

    The first step in reprocessing disassembled light-water reactor (LWR) spent fuel is to separate the zirconium-based cladding from the UO{sub 2} fuel. A survey of decladding technologies has been performed to identify candidate decladding processes suitable for LWR fuel and compatible with downstream pyropr for separation of actinides and fission products. Technologies for the primary separation of Zircaloy cladding from oxide fuel and for secondary separations (in most cases, a further decontamination of the cladding) were reviewed. Because cutting of the fuel cladding is a necessary step in all flowsheet options, metal cutting technologies were also briefly evaluated. The assessment of decladding processes resulted in the identification of the three or four potentially attractive options that may warrant additional near-term evaluation. These options are summarized, and major strengths and issues of each option are discussed.

  17. Office of Inspector General semiannual report to Congress, April 1--September 30, 1998

    SciTech Connect

    1998-10-01

    This Semiannual Report to Congress covers the period April 1 to September 30, 1998. The report summarizes significant Office of Inspector General (OIG) audit, inspection, and investigative accomplishments for the reporting period.These OIG efforts facilitated Department of Energy (DOE) efforts to improve the overall management of its programs. The OIG has developed a Strategic Plan which sets out its overall goals and objectives. The Office`s significant accomplishments are grouped by the strategic goals against which the OIG measures its performance. Highlights are presented on the following items: prime contractor fees policy strengthening; low-level and low-level mixed waste management program improvement; hazardous waste training agreement cost $6 million more than necessary; controls over architect-engineering costs improvement; funds expended contrary to Congressional direction and internal budget execution guidelines; company mischarges costs on several federal contracts; year 2000 computer issues; Qui Tam investigations; task force investigations; financial assistance grantees; DOE suspect/counterfeit items information trending and analysis; and management information systems.

  18. Draft report: a selection methodology for LWR safety R and D programs and proposals

    SciTech Connect

    Husseiny, A. A.; Ritzman, R. L.

    1980-03-01

    The results of work done to develop a methodology for selecting LWR safety R and D programs and proposals is described. A critical survey of relevant decision analysis methods is provided including the specifics of multiattribute utility theory. This latter method forms the basis of the developed selection methodology. Details of the methodology and its use are provided along with a sample illustration of its application.

  19. Effects of LWR coolant environments on fatigue lives of austenitic stainless steels

    SciTech Connect

    Chopra, O.K.; Gavenda, D.J.

    1997-07-01

    The ASME Boiler and Pressure Vessel Code fatigue design curves for structural materials do not explicitly address the effects of reactor coolant environments on fatigue life. Recent test data indicate a significant decrease in fatigue life of pressure vessel and piping materials in light water reactor (LWR) environments. Fatigue tests have been conducted on Types 304 and 316NG stainless steel in air and LWR environments to evaluate the effects of various material and loading variables, e.g., steel type, strain rate, dissolved oxygen (DO) in water, and strain range, on fatigue lives of these steels. The results confirm the significant decrease in fatigue life in water. The environmentally assisted decrease in fatigue life depends both on strain rate and DO content in water. A decrease in strain rate from 0.4 to 0.004%/s decreases fatigue life by a factor of {approx} 8. However, unlike carbon and low-alloy steels, environmental effects are more pronounced in low-DO than in high-DO water. At {approx} 0.004%/s strain rate, reduction in fatigue life in water containing <10 ppb D is greater by a factor of {approx} 2 than in water containing {ge} 200 ppb DO. Experimental results have been compared with estimates of fatigue life based on the statistical model. The formation and growth of fatigue cracks in austenitic stainless steels in air and LWR environments are discussed.

  20. Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments.

    SciTech Connect

    Chopra, O. K.; Energy Technology

    2002-08-01

    The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the Code specify fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of fatigue crack initiation in austenitic stainless steels in LWR coolant environments. The existing fatigue {var_epsilon}-N data have been evaluated to establish the effects of key material, loading, and environmental parameters (such as steel type, strain range, strain rate, temperature, dissolved-oxygen level in water, and flow rate) on the fatigue lives of these steels. Statistical models are presented for estimating the fatigue {var_epsilon}-N curves for austenitic stainless steels as a function of the material, loading, and environmental parameters. Two methods for incorporating environmental effects into the ASME Code fatigue evaluations are presented. The influence of reactor environments on the mechanism of fatigue crack initiation in these steels is also discussed.

  1. Annual and Semi-Annual Temperature Oscillations in the Upper Mesosphere

    NASA Technical Reports Server (NTRS)

    Niciejewski, R. J.; Killeen, T. L.

    1995-01-01

    Fourier transform spectrometer observations of the mesosphere have been performed at the University of Michigan (latitude: 42.5 N) on a long term basis. A database of near infrared Meinel hydroxyl spectra has been accumulated from which rotational temperatures have been determined. Harmonic analysis of one-day averaged temperatures for the period 1992.0 to 1994.5 has shown a distinct annual and semi-annual variation. Subsequent fitting of a five term periodic function characterizing the annual and semi-annual temperature oscillations to the daily averaged temperatures was performed. The resultant mean temperature and the amplitudes and phases of the annual and semi-annual variations are shown to coincide with an emission height slightly above 85 km which is consistent with the mean rocket derived altitude for peak nocturnal hydroxyl emission.

  2. LWR design decision methodology: Phase II. Final report

    SciTech Connect

    1981-01-01

    Techniques were identified to augment existing design process at the component and system level in order to optimize cost and safety between alternative system designs. The method was demonstrated using the Surry Low Pressure Injection System (LPIS). Three possible backfit options were analyzed for the Surry LPIS, assessing the safety level of each option and estimating the acquisition and installation costs for each. (DLC)

  3. Evaluation of methods for noise-free measurement of LER/LWR using synthesized CD-SEM images

    NASA Astrophysics Data System (ADS)

    Constantoudis, Vassilios; Pargon, Erwine

    2013-04-01

    The aim of this paper is to contribute to the understanding of the effects of noise on LER/LWR parameters when they are measured through the analysis of top-down CD-SEM images. To this end, first we present a methodology for the generation of synthesized CD-SEM images including resist lines with predetermined CD/pitch and LER/LWR parameters in which the noise level can be tuned at will. The sources of noise can be the shot noise of SEM electron beam (Poisson-type) and the microscope electronics (Gaussian-type). Then we use the generated CD-SEM images to evaluate three methods devised for the reduction of noise effects and the extraction of noise-free LER/LWR parameters. The first method (called fractal method) is presented for first time while the next two (model filtering and Power Spectral Density) have been already proposed and applied in literature. We compare the output of each method with the noise-less LER/LWR parameters for various noise levels, number of images and LER/LWR initial parameters and discuss their advantages and limitations.

  4. 31 CFR Appendix B to Part 359 - Composite Semiannual Rate Period Table

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Composite Semiannual Rate Period Table B Appendix B to Part 359 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) FISCAL SERVICE, DEPARTMENT OF THE TREASURY BUREAU OF THE PUBLIC DEBT OFFERING OF UNITED STATES SAVINGS BONDS, SERIES I Pt. 359, App....

  5. Annual and semiannual variations of thermospheric density: EOF analysis of CHAMP and GRACE data

    NASA Astrophysics Data System (ADS)

    Lei, Jiuhou; Matsuo, Tomoko; Dou, Xiankang; Sutton, Eric; Luan, Xiaoli

    2012-01-01

    In this paper, observations from CHAMP and GRACE during 2002-2010 are used to study the seasonal variations of thermospheric density by characterizing the dominant modes of thermospheric density variability as empirical orthogonal functions (EOFs). Our results showed that the first three EOFs captured most of the density variability, which can be as large as 98% of total density variability. Subsequently, the obtained mean field, first three EOFs and the corresponding amplitudes of three EOFs are applied to construct a thermospheric density model at 400 km to study seasonal variations of thermospheric density under geomagnetically quiet conditions. Thermospheric density shows strong latitudinal dependence in seasonal variation, although it usually has maxima near the equinoxes and minimum in the local winter at middle and high latitudes. Semiannual variations imbedded in the annual variations are seen at all latitudes; annual variations however become dominant in the southern hemisphere. Specifically, the observations show that the annual amplitude can reach as large as 40-50% of the annual mean at high latitudes in the southern hemisphere and it decreases gradually from the southern to northern hemisphere. The semiannual component to the annual mean is about 15-20% without significant latitudinal dependence. Additionally, the relative amplitudes of annual and semiannual variations in the MSISE00 density agree fairly well with the observations, albeit the MSISE00 gives an opposite solar activity dependence for the annual and semiannual variations compared with the positive F107 dependence seen in the observations.

  6. Fusion materials semiannual progress report for period ending December 31, 1999

    SciTech Connect

    Burn, G.

    2000-03-01

    This is the twenty-seventh in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components.

  7. 75 FR 41878 - Semi-Annual Labor Standards Enforcement Report-Local Contracting Agencies (HUD Programs)

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-19

    ... URBAN DEVELOPMENT Semi-Annual Labor Standards Enforcement Report--Local Contracting Agencies (HUD... Development, 451 Seventh Street, SW., Washington, DC 20410; e-mail Leroy McKinney Jr. at Leroy.McKinneyJr@hud... public that the Department of Housing and Urban Development has submitted to OMB a request for...

  8. Low-rank coal research semiannual report, January 1992--June 1992

    SciTech Connect

    Not Available

    1992-12-31

    This semiannual report is a compilation of seventeen reports on ongoing coal research at the University of North Dakota. The following research areas are covered: control technology and coal preparation; advanced research and technology development; combustion; liquefaction and gasification. Individual papers have been processed separately for inclusion in the Energy Science and Technology Database.

  9. Inspector General's Semiannual Report to Congress, No. 55. April 1, 2007-September 30, 2007

    ERIC Educational Resources Information Center

    US Department of Education, 2007

    2007-01-01

    This semiannual report to Congress on the activities and accomplishments of the Office of Inspector General (OIG), U.S. Department of Education (Department) from April 1, 2007, through September 30, 2007, highlights the audits, inspections, investigations, and other activities to illustrate an ongoing commitment to promoting accountability,…

  10. 76 FR 54829 - The First Semi-Annual Aviation Workforce Management Conference

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-02

    ...The Department of Transportation, Office of the Secretary of Transportation, announces the First Semi-Annual Aviation Workforce Management Conference which will be held in Washington DC. The Conference will be co-hosted by the Secretary of Transportation Ray LaHood, Secretary of Labor Hilda L. Solis and Secretary of Education Arne Duncan. The Federal Aviation Administrator J. Randolph (Randy)......

  11. Unconventional gas recovery program. Semi-annual report for the period ending September 30, 1979

    SciTech Connect

    Manilla, R.D.

    1980-04-01

    This document is the third semi-annual report describing the technical progress of the US DOE projects directed at gas recovery from unconventional sources. Currently the program includes Methane Recovery from Coalbeds Project, Eastern Gas Shales Project, Western Gas Sands Project, and Geopressured Aquifers Project.

  12. Semi-Annual Report to Congress: April 1, 1980-September 30, 1980.

    ERIC Educational Resources Information Center

    Office of Inspector General (ED), Washington, DC.

    EStablished in 1980 to help improve management effectiveness, the U.S. Department of Education's Office of Inspector General (OIG) is responsible for audit, investigative, fraud detection and prevention, and some security services for the Department. In this document--its first semi-annual report--the OIG first describes its organizational…

  13. NRC regulatory agenda: Semiannual report, July--December 1996. Volume 15, Number 2

    SciTech Connect

    1997-03-01

    The NRC Regulatory Agenda is a compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and all petitions for rulemaking which have been received by the Commission and are pending disposition by the Commission. The Regulatory Agenda is updated and issued semiannually.

  14. Theoretical model for the latitude dependence of the thermospheric annual and semiannual variations

    NASA Technical Reports Server (NTRS)

    Mayr, H. G.; Volland, H.

    1972-01-01

    A three-dimensional model for the annual and semiannual variations of the thermosphere is presented in which energy and diffusive mass transport associated with the global circulation are considered in a self-consistent form. It is shown that these processes play a major role in the thermosphere dynamics and account for a number of temperature and compositional phenomena.

  15. 31 CFR 359.11 - What is the semiannual inflation rate?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...? 359.11 Section 359.11 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued... BONDS, SERIES I General Information § 359.11 What is the semiannual inflation rate? The index used to... from the preceding March 2002 and September 2001. The rate of change over the six-month period, if...

  16. 31 CFR 359.11 - What is the semiannual inflation rate?

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ...? 359.11 Section 359.11 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued... BONDS, SERIES I General Information § 359.11 What is the semiannual inflation rate? The index used to... from the preceding March 2002 and September 2001. The rate of change over the six-month period, if...

  17. 31 CFR 359.11 - What is the semiannual inflation rate?

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 31 Money and Finance:Treasury 2 2013-07-01 2013-07-01 false What is the semiannual inflation rate? 359.11 Section 359.11 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) FISCAL SERVICE, DEPARTMENT OF THE TREASURY BUREAU OF THE PUBLIC DEBT OFFERING OF UNITED STATES SAVINGS BONDS, SERIES I General Information...

  18. Semiannual report to Congress, October 1, 1995--March 31, 1996

    SciTech Connect

    1996-04-01

    This Office of Inspector General Semiannual Report to the Congress covers the period from October 1, 1995, through March 31, 1996. The report summarizes significant audit, inspection, and investigative accomplishments for the reporting period, a large portion of which facilitated Department of Energy management efforts to improve management controls and ensure efficient and effective operation of its programs. A major accomplishment during this period was the completion of financial statement audits for Fiscal Year 1995. Annual financial statement audits are mandated by the Chief Financial Officers Act of 1990. Narratives of our most significant reports are grouped by measures which the Office of Inspector General uses to gauge its performance. The common thread that ties the performance measures together is their emphasis on supporting Department efforts to produce high quality products at the lowest possible cost to the taxpayer. During this reporting period, the Office of Inspector General issued 67 audit and 15 inspection reports. For reports issued during the period, the Office of Inspector General made audit recommendations that, when implemented by management, could result in $134.6 million being put to better use. Management committed to taking corrective actions which the Office of Inspector General estimates will result in a more efficient use of funds totaling $333.2 million. Office of Inspector General investigations led to 6 criminal convictions and 1 pretrial diversion, as well as criminal and civil prosecutions which resulted in fines and recoveries of $10,942,714. The Office of Inspector General also provided 33 investigative referrals to management for recommended positive action.

  19. Optimization of accelerator-driven technology for LWR waste transmutation

    SciTech Connect

    Bowman, C.D.

    1996-12-31

    The role of accelerator-driven transmutation technology is examined in the context of the destruction of actinide waste from commercial light water reactors. It is pointed out that the commercial plutonium is much easier to use for entry-level nuclear weapons than weapons plutonium. Since commercial plutonium is easier to use, since there is very much more of it already, and since it is growing rapidly, the permanent disposition of commercial plutonium is an issue of greater importance than weapons plutonium. The minor actinides inventory, which may be influenced by transmutation, is compared in terms of nuclear properties with commercial and weapons plutonium and for possible utility as weapons material. Fast and thermal spectrum systems are compared as means for destruction of plutonium and the minor actinides. it is shown that the equilibrium fast spectrum actinide inventory is about 100 times larger than for thermal spectrum systems, and that there is about 100 times more weapons-usable material in the fast spectrum system inventory compared to the thermal spectrum system. Finally it is shown that the accelerator size for transmutation can be substantially reduced by design which uses the accelerator-produced neutrons only to initiate the unsustained fission chains characteristic of the subcritical system. The analysis argues for devoting primary attention to the development of thermal spectrum transmutation technology. A thermal spectrum transmuter operating at a fission power of 750-MWth fission power, which is sufficient to destroy the actinide waste from one 3,000-MWth light water reactor, may be driven by a proton beam of 1 GeV energy and a current of 7 mA. This accelerator is within the range of realizable cyclotron technology and is also near the size contemplated for the next generation spallation neutron source under consideration by the US, Europe, and Japan.

  20. 76 FR 37121 - Medicare Program; Second Semi-Annual Meeting of the Advisory Panel on Ambulatory Payment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-24

    ... the Advisory Panel on Ambulatory Payment Classification Groups--August 10, 2011 Through August 12...: Notice. SUMMARY: This notice announces the second semi-annual meeting of the Advisory Panel on Ambulatory... at:...

  1. Prioritization of tasks in the draft LWR safety technology program plan. Final report

    SciTech Connect

    Lim, E. Y.; Miller, W. J.; Parkinson, W. J.; Ritzman, R. L.; vonHerrmann, J. L.; Wood, P. J.

    1980-05-01

    The purpose of this report is to describe both the approach taken and the results produced in the SAI effort to prioritize the tasks in the Sandia draft LWR Safety Technology Program Plan. This work used the description of important safety issues developed in the Reactor Safety Study (2) to quantify the effect of safety improvements resulting from a research and development program on the risk from nuclear power plants. Costs of implementation of these safety improvements were also estimated to allow a presentation of the final results in a value (i.e., risk reduction) vs. impact (i.e., implementation costs) matrix.

  2. Characterization and chemistry of fission products released from LWR fuel under accident conditions

    SciTech Connect

    Norwood, K.S.; Collins, J.L.; Osborne, M.F.; Lorenz, R.A.; Wichner, R.P.

    1984-01-01

    Segments from commercial LWR fuel rods have been tested at temperatures between 1400 and 2000/sup 0/C in a flowing steam-helium atmosphere to simulate severe accident conditions. The primary goals of the tests were to determine the rate of fission product release and to characterize the chemical behavior. This paper is concerned primarily with the identification and chemical behavior of the released fission products with emphasis on antimony, cesium, iodine, and silver. The iodine appeared to behave primarily as cesium iodide and the antimony and silver as elements, while cesium behavior was much more complex. 17 refs., 7 figs., 1 tab.

  3. Aging management of major LWR components with nondestructive evaluation

    SciTech Connect

    Shah, V.N.; MacDonald, P.E.; Akers, D.W.; Sellers, C.; Murty, K.L.; Miraglia, P.Q.; Mathew, M.D.; Haggag, F.M.

    1997-12-31

    Nondestructive evaluation of material damage can contribute to continued safe, reliable, and economical operation of nuclear power plants through their current and renewed license period. The aging mechanisms active in the major light water reactor components are radiation embrittlement, thermal aging, stress corrosion cracking, flow-accelerated corrosion, and fatigue, which reduce fracture toughness, structural strength, or fatigue resistance of the components and challenge structural integrity of the pressure boundary. This paper reviews four nondestructive evaluation methods with the potential for in situ assessment of damage caused by these mechanisms: stress-strain microprobe for determining mechanical properties of reactor pressure vessel and cast stainless materials, magnetic methods for estimating thermal aging damage in cast stainless steel, positron annihilation measurements for estimating early fatigue damage in reactor coolant system piping, and ultrasonic guided wave technique for detecting cracks and wall thinning in tubes and pipes and corrosion damage to embedded portion of metal containments.

  4. Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code

    NASA Astrophysics Data System (ADS)

    Collin, Blaise P.

    2014-08-01

    The Idaho National Laboratory (INL) PARFUME (PARticle FUel ModEl) code was used to assess the overall fuel performance of uranium nitride (UN) tristructural isotropic (TRISO) ceramic fuel under irradiation conditions typical of a Light Water Reactor (LWR). The dimensional changes of the fuel particle layers and kernel were calculated, including the formation of an internal gap. The survivability of the UN TRISO particle was estimated depending on the strain behavior of the constituent materials at high fast fluence and burn-up. For nominal cases, internal gas pressure and representative thermal profiles across the kernel and layers were determined along with stress levels in the inner and outer pyrolytic carbon (IPyC/OPyC) and silicon carbide (SiC) layers. These parameters were then used to evaluate fuel particle failure probabilities. Results of the study show that the survivability of UN TRISO fuel under LWR irradiation conditions might only be guaranteed if the kernel and PyC swelling rates are limited at high fast fluence and burn-up. These material properties have large uncertainties at the irradiation levels expected to be reached by UN TRISO fuel in LWRs. Therefore, a large experimental effort would be needed to establish material properties, including kernel and PyC swelling rates, under these conditions before definitive conclusions can be drawn on the behavior of UN TRISO fuel in LWRs.

  5. Application of the Reactor Analysis Support Package LWR set-point analysis guidelines

    SciTech Connect

    Engel, R.E.; Sorensen, J.M.; May, R.S.; Doran, K.J.; Trikouros, N.G.; Mozzias, E.S.

    1989-07-01

    Frequently, a situation is encountered in which the technical specification setpoints established by the plant safety analysis are judged to be unacceptable from a plant operational standpoint. This report documents the application of the Electric Power Research Institute (EPRI) Reactor Analysis Support Package (RASP) Light Water Reactor (LWR) setpoint analysis guidelines to provide justification for relaxing the high pressure setpoints at the Oyster Creek Nuclear Generation Station. More Specifically, the plant operation's staff determined that it was desirable to provide increased margin for measurement uncertainties in the high pressure instrument and safety valve setpoints. Previous experience had indicated that there was insufficient margin to justify the desired setpoints using conventional deterministic inputs to the safety analysis and plant performance evaluation process. Therefore, it was determined that the RASP LWR setpoint analysis guidelines, which incorporated the use of a statistical combination of uncertainties methodology, would be used to establish an acceptable set of high pressure setpoints. This report documents the results of applying the RASP setpoint analysis guidelines to provide justification for an acceptable set of high pressure setpoints for the Oyster Creek station. 14 refs., 53 figs., 28 tabs.

  6. Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels

    SciTech Connect

    Chopra, O.K.; Shack, W.J.

    1998-03-01

    The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the code specify fatigue design curves for structural materials. While effects of reactor coolant environments are not explicitly addressed by the design curves, test data indicate that the Code fatigue curves may not always be adequate in coolant environments. This report summarizes work performed by Argonne National Laboratory on fatigue of carbon and low-alloy steels in light water reactor (LWR) environments. The existing fatigue S-N data have been evaluated to establish the effects of various material and loading variables such as steel type, dissolved oxygen level, strain range, strain rate, temperature, orientation, and sulfur content on the fatigue life of these steels. Statistical models have been developed for estimating the fatigue S-N curves as a function of material, loading, and environmental variables. The results have been used to estimate the probability of fatigue cracking of reactor components. The different methods for incorporating the effects of LWR coolant environments on the ASME Code fatigue design curves are presented.

  7. Feasibility of Water Cooled Thorium Breeder Reactor Based on LWR Technology

    SciTech Connect

    Takaki, Naoyuki; Permana, Sidik; Sekimoto, Hiroshi

    2007-07-01

    The feasibility of Th-{sup 233}U fueled, homogenous breeder reactor based on matured conventional LWR technology was studied. The famous demonstration at Shipping-port showed that the Th-{sup 233}U fueled, heterogeneous PWR with four different lattice fuels was possible to breed fissile but its low averaged burn-up including blanket fuel and the complicated core configuration were not suitable for economically competitive reactor. The authors investigated the wide design range in terms of fuel cell design, power density, averaged discharge burn-up, etc. to determine the potential of water-cooled Th reactor as a competitive breeder. It is found that a low moderated (MFR=0.3) H{sub 2}O-cooled reactor with comparable burn-up with current LWR is feasible to breed fissile fuel but the core size is too large to be economical because of the low pellet power density. On the other hand, D{sub 2}O-cooled reactor shows relatively wider feasible design window, therefore it is possible to design a core having better neutronic and economic performance than H{sub 2}O-cooled. Both coolant-type cores show negative void reactivity coefficient while achieving breeding capability which is a distinguished characteristics of thorium based fuel breeder reactor. (authors)

  8. Compatibility/Stability Issues in the Use of Nitride Kernels in LWR TRISO Fuel

    SciTech Connect

    Armstrong, Beth L; Besmann, Theodore M

    2012-02-01

    The stability of the SiC layer in the presence of free nitrogen will be dependent upon the operating temperatures and resulting nitrogen pressures whether it is at High Temperature Gas-Cooled Reactor (HTGR) temperatures of 1000-1400 C (coolant design dependent) or LWR temperatures that range from 500-700 C. Although nitrogen released in fissioning will form fission product nitrides, there will remain an overpressure of nitrogen of some magnitude. The nitrogen can be speculated to transport through the inner pyrolytic carbon layer and contact the SiC layer. The SiC layer may be envisioned to fail due to resulting nitridation at the elevated temperatures. However, it is believed that these issues are particularly avoided in the LWR application. Lower temperatures will result in significantly lower nitrogen pressures. Lower temperatures will also substantially reduce nitrogen diffusion rates through the layers and nitriding kinetics. Kinetics calculations were performed using an expression for nitriding silicon. In order to further address these concerns, experiments were run with surrogate fuel particles under simulated operating conditions to determine the resulting phase formation at 700 and 1400 C.

  9. Modeling and Analysis of UN TRISO Fuel for LWR Application Using the PARFUME Code

    SciTech Connect

    Blaise Collin

    2014-08-01

    The Idaho National Laboraroty (INL) PARFUME (particle fuel model) code was used to assess the overall fuel performance of uranium nitride (UN) tristructural isotropic (TRISO) ceramic fuel under irradiation conditions typical of a Light Water Reactor (LWR). The dimensional changes of the fuel particle layers and kernel were calculated, including the formation of an internal gap. The survivability of the UN TRISO particle was estimated depending on the strain behavior of the constituent materials at high fast fluence and burn up. For nominal cases, internal gas pressure and representative thermal profiles across the kernel and layers were determined along with stress levels in the inner and outer pyrolytic carbon (IPyC/OPyC) and silicon carbide (SiC) layers. These parameters were then used to evaluate fuel particle failure probabilities. Results of the study show that the survivability of UN TRISO fuel under LWR irradiation conditions might only be guaranteed if the kernel and PyC swelling rates are limited at high fast fluence and burn up. These material properties have large uncertainties at the irradiation levels expected to be reached by UN TRISO fuel in LWRs. Therefore, a large experimental effort would be needed to establish material properties, including kernel and PyC swelling rates, under these conditions before definitive conclusions can be drawn on the behavior of UN TRISO fuel in LWRs.

  10. The stratopause semiannual oscillation in the NCAR Community Climate Model

    NASA Technical Reports Server (NTRS)

    Sassi, Fabrizio; Garcia, Roland R.; Boville, Byron A.

    1993-01-01

    The middle atmospheric version of the NCAR Community Climate Model (CCM2) has been used to study the development of the equatorial semiannual oscillation (SAO) in the stratosphere. The model domain extends from the ground to about 80 km, with a vertical resolution of 1 km. Transport of nitrous oxide (N2O) with simplified photochemistry is included in the calculation to illustrate the influence of tropical circulations on the distribution of trace species. Diagnosis of model output reveals two distinct phases in the evolution of the zonal mean state on the equator. In early December, a strong and broad easterly jet appears near the stratopause in connection with a midlatitude wave event (sudden stratospheric warming) that reverses the winter westerlies of the Northern Hemisphere throughout the upper stratosphere. When the wave forcing dies out, the radiative drive allows the westerlies to recover at midlatitudes, while easterlies persist in the tropics. The resulting strong meridional gradient of the zonal mean wind provides favorable conditions for the development of inertial instability at lower latitudes. The meridional circulation associated with the instability shapes the 'nose' of the easterly jet, reducing the extension of the unstable region. In equinoctial conditions, a jet of westerlies appears in the lower equatorial mesosphere and descends to lower altitudes; positive accelerations associated with the descending westerlies are due primarily to Kelvin waves. The descent of the westerly jet does not reproduce well the observed behavior of the SAO westerly phase, either in amplitude or in the extent of downward propagation. As a consequence, the model does not simulate the 'double peak' observed in the tropical distribution of N2O. Comparison of wave amplitudes in the model with those derived from satellite observations shows that the calculated amplitudes are larger than observed in the upper stratosphere. It follows that inadequate Kelvin wave forcing is

  11. Office of Inspector General semiannual report to Congress, October 1, 1996--March 31, 1997

    SciTech Connect

    1997-04-01

    This Office of Inspector General Semiannual Report to the Congress covers the period from October 1, 1996, through March 31, 1997. The report summarizes significant audit, inspection, and investigative accomplishments for the reporting period which facilitated Department of Energy management efforts to improve management controls and ensure efficient and effective operation of its programs. Narratives of the most significant reports are grouped by measures which the Office of Inspector General uses to gauge its performance. The common thread that ties the performance measures together is their emphasis on supporting Department efforts to produce high quality products at the lowest possible cost to the taxpayer. Five such performance measures were used during this semiannual period to present outcomes of Office of Inspector General work in terms of improvements in Department programs and operations.

  12. Microstructure evolution in proton-irradiated austenitic Fe-Cr-Ni alloys under LWR core conditions

    NASA Astrophysics Data System (ADS)

    Gan, Jian

    1999-11-01

    Irradiation-induced microstructure of austenitic stainless steel was investigated using proton irradiation. High-purity alloys of Fe-20Cr-9Ni (UHP 304 SS), Fe-20Cr-24Ni and Ni-18Cr-9Fe were irradiated using 3.2 MeV protons at a dose rate of 7 × 10-6 dpa/s between 300°C and 600°C. The irradiation produced a microstructure consisting of dislocation loops and voids. The dose and temperature dependence of the number density and size of dislocation loops and voids were investigated. The changes in yield strength due to irradiation were estimated from Vickers hardness measurements and compared to calculations using a dispersed-barrier hardening model. The dose and temperature dependence of microstructure and hardness change for proton irradiation follows the same trend as that for neutron irradiation at comparable irradiation conditions. Commercial purity alloys of CP 304 SS and CP 316 SS were irradiated at 360°C to doses between 0.3 and 3.0 dpa. The irradiated microstructure consists of dislocation loops. No voids were detected at doses up to 3.0 dpa. Loop size distributions are in close agreement with that in the same alloys neutron-irradiated in a LWR core. The loop density also agrees with neutron irradiation data. The yield strength as a function of dose in proton irradiated commercial purity alloys is consistent with the neutron- data trend. A fast-reactor microstructure model was adapted for light water reactor (LWR) irradiation conditions (275°C, 7 × 10 -8 dpa/s) and then applied to proton irradiation under conditions (360°C, 7 × 10-6 dpa/s) relevant to LWRs. The original model was modified by including in-cascade interstitial clustering and the loss of interstitial clusters to sinks by cluster diffusion. It was demonstrated that loop nucleation for both LWR irradiation condition and proton irradiation are driven by in-cascade interstitial clustering. One important result from this modeling work is that the difference in displacement cascade between

  13. Semiannual Variation in the Number of Energetic Electron Precipitation Events Recorded in the Polar Atmosphere

    NASA Astrophysics Data System (ADS)

    Stozhkov, Y. Ivanovich; Makhmutov, V. S.; Bazilevskaya, G. A.; Krainev, M. B.; Svirkhevskaya, A. K.; Svirzhevsky, N. S.; Mailin, S. Y.

    2003-07-01

    The analysis of the monthly numbers of Electron Precipitation Events (EPEs) recorded at Olenya station (Murmansk region) during 1970-1987, shows the semiannual variation with two maxima centered on April and September. We analyse the interplanetary plasma and geomagnetic indices data sets associated with the EPEs recorded. The possible relationship of this variation and RusselMcPherron, Equino ctial and Axial effects is discussed.

  14. National Institute for Global Environmental Change. Semi-annual report, July 1, 1991--December 31, 1991

    SciTech Connect

    Werth, G.C.

    1992-04-01

    This document is the Semi-Annual Report of the National Institute for Global Environmental Change for the reporting period July 1 to December 31, 1991. The report is in two parts. Part I presents the mission of the Institute, examples of progress toward that mission, a brief description of the revised management plan, and the financial report. Part II presents the statements of the Regional Center Directors along with progress reports of the projects written by the researchers themselves.

  15. Annual and semiannual harmonics of wind in the Northern stratosphere, mesosphere, and lower thermosphere

    NASA Astrophysics Data System (ADS)

    Guryanov, Vladimir V.; Jacobi, Christoph; Eliseev, Alexey V.; Fahrutdinova, Antonina N.

    2015-11-01

    Based on the UK MetOffice gridded analysis in the altitudes from the tropopause to the mesopause of the Northern Hemisphere and the meteor radar observations in the mesosphere/lower thermosphere over Kazan (56 °N 49 °E) and Collm (51 °N 13 °E), the annual and semiannual harmonics of the horizontal wind components in the stratosphere, mesosphere, and lower thermosphere are studied for the period 2004-2013. The maxima of the amplitude of the annual harmonics of zonal wind are much more pronounced than the respective maxima for meridional wind. In contrast, the magnitudes of the maxima of the semiannual harmonics are comparable between zonal and meridional wind. The annual harmonics of horizontal wind in the studied layer typically reaches maximum in January-February. The semiannual harmonics of the components of horizontal wind in the stratosphere-lower thermosphere layer basically attains it first maximum in spring or in early summer. The results, included in the present paper, may be used for climate models validation.

  16. Surface Gasification Materials Program semiannual progress report for the period ending March 31, 1986. [Fe/sub 3/Al (iron aluminides)

    SciTech Connect

    Not Available

    1986-06-01

    The objective of the Surface Gasification Materials Program is to conduct research and development on materials for application to the specific needs of coal gasification systems. One of the goals of the program is to evaluate innovative fabrication methods which have the potential to lower costs and improve reliability and safety for gasifier vessels and components. Another goal is to conduct engineering-scale development and application of materials for coal gasification systems to ensure that the materials of construction for pilot plants and future large-scale plants can be properly selected and specified. Contents of this semiannual progress report include: (1) protective coatings and claddings - application/evaluation; (2) corrosion of structural ceramics in coal gasification environments; (3) electroslag component casting; and (4) development of iron aluminides. 8 figs., 14 tabs.

  17. Review of Technical Issues Related to Predicting Isotopic Compositions and Source Terms for High-Burnup LWR Fuel

    SciTech Connect

    Gauld, I. C.; Parks, C. V.

    2000-12-11

    This report has been prepared to review the technical issues important to the prediction of isotopic compositions and source terms for high-burnup, light-water-reactor (LWR) fuel as utilized in the licensing of spent fuel transport and storage systems. The current trend towards higher initial 235U enrichments, more complex assembly designs, and more efficient fuel management schemes has resulted in higher spent fuel burnups than seen in the past. This trend has led to a situation where high-burnup assemblies from operating LWRs now extend beyond the area where available experimental data can be used to validate the computational methods employed to calculate spent fuel inventories and source terms. This report provides a brief review of currently available validation data, including isotopic assays, decay heat measurements, and shielded dose-rate measurements. Potential new sources of experimental data available in the near term are identified. A review of the background issues important to isotopic predictions and some of the perceived technical challenges that high-burnup fuel presents to the current computational methods are discussed. Based on the review, the phenomena that need to be investigated further and the technical issues that require resolution are presented. The methods and data development that may be required to address the possible shortcomings of physics and depletion methods in the high-burnup and high-enrichment regime are also discussed. Finally, a sensitivity analysis methodology is presented. This methodology is currently being investigated at the Oak Ridge National Laboratory as a computational tool to better understand the changing relative significance of the underlying nuclear data in the different enrichment and burnup regimes and to identify the processes that are dominant in the high-burnup regime. The potential application of the sensitivity analysis methodology to help establish a range of applicability for experimental

  18. Nonlinear analysis of LWR components: areas of investigation/benefits/recommendations

    SciTech Connect

    Brown, S. J.

    1980-04-01

    The purpose of this study is to identify specific topics of investigation into design procedures, design concepts, methods of analysis, testing practices, and standards which are characterized by nonlinear behavior (both geometric and material) and which are considered to offer some economic and/or technical benefits to the LWR industry (excluding piping). In this study these topics were collected, compiled, and subjectively evaluated as to their potential benefit. The topics considered to have the greatest benefit/impact potential are discussed. The topics of investigation were found to fall basically into three areas: component, code interpretation, and load/failure mechanism. The topics are arbitrarily reorganized into six areas of investigation: Fracture, Fatigue, Vibration/Dynamic/Seismic, Plasticity, Component/Computational Considerations, and Code Interpretation.

  19. A Model for Assessment of Failure of LWR Fuel during an RIA

    SciTech Connect

    Liu, Wenfeng; Kazimi, Mujid S.

    2007-07-01

    This paper presents a model for Pellet-Cladding Mechanical Interaction (PCMI) failure of LWR fuel during an RIA. The model uses the J-integral as a driving parameter to characterize the failure potential during PCMI. The model is implemented in the FRAPTRAN code and is validated by CABRI and NSRR simulated RIA test data. Simulation of PWR and BWR conditions are conducted by FRAPTRAN to evaluate the fuel failure potential using this model. Model validation and simulation results are compared with the strain-based failure model of PNNL and the SED/CSED model of EPRI. Our fracture mechanics model has good capability to differentiate failure from non-failure cases. The results reveal significant effects of power pulse width: a wider pulse width generally increases the threshold for fuel failure. However, this effect is less obvious for highly corroded cladding. (authors)

  20. Information on the evolution of severe LWR fuel element damage obtained in the CORA program

    NASA Astrophysics Data System (ADS)

    Schanz, G.; Hagen, S.; Hofmann, P.; Schumacher, G.; Sepold, L.

    1992-06-01

    In the CORA program a series of out-of-pile experiments on LWR severe accidental situations is being performed, in which test bundles of LWR typical components and arrangements (PWR, BWR) are exposed to temperature transients up to about 2400°C under flowing steam. The individual features of the facility, the test conduct, and the evaluation will be presented. In the frame of the international cooperation in severe fuel damage (SFD) programs the CORA tests are contributing confirmatory and complementary informations to the results from the limited number of in-pile tests. The identification of basic phenomena of the fuel element destruction, observed as a function of temperature, is supported by separate-effects test results. Most important mechanisms are the steam oxidation of the Zircaloy cladding, which determines the temperature escalation, the chemical interaction between UO 2 fuel and cladding, which dominates fuel liquefaction, relocation and resulting blockage formation, as well as chemical interactions with Inconel spacer grids and absorber units ((Ag, In, Cd) alloy or B 4C), which are leading to extensive low-temperature melt formation around 1200°C. Interrelations between those basic phenomena, resulting for example in cladding deformation ("flowering") and the dramatic hydrogen formation in response to the fast cooling of a hot bundle by cold water ("quenching") are determining the evolution paths of fuel element destruction, which are to be identified. A further important task is the abstraction from mechanistic and microstructural details in order to get a rough classification of damage regimes (temperature and extent), a practicable analytical treatment of the materials behaviour, and a basis for decisions in accident mitigation and management procedures.

  1. The impact of integrated water management on the Space Station propulsion system

    NASA Technical Reports Server (NTRS)

    Schmidt, George R.

    1987-01-01

    The water usage of elements in the Space Station integrated water system (IWS) is discussed, and the parameters affecting the overall water balance and the water-electrolysis propulsion-system requirements are considered. With nominal IWS operating characteristics, extra logistic water resupply (LWR) is found to be unnecessary in the satisfaction of the nominal propulsion requirements. With the consideration of all possible operating characteristics, LWR will not be required in 65.5 percent of the cases, and for 17.9 percent of the cases LWR can be eliminated by controlling the stay time of theShuttle Orbiter orbiter.

  2. HANFORD SITE AIR OPERATING PERMIT SEMIANNUAL REPORT FOR THE PERIOD 07/01/2004 THRU 12/31/2004

    SciTech Connect

    GREEN, W.E.

    2005-01-19

    The Hanford Site Air Operating Permit (AOP), Number 00-05-006, became effective on July 2, 2001. One condition contained in the AOP, ''Standard Terms and Conditions'', Section 4.3.3, is the requirement to submit semiannual reports by March 15th and September 15th each year, which are certified for truth, accuracy, and completeness by a Responsible Official. This semiannual report contains information from July 1, 2004 through December 31, 2004. Copies of semiannual reports are transmitted to the Washington State Department of Ecology (Ecology). the Washington State Department of Health (WDOH), the Benton Clean Air Authority (BCAA), and the US Environmental Protection Agency (EPA), Region 10. For the applicable reporting period, AOP, ''Standard Terms and Conditions'', Section 4.3.3, as amended in August 2002 and December 2002, identifies the following. (1) Each semiannual report will provide a reference to deviation reports submitted to the regulatory agencies as required by Section 4.5. ''Permit Deviation Reporting''. (2) Each semiannual report will consist of reports of any required monitoring not submitted previously to the agencies or a reference to reports of required monitoring submitted during the reporting period. (3) Each semiannual report will contain a summary of any substantiated air emission complaint investigation(s) required in Table 1.2 of AOP, Attachment 1, and issued during the reporting period. (4) For all minor radioactive emission points (potential to emit <0.1 mrem to the maximally exposed individual) listed in AOP, Attachment 2. Tables 1.2. 1.3, and 2.1, each semiannual report will confirm that any required monitoring was conducted to verify low emissions during the reporting period. Data derived from that monitoring will be reported in the Annual National Emission Standards for Hazardous Air Pollutants (NESHAP) Report (AOP, ''Standard Terms and Conditions'', Section 4.3.1). AOP requirement is for annual monitoring (e.g., four 1 week samples

  3. Short cracks in piping and piping welds. Semiannual report, October 1990--March 1991: Volume 1, No. 2

    SciTech Connect

    Wilkowski, G.M.; Brust, F.; Francini, R.; Ghadiali, N.; Kilinski, T.; Krishnaswamy, P.; Landow, M.; Marschall, C.W.; Rahman, S.; Scott, P.

    1992-04-01

    This is the second semiannual report of the US Nuclear Regulatory Commission`s Short Cracks in Piping and Piping Welds research program. The program began in March 1990 and will extend for 4 years. The intent of this program is to verify and improve fracture analyses for circumferentially cracked large-diameter nuclear piping with crack sizes typically used in leak-before-break analyses or in-service flaw evaluations. Only quasi-static loading rates are evaluated since the NRC`s International Piping Integrity Research Group (IPIRG) program is evaluating the effects of seismic loading rates on cracked piping systems. Progress for through-wall-cracked pipe involved (1) conducting a 28-inch diameter stainless steel SAW and 4-inch diameter French TP316 experiments, (2) conducting a matrix of FEM analyses to determine GE/EPRI functions for short TWC pipe, (3) comparison of uncracked pipe maximum moments to various analyses and FEM solutions, (4) development of a J-estimation scheme that includes the strength of both the weld and base metals. Progress for surface-cracked pipe involved (1) conducting two experiments on 6-inch diameter pipe with d/t = 0.5 and {Theta}/{pi} = 0.25 cracks, (2) comparisons of the pipe experiments to Net-Section-Collapse predictions, and (3) modification of the SC.TNP and SC.TKP J-estimation schemes to include external surface cracks.

  4. Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 14, Semiannual report, April 1991--September 1991

    SciTech Connect

    Doctor, S.R.; Diaz, A.A.; Friley, J.R.; Good, M.S.; Greenwood, M.S.; Heasler, P.G.; Hockey, R.L.; Kurtz, R.J.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V.

    1992-07-01

    The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWR`s); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other components inspected in accordance with Section XI of the ASME Code. This is a progress report covering the programmatic work from April 1991 through September 1991.

  5. Evaluation of conceptual flowsheets for incorporating Light Water Reactor (LWR) fuel materials in an advanced nuclear fuel cycle

    SciTech Connect

    Bell, J.T.; Burch, W.D.; Collins, E.D.; Forsberg, C.W.; Prince, B.E.; Bond, W.D.; Campbell, D.O.; Delene, J.G.; Mailen, J.C.

    1990-08-01

    A preliminary study by a group of experts at ORNL has generated and evaluated a number of aqueous and non-aqueous flowsheets for recovering transuranium actinides from LWR fuel for use as fuel in an LMR and, at the same time, for transmutation of the wastes to less hazardous materials. The need for proliferation resistance was a consideration in the flowsheets. The current state of development of the flowsheets was evaluated and recommendations for additional study were made. 3 refs., 6 figs.

  6. CFD Simulations of a Flow Mixing and Heat Transfer Enhancement in an Advanced LWR Nuclear Fuel Assembly

    SciTech Connect

    In, Wang-Kee; Chun, Tae-Hyun; Shin, Chang-Hwan; Oh, Dong-Seok

    2007-07-01

    A computational fluid dynamics (CFD) analysis has been performed to investigate a flow-mixing and heat-transfer enhancement caused by a mixing-vane spacer in a LWR fuel assembly which is a rod bundle. This paper presents the CFD simulations of a flow mixing and heat transfer in a fully heated 5x5 array of a rod bundle with a split-vane and hybrid-vane spacer. The CFD prediction at a low Reynolds number of 42,000 showed a reasonably good agreement of the initial heat transfer enhancement with the measured one for a partially heated experiment using a similar spacer structure. The CFD simulation also predicted the decay rate of a normalized Nusselt number downstream of the split-vane spacer which agrees fairly well with those of the experiment and the correlation. The CFD calculations for the split vane and hybrid vane at the LWR operating conditions(Re = 500,000) predicted hot fuel spots in a streaky structure downstream of the spacer, which occurs due to the secondary flow occurring in an opposite direction near the fuel rod. However, the split-vane and hybrid-vane spacers are predicted to significantly enhance the overall heat transfer of a LWR nuclear fuel assembly. (authors)

  7. Rate Theory Modeling and Simulations of Silicide Fuel at LWR Conditions

    SciTech Connect

    Miao, Yinbin; Ye, Bei; Mei, Zhigang; Hofman, Gerard; Yacout, Abdellatif

    2015-12-10

    Uranium silicide (U3Si2) fuel has higher thermal conductivity and higher uranium density, making it a promising candidate for the accident-tolerant fuel (ATF) used in light water reactors (LWRs). However, previous studies on the fuel performance of U3Si2, including both experimental and computational approaches, have been focusing on the irradiation conditions in research reactors, which usually involve low operation temperatures and high fuel burnups. Thus, it is important to examine the fuel performance of U3Si2 at typical LWR conditions so as to evaluate the feasibility of replacing conventional uranium dioxide fuel with this silicide fuel material. As in-reactor irradiation experiments involve significant time and financial cost, it is appropriate to utilize modeling tools to estimate the behavior of U3Si2 in LWRs based on all those available research reactor experimental references and state-of-the-art density functional theory (DFT) calculation capabilities at the early development stage. Hence, in this report, a comprehensive investigation of the fission gas swelling behavior of U3Si2 at LWR conditions is introduced. The modeling efforts mentioned in this report was based on the rate theory (RT) model of fission gas bubble evolution that has been successfully applied for a variety of fuel materials at devious reactor conditions. Both existing experimental data and DFT-calculated results were used for the optimization of the parameters adopted by the RT model. Meanwhile, the fuel-cladding interaction was captured by the coupling of the RT model with simplified mechanical correlations. Therefore, the swelling behavior of U3Si2 fuel and its consequent interaction with cladding in LWRs was predicted by the rate theory modeling, providing valuable information for the development of U3Si2 fuel as an accident

  8. Low leaching and low LWR photoresist development for 193 nm immersion lithography

    NASA Astrophysics Data System (ADS)

    Ando, Nobuo; Lee, Youngjoon; Miyagawa, Takayuki; Edamatsu, Kunishige; Takemoto, Ichiki; Yamamoto, Satoshi; Tsuchida, Yoshinobu; Yamamoto, Keiko; Konishi, Shinji; Nakano, Katsushi; Tomoharu, Fujiwara

    2006-03-01

    receding contact angle become very important issue for not only defectivity but also scanner throughput. Some of our experimental results along this line of study are also included in the report. The last topic covered is LWR (Line Width Roughness) as an essential leverage for performance improvement, especially for the smaller CD that immersion lithography is aiming to define. Our recent effort to find effect and working concept to reduce LWR with low leaching materials is also described.

  9. BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) - Generation Methodology and Preliminary Testing of two ENEA-Bologna Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry

    NASA Astrophysics Data System (ADS)

    Pescarini, Massimo; Sinitsa, Valentin; Orsi, Roberto; Frisoni, Manuela

    2016-02-01

    Two broad-group coupled neutron/photon working cross section libraries in FIDO-ANISN format, dedicated to LWR shielding and pressure vessel dosimetry applications, were generated following the methodology recommended by the US ANSI/ANS-6.1.2-1999 (R2009) standard. These libraries, named BUGJEFF311.BOLIB and BUGENDF70.BOLIB, are respectively based on JEFF-3.1.1 and ENDF/B-VII.0 nuclear data and adopt the same broad-group energy structure (47 n + 20 γ) of the ORNL BUGLE-96 similar library. They were respectively obtained from the ENEA-Bologna VITJEFF311.BOLIB and VITENDF70.BOLIB libraries in AMPX format for nuclear fission applications through problem-dependent cross section collapsing with the ENEA-Bologna 2007 revision of the ORNL SCAMPI nuclear data processing system. Both previous libraries are based on the Bondarenko self-shielding factor method and have the same AMPX format and fine-group energy structure (199 n + 42 γ) as the ORNL VITAMIN-B6 similar library from which BUGLE-96 was obtained at ORNL. A synthesis of a preliminary validation of the cited BUGLE-type libraries, performed through 3D fixed source transport calculations with the ORNL TORT-3.2 SN code, is included. The calculations were dedicated to the PCA-Replica 12/13 and VENUS-3 engineering neutron shielding benchmark experiments, specifically conceived to test the accuracy of nuclear data and transport codes in LWR shielding and radiation damage analyses.

  10. National Council on Radiation Protection and Measurements semiannual technical progress report, March 1989--August 1989

    SciTech Connect

    Ney, W.R.

    1991-01-01

    This semiannual technical progress report is for the period 1 March 1989 through 31 August 1989. This National Council on Radiation Protection and Measurements (NCRP) program is designed to provide recommendations for radiation protection based on scientific principles. During this period several reports were published covering the topics of occupational radiation exposure, medical exposure, radon control, dosimetry, and radiation protection standards. Accomplishments of various committees are also reported; including the committees on dental x-ray protection, radiation safety in uranium mining and milling, ALARA, instrumentation, records maintenance, occupational exposures of medical personnel, emergency planning, and others. (SM)

  11. Fusion Materials Semiannual Progress Report for the Period Ending June 30, 1999

    SciTech Connect

    Rowcliffe, A.F.

    1999-09-01

    This is the twenty-sixth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and its reported separately.

  12. TFE Verification Program: Semiannual report for the period ending April 30, 1989

    SciTech Connect

    Not Available

    1989-09-01

    The objective of the semiannual progress report is to summarize the technical results obtained during the latest reporting period. The information presented herein will include evaluated test data, design evaluations, the results of analyses and the significance of results. The program objective is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. 55 figs., 30 tabs.

  13. Fusion materials semiannual progress report for the period ending June 30, 1998

    SciTech Connect

    Burn, G.

    1998-09-01

    This is the twenty-fourth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  14. Fusion reactor materials semiannual progress report for the period ending March 31, 1993

    SciTech Connect

    Not Available

    1993-07-01

    This is the fourteenth in a series of semiannual technical progress reports on fusion reactor materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Depart of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. Separate abstracts were prepared for each individual section.

  15. Fusion Materials Semiannual Progress Report for Period Ending December 31, 1998

    SciTech Connect

    Rowcliff, A.F.; Burn, G.

    1999-04-01

    This is the twenty-fifth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the U.S. Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately.

  16. TFE verification program: Semiannual report for the period ending April 30, 1988

    SciTech Connect

    Not Available

    1988-06-01

    The objective of the semiannual progress report is to summarize the technical results obtained during the latest reporting period. The information presented herein will include evaluated test data, design evaluations, the results of analyses and the significance of results. The program objective is to demonstrate the technology readiness of a Thermionic Fuel Element suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. 14 refs., 107 figs., 35 tabs.

  17. Fusion reactor materials: Semiannual progress report for the period ending March 31, 1987

    SciTech Connect

    none,

    1987-09-01

    This is the second in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities in the following areas: (1) Alloy Development for Irradiation Performance; (2) Damage Analysis and Fundamental Studies; and (3) Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. Separate analytics were prepared for the reports in this volume.

  18. Interdisciplinary program for quantitative nondestructive evaluation. Semiannual report, 1 October 1981-31 March 1982

    SciTech Connect

    Not Available

    1982-01-01

    This report constitutes the semiannual report of the Air Force/Defense Advanced Research Project Agency research program in quantitative nondestructive evaluation covering the period October 1, 1981 to March 31, 1982. It is organized by projects, each of which contains the reports of individual investigations. Because the goals of the projects are largely such that strong interdisciplinary interactions are necessary in order to achieve them, the individual reports reflect a close cooperation between various investigators. Projects included in this year's effort are: application of ultrasonic QNDE to RFC window problems; electromagnetic detection and sizing; new technical opportunities; and new flaw detection techniques. Twenty-three project reports are presented.

  19. Surface-Gasification Materials Program. Semiannual progress report for the period ending March 31, 1983

    SciTech Connect

    Bradley, R.A.

    1983-05-01

    Contents of this semiannual report include the following: introduction; (1) plant materials surveillance tests (Illinois Institute of Technology); (2) slagging gasifier refractories - appliction/evaluation (Argonne National Laboratory); (3) protective clothing and claddings - application/evaluation (ANL); (4) ceramic application technology - brittle material design (LANL); (5) advanced pressure vessel materials technology (ORNL); (6) electroslag component casting (ORNL); (7) cost reduction of the electroslag casting manufacturing process (CMU); (8) materials review and component failure analysis in support of coal gasification processes and plants (ANL); (9) process plant materials review, evaluation, and support (ORNL).

  20. TFE Verification Program semiannual report for the period ending September 30, 1990

    SciTech Connect

    Not Available

    1991-01-01

    The program objective is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and full-power life of 7 years. The objective of the semiannual progress report is to summarize the technical results obtained during the latest reporting period. The information presented in this paper will include evaluated test data, design evaluations, the results of analyses and the significance of results.

  1. Uniform corrosion of FeCrAl alloys in LWR coolant environments

    NASA Astrophysics Data System (ADS)

    Terrani, K. A.; Pint, B. A.; Kim, Y.-J.; Unocic, K. A.; Yang, Y.; Silva, C. M.; Meyer, H. M.; Rebak, R. B.

    2016-10-01

    The corrosion behavior of commercial and model FeCrAl alloys and type 310 stainless steel was examined by autoclave tests and compared to Zircaloy-4, the reference cladding materials in light water reactors. The corrosion studies were carried out in three distinct water chemistry environments found in pressurized and boiling water reactor primary coolant loop conditions for up to one year. The structure and morphology of the oxides formed on the surface of these alloys was consistent with thermodynamic predictions. Spinel-type oxides were found to be present after hydrogen water chemistry exposures, while the oxygenated water tests resulted in the formation of very thin and protective hematite-type oxides. Unlike the alloys exposed to oxygenated water tests, the alloys tested in hydrogen water chemistry conditions experienced mass loss as a function of time. This mass loss was the result of net sum of mass gain due to parabolic oxidation and mass loss due to dissolution that also exhibits parabolic kinetics. The maximum thickness loss after one year of LWR water corrosion in the absence of irradiation was ∼2 μm, which is inconsequential for a ∼300-500 μm thick cladding.

  2. Proceedings of the IAEA specialists` meeting on cracking in LWR RPV head penetrations

    SciTech Connect

    Pugh, C.E.; Raney, S.J.

    1996-07-01

    This report contains 17 papers that were presented in four sessions at the IAEA Specialists` meeting on Cracking in LWR RPV Head Penetrations held at ASTM Headquarters in Philadelphia on May 2-3, 1995. The papers are compiled here in the order that presentations were made in the sessions, and they relate to operational observations, inspection techniques, analytical modeling, and regulatory control. The goal of the meeting was to allow international experts to review experience in the field of ensuring adequate performance of reactor pressure vessel (RPV) heads and penetrations. The emphasis was to allow a better understanding of RPV material behavior, to provide guidance supporting reliability and adequate performance, and to assist in defining directions for further investigations. The international nature of the meeting is illustrated by the fact that papers were presented by researchers from 10 countries. There were technical experts present form other countries who participated in discussions of the results presented. This present document incorporates the final version of the papers as received from the authors. The final chapter includes conclusions and recommendations. Individual papers have been cataloged separately.

  3. Uniform corrosion of FeCrAl alloys in LWR coolant environments

    DOE PAGESBeta

    Terrani, K. A.; Pint, B. A.; Kim, Y. -J.; Unocic, K. A.; Yang, Y.; Silva, C. M.; Meyer, III, H. M.; Rebak, R. B.

    2016-06-29

    In this study, the corrosion behavior of commercial and model FeCrAl alloys and type 310 stainless steel was examined by autoclave tests and compared to Zircaloy-4, the reference cladding materials in light water reactors. The corrosion studies were carried out in three distinct water chemistry environments found in pressurized and boiling water reactor primary coolant loop conditions for up to one year. The structure and morphology of the oxides formed on the surface of these alloys was consistent with thermodynamic predictions. Spinel-type oxides were found to be present after hydrogen water chemistry exposures, while the oxygenated water tests resulted inmore » the formation of very thin and protective hematite-type oxides. Unlike the alloys exposed to oxygenated water tests, the alloys tested in hydrogen water chemistry conditions experienced mass loss as a function of time. This mass loss was the result of net sum of mass gain due to parabolic oxidation and mass loss due to dissolution that also exhibits parabolic kinetics. Finally, the maximum thickness loss after one year of LWR water corrosion in the absence of irradiation was ~2 μm, which is inconsequential for a ~300–500 μm thick cladding.« less

  4. Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel

    SciTech Connect

    Parks, C V; DeHart, M D; Wagner, John C

    2000-03-13

    This report has been prepared to review relevant background information and provide technical discussion that will help initiate a PIRT (Phenomena Identification and Ranking Tables) process for use of burnup credit in light-water reactor (LWR) spent fuel storage and transport cask applications. The PIRT process will be used by the NRC Office of Nuclear Regulatory Research to help prioritize and guide a coordinated program of research and as a means to obtain input/feedback from industry and other interested parties. The review and discussion in this report are based on knowledge and experience gained from work performed in the United States and other countries. Current regulatory practice and perceived industry needs are also reviewed as a background for prioritizing technical needs that will facilitate safe practice in the use of burnup credit. Relevant physics and analysis phenomenon are identified, and an assessment of their importance to burnup credit implementation is given. Finally, phenomena that need to be better understood for effective licensing, together with technical issues that require resolution, are presented and discussed in the form of a prioritization ranking and initial draft program plan.

  5. Storage of LWR (light-water-reactor) spent fuel in air

    SciTech Connect

    Thomas, L.E.; Charlot, L.A.; Coleman, J.E. ); Knoll, R.W. )

    1989-12-01

    An experimental program is being conducted at Pacific Northwest Laboratory (PNL) to determine the oxidation response of light-water-reactor (LWR) spent fuels under conditions appropriate to fuel storage in air. The program is designed to investigate several independent variables that might affect the oxidation behavior of spent fuel. Included are temperature (135 to 230{degree}C), fuel burnup (to about 34 MWd/kgM), reactor type (pressurized and boiling water reactors), moisture level in the air, and the presence of a high gamma field. In continuing tests with declad spent fuel and nonirradiated UO{sub 2} specimens, oxidation rates were monitored by weight-gain measurements and the microstructures of subsamples taken during the weighing intervals were characterized by several analytical methods. The oxidation behavior indicated by weight gain and time to form powder will be reported in Volume III of this series. The characterization results obtained from x-ray diffractometry, transmission electron microscopy, scanning electron microscopy, and Auger electron spectrometry of oxidized fuel samples are presented in this report. 28 refs., 21 figs., 3 tabs.

  6. Analysis of fission gas release in LWR fuel using the BISON code

    SciTech Connect

    G. Pastore; J.D. Hales; S.R. Novascone; D.M. Perez; B.W. Spencer; R.L. Williamson

    2013-09-01

    Recent advances in the development of the finite-element based, multidimensional fuel performance code BISON of Idaho National Laboratory are presented. Specifically, the development, implementation and testing of a new model for the analysis of fission gas behavior in LWR-UO2 fuel during irradiation are summarized. While retaining a physics-based description of the relevant mechanisms, the model is characterized by a level of complexity suitable for application to engineering-scale nuclear fuel analysis and consistent with the uncertainties pertaining to some parameters. The treatment includes the fundamental features of fission gas behavior, among which are gas diffusion and precipitation in fuel grains, growth and coalescence of gas bubbles at grain faces, grain growth and grain boundary sweeping effects, thermal, athermal, and transient gas release. The BISON code incorporating the new model is applied to the simulation of irradiation experiments from the OECD/NEA International Fuel Performance Experiments database, also included in the IAEA coordinated research projects FUMEX-II and FUMEX-III. The comparison of the results with the available experimental data at moderate burn-up is presented, pointing out an encouraging predictive accuracy, without any fitting applied to the model parameters.

  7. Fission product release and survivability of UN-kernel LWR TRISO fuel

    SciTech Connect

    T. M. Besmann; M. K. Ferber; H.-T. Lin; B. P. Collin

    2014-05-01

    A thermomechanical assessment of the LWR application of TRISO fuel with UN kernels was performed. Fission product release under operational and transient temperature conditions was determined by extrapolation from fission product recoil calculations and limited data from irradiated UN pellets. Both fission recoil and diffusive release were considered and internal particle pressures computed for both 650 and 800 um diameter kernels as a function of buffer layer thickness. These pressures were used in conjunction with a finite element program to compute the radial and tangential stresses generated within a TRISO particle undergoing burnup. Creep and swelling of the inner and outer pyrolytic carbon layers were included in the analyses. A measure of reliability of the TRISO particle was obtained by computing the probability of survival of the SiC barrier layer and the maximum tensile stress generated in the pyrolytic carbon layers from internal pressure and thermomechanics of the layers. These reliability estimates were obtained as functions of the kernel diameter, buffer layer thickness, and pyrolytic carbon layer thickness. The value of the probability of survival at the end of irradiation was inversely proportional to the maximum pressure.

  8. Feasibility study of a plant for LWR used fuel reprocessing by pyrochemical methods

    SciTech Connect

    Bychkov, A.V.; Kormilitsyn, M.V.; Savotchkin, Yu.P.; Sokolovsky, Yu.S.; Baganz, Catherine; Lopoukhine, Serge; Maurin, Guy; Medzadourian, Michel

    2007-07-01

    In 2005, experts from AREVA and RIAR performed a joint research work on the feasibility study of a plant reprocessing 1000 t/y of LWR spent nuclear fuel by the gas-fluoride and pyro-electrochemical techniques developed at RIAR. This work was based on the RIAR experience in development of pyrochemical processes and AREVA experience in designing UNF reprocessing plants. UNF reprocessing pyrochemical processes have been developed at RIAR at laboratory scale and technology for granulated MOX fuel fabrication and manufacturing of vibro-packed fuel rods is developed at pilot scale. The research work resulted in a preliminary feasibility assessment of the reprocessing plant according to the norms and standards applied in France. The study results interpretation must integrate the fact that the different technology steps are at very different stage of development. It appears clearly however that in its present state of development, pyro-electrochemical technology is not adapted to the treatment of an important material flow issuing from thermal reactors. There is probably an economic optimum to be studied for the choice of hydrometallurgical or pyro-electrochemical technology, depending on the area of application. This work is an example of successful and fruitful collaboration between French and Russian specialists. (authors)

  9. Fission Product Release and Survivability of UN-Kernel LWR TRISO Fuel

    SciTech Connect

    Besmann, Theodore M; Ferber, Mattison K; Lin, Hua-Tay

    2014-01-01

    A thermomechanical assessment of the LWR application of TRISO fuel with UN kernels was performed. Fission product release under operational and transient temperature conditions was determined by extrapolation from range calculations and limited data from irradiated UN pellets. Both fission recoil and diffusive release were considered and internal particle pressures computed for both 650 and 800 m diameter kernels as a function of buffer layer thickness. These pressures were used in conjunction with a finite element program to compute the radial and tangential stresses generated with a TRISO particle as a function of fluence. Creep and swelling of the inner and outer pyrolytic carbon layers were included in the analyses. A measure of reliability of the TRISO particle was obtained by measuring the probability of survival of the SiC barrier layer and the maximum tensile stress generated in the pyrolytic carbon layers as a function of fluence. These reliability estimates were obtained as functions of the kernel diameter, buffer layer thickness, and pyrolytic carbon layer thickness. The value of the probability of survival at the end of irradiation was inversely proportional to the maximum pressure.

  10. Fission product release and survivability of UN-kernel LWR TRISO fuel

    NASA Astrophysics Data System (ADS)

    Besmann, T. M.; Ferber, M. K.; Lin, H.-T.; Collin, B. P.

    2014-05-01

    A thermomechanical assessment of the LWR application of TRISO fuel with UN kernels was performed. Fission product release under operational and transient temperature conditions was determined by extrapolation from fission product recoil calculations and limited data from irradiated UN pellets. Both fission recoil and diffusive release were considered and internal particle pressures computed for both 650 and 800 μm diameter kernels as a function of buffer layer thickness. These pressures were used in conjunction with a finite element program to compute the radial and tangential stresses generated within a TRISO particle undergoing burnup. Creep and swelling of the inner and outer pyrolytic carbon layers were included in the analyses. A measure of reliability of the TRISO particle was obtained by computing the probability of survival of the SiC barrier layer and the maximum tensile stress generated in the pyrolytic carbon layers from internal pressure and thermomechanics of the layers. These reliability estimates were obtained as functions of the kernel diameter, buffer layer thickness, and pyrolytic carbon layer thickness. The value of the probability of survival at the end of irradiation was inversely proportional to the maximum pressure.

  11. US oil company participation in the International Energy Program. Eleventh semi-annual report to the Congress and the President

    SciTech Connect

    Not Available

    1981-10-01

    This publication is a semiannual report on the impact on competition and small business of US oil company participation in the IEP activities. IEA's response to the oil supply disruption created by the Iran/Iraq war is discussed. The proposed Plan of Action released by the DOE on May 8, 1981 is described. The report reviews the subjects discussed at meetings of the IAB and Subcommittees A and C during the reporting period. One important issue addressed at these meetings was the potential effectiveness of the allocation system. The report describes industry advice on the date to begin oil sharing after system activation. Another passage focuses on the controversies surrounding the reporting of stocks at sea and the monitoring of oil markets during non-crisis periods. Industry advice concerning emergency stock policy is reviewed. The review of industry activities during this six-month reporting period has disclosed no adverse effects on competition or small business. The allocation system was not activated, no proprietary information was exchanged among the companies, and, except as noted in the discussion of sub-trigger situations, the topics discussed were confined to those for which an antitrust defense is authorized by Section 252. To assist the Secretariat in analyzing the disruption resulting from the Iran-Iraq war, the industry did receive non-public IEA Secretariat forecasts and discussed the short-term oil supply outlook with the Secretariat. While under some circumstances these activities may have anticompetitive potential, the Commission does not believe that any adverse effects on competition actually occurred; we have no evidence that supply actions were taken by companies as a result of access to this information or participation in the meetings.

  12. 75 FR 38533 - Medicare Program; Second Semi-Annual Meeting of the Advisory Panel on Ambulatory Payment...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-02

    ... the Advisory Panel on Ambulatory Payment Classification Groups--August 23 & 24, 2010 AGENCY: Centers...: This notice announces the second semi-annual meeting of the Advisory Panel on Ambulatory Payment.../FACA/05_AdvisoryPanelonAmbulatoryPaymentClassificationGroups.asp#TopOfPage to obtain the...

  13. Data Summary Report for the 1998 Semiannual Tritium Surveys for Fourmile Branch and the F- and H-Area Seeplines

    SciTech Connect

    Koch, J.

    1999-01-26

    This report presents a summary of the definitive data validation and verification for the 1998 semiannual tritium surveys for Fourmile Branch and the F- and H-Area Seeplines. The project was performed under the direction of WSRC EAS/Ecology. This report was prepared under the direction of EPD/EMS.

  14. 78 FR 59047 - 30-Day Notice of Proposed Information Collection: Semi-Annual Labor Standards Enforcement Report...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-25

    ... URBAN DEVELOPMENT 30-Day Notice of Proposed Information Collection: Semi-Annual Labor Standards Enforcement Report--Local Contracting Agencies (HUD Programs) AGENCY: Office of the Chief Information Officer...: Colette Pollard, Reports Management Officer, QDAM, Department of Housing and Urban Development, 451...

  15. 78 FR 45260 - 60-Day Notice of Proposed Information Collection: Semi-annual Labor Standards Enforcement Report...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-26

    ... URBAN DEVELOPMENT 60-Day Notice of Proposed Information Collection: Semi-annual Labor Standards Enforcement Report- Local Contracting Agencies (HUD Programs) AGENCY: Office of Labor Relation, HUD. ACTION..., Office of labor Relation, Department of Housing and Urban Development, 451 7th Street SW., Room...

  16. The low and middle latitude semi-annual anomaly in NmF2 near noon: A statistical study

    NASA Astrophysics Data System (ADS)

    Pavlov, A. V.

    2012-03-01

    Hourly values of the F2-layer peak density, NmF2, measured by 99 ionosonde stations near noon from 1957 to 2010 at low and middle geomagnetic latitudes of the northern and southern geographic hemispheres are used in a statistical study of the F2-region semi-annual anomaly. The equinox/winter and equinox/summer geomagnetically quiet NmF2 ratios, X and Y, taken near noon over each ionosonde for approximately the same winter, equinox, and summer solar activity conditions are analyzed. The conditional probabilities of occurrences of X and Y in intervals of X and Y, the most frequent values of X and Y, the mean expected values of X and Y, and the conditional probability to observe the F2-region semi-annual anomaly are calculated and studied for the fist time for low, moderate, and high solar activity conditions. These statistical parameters are averaged over 5° geomagnetic latitude interval in the northern and southern geographic hemispheres, and the trends in these averaged statistical characteristics of the NmF2 semi-annual anomaly are calculated and studied for the fist time. It is shown that the median approach can produce the incorrect conclusions about the absence of the NmF2 semi-annual anomaly.

  17. 46 CFR Appendix III to Part 390 - U.S. Department of Transportation, Maritime Administration-Sample Semiannual Report

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 46 Shipping 8 2013-10-01 2013-10-01 false U.S. Department of Transportation, Maritime Administration-Sample Semiannual Report III Appendix III to Part 390 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION REGULATIONS UNDER PUBLIC LAW 91-469 CAPITAL CONSTRUCTION FUND Pt. 390, App. III Appendix III to Part 390—U.S. Department...

  18. 78 FR 13346 - Medicare Program; Changes to the Semi-Annual Meeting of the Advisory Panel on Hospital Outpatient...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-27

    ... Federal Register (77 FR 70447) announcing the first semi-annual meeting of the Advisory Panel on Hospital.... We refer readers to that previously published notice for general information. II. Provisions of the... HUMAN SERVICES Centers for Medicare & Medicaid Services Medicare Program; Changes to the...

  19. Research Libraries in the Online Environment. Minutes of the Semiannual Meeting (102nd, Banff, Alberta, May 4-6, 1983).

    ERIC Educational Resources Information Center

    Association of Research Libraries, Washington, DC.

    Included in the transcript of this semiannual meeting of the Assocation of Research Libraries (ARL) are the following: (1) papers by Sharon Hogan on the definition of data in an online environment, by John Black on ways of communicating data, and by Peter Wolters on data sharing and library networking in the United States and Canada; (2) a record…

  20. Data Summary Report for the Semiannual Tritium Survey for Fourmile Branch and the F- and H-Area Seeplines

    SciTech Connect

    Koch, J. II

    1996-12-16

    This report presents a summary of the definitive data validation and verification for the Semiannual Tritium Survey for Fourmile Branch and the F- and H-Area Seeplines. The survey was performed at the request of the WSRC ERD and conducted by WSRC/ESS. This report was prepared under the direction of EPD/EMS.

  1. 46 CFR Appendix III to Part 390 - U.S. Department of Transportation, Maritime Administration-Sample Semiannual Report

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false U.S. Department of Transportation, Maritime Administration-Sample Semiannual Report III Appendix III to Part 390 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION REGULATIONS UNDER PUBLIC LAW 91-469 CAPITAL CONSTRUCTION FUND Pt. 390, App. III Appendix III to Part 390—U.S. Department...

  2. Research on Reading in Secondary Schools: A Semi-Annual Report, Volume 2, Number 2. Monograph Number Three.

    ERIC Educational Resources Information Center

    Vaughan, Joseph L., Jr., Ed.; Gaus, Paula J., Ed.

    This monograph is the third in a series of semiannual reports of research related to reading in secondary schools. The first section of the monograph is made up of three research studies on the validation of teaching procedures to facilitate students' comprehension of content area texts, the graph-reading abilities of seventh grade students, and a…

  3. Prospects for Improving Document Delivery. Minutes of the Semiannual Meeting (101st, Arlington, Virginia, October 13-14, 1982).

    ERIC Educational Resources Information Center

    Daval, Nicola, Ed.

    This set of minutes from a semiannual meeting of the Association of Research Libraries (ARL) includes three presentations: "The Economics of Document Delivery" by Donald B. Simpson, "Electronic Journal Publishing and Libraries" by Jay K. Lucker, and "Policies and Controversies" by Hugh C. Atkinson. Atkinson reviews copyright issues,…

  4. Estimation of mechanical properties of cast stainless steels during thermal aging in LWR systems

    SciTech Connect

    Chopra, O.K.

    1991-10-01

    A procedure and correlations are presented for predicting Charpy- impact energy, tensile flow stress, fracture toughness J-R curve, and J{sub IC} of aged cast stainless steels from known material information. The ``saturation`` impact strength and fracture toughness of a specific cast stainless steel, i.e., the minimum value that would be achieved for the material after long-term service, is estimated from the chemical composition of the steel. Mechanical properties as a function of time and temperature of reactor service are estimated from impact energy and flow stress of the unaged material and the kinetics of embrittlement, which are also determined from chemical composition. The J{sub IC} values are determined from the estimated J-R curve and flow stress. Examples of estimating mechanical properties of cast stainless steel components during reactor service are presented. A common ``lower-bound`` J-R curve for cast stainless steels of unknown chemical composition is also defined for a given grade of steel, ferrite content, and temperature.

  5. Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems

    SciTech Connect

    Chopra, O.K. )

    1991-06-01

    A procedure and correlations are presented for predicting the change in fracture toughness of cast stainless steel components due to thermal aging during service in light water rectors (LWRs) at 280--330{degrees}C (535--625{degrees}F). The fracture toughness J-R curve and Charpy-impact energy of aged cast stainless steels are estimated from known mineral in formation. Fracture toughness of a specific cast stainless steel is estimated from the extent and kinetics of thermal embrittlement. The extent of thermal embrittlement is characterized by the room-temperature normalized'' Charpy-impact energy. A correlation for the extent of embrittlement at saturation,'' i.e., the minimum impact energy that would be achieved for the material after long-term aging, is given in terms of a material parameter, {Phi}, which is determined from the chemical composition. The fracture toughness J-R curve for the material is then obtained from correlations between room-temperature Charpy-impact energy and fracture toughness parameters. Fracture toughness as a function of time and temperature of reactor service is estimated from the kinetics of thermal embrittlement, which is determined from chemical composition. A common lower-bound'' J-R curve for cast stainless steels with unknown chemical composition is also defined for a given material specification, ferrite content, and temperature. Examples for estimating impact strength and fracture toughness of cast stainless steel components during reactor service are describes. 24 refs., 39 figs., 2 tabs.

  6. Prediction of aging degradation of cast stainless steel components in LWR systems

    SciTech Connect

    Chopra, O.K.

    1992-03-01

    A procedure and correlations are presented for predicting Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, and J{sub IC} of aged cast stainless steels from known material information. The ``saturation`` impact strength and fracture toughness of a specific cast stainless steel, i.e., the minimum value that would be achieved for the material after long-term service, is estimated from the chemical composition of the steel. Mechanical properties as a function of time and temperature of reactor service are estimated from impact energy and flow stress of the unaged material and the kinetics of embrittlement, which are also determined from chemical composition. The J{sub IC} values are determined from the estimated J-R curve and flow stress. Examples of estimating mechanical properties of of cast stainless steel components during reactor service are presented. A common ``predicted lower-bound` J-R curve for cast stainless steels of unknown chemical composition is also defined for a given grade of steel, ferrite content, and temperature.

  7. Prediction of aging degradation of cast stainless steel components in LWR systems

    SciTech Connect

    Chopra, O.K.

    1992-03-01

    A procedure and correlations are presented for predicting Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, and J{sub IC} of aged cast stainless steels from known material information. The saturation'' impact strength and fracture toughness of a specific cast stainless steel, i.e., the minimum value that would be achieved for the material after long-term service, is estimated from the chemical composition of the steel. Mechanical properties as a function of time and temperature of reactor service are estimated from impact energy and flow stress of the unaged material and the kinetics of embrittlement, which are also determined from chemical composition. The J{sub IC} values are determined from the estimated J-R curve and flow stress. Examples of estimating mechanical properties of of cast stainless steel components during reactor service are presented. A common predicted lower-bound' J-R curve for cast stainless steels of unknown chemical composition is also defined for a given grade of steel, ferrite content, and temperature.

  8. Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems - Revison 1.

    SciTech Connect

    Chopra, O. K.; Energy Technology

    1994-10-05

    This report presents a revision of the procedure and correlations presented earlier in NUREG/CR-4513, ANL-90/42 (June 1991) for predicting the change in mechanical properties of cast stainless steel components due to thermal aging during service in light water reactors at 280-330 C (535-625 F). The correlations presented in this report are based on an expanded data base and have been optimized with mechanical-property data on cast stainless steels aged up to {approx}58,000 h at 290-350 C (554-633 F). The correlations for estimating the change in tensile stress, including the Ramberg/Osgood parameters for strain hardening, are also described. The fracture toughness J-R curve, tensile stress, and Charpy-impact energy of aged cast stainless steels are estimated from known material information. Mechanical properties of a specific cast stainless steel are estimated from the extent and kinetics of thermal embrittlement. Embrittlement of cast stainless steels is characterized in terms of room-temperature Charpy-impact energy. The extent or degree of thermal embrittlement at 'saturation,' i.e., the minimum impact energy that can be achieved for a material after long-term aging, is determined from the chemical composition of the steel. Charpy-impact energy as a function of time and temperature of reactor service is estimated from the kinetics of thermal embrittlement, which are also determined from the chemical composition. The initial impact energy of the unaged steel is required for these estimations. Initial tensile flow stress is needed for estimating the flow stress of the aged material. The fracture toughness J-R curve for the material is then obtained by correlating room-temperature Charpy-impact energy with fracture toughness parameters. The values of JIC are determined from the estimated J-R curve and flow stress. A common 'predicted lower-bound' J-R curve for cast stainless steels of unknown chemical composition is also defined for a given grade of steel, range of ferrite content, and temperature. Examples of estimating mechanical properties of cast stainless steel components during reactor service are presented.

  9. The development of coal-based technologies for Department of Defense facilities. Volume 2, Appendices. Semiannual technical progress report, September 28, 1994--March 27, 1995

    SciTech Connect

    Miller, B.G.; Bartley, D.A.; Hatcher, P.

    1996-10-15

    This semiannual progress report contains the following appendices: description of the 1,000 lb steam/h watertube research boiler; the Pennsylvania CGE model; Phase II, subtask 3.9 coal market analysis; the CGE model; and sector definition.

  10. Fuel Performance Improvement Program. Semiannual progress report, October 1979-March 1980. [PWR; BWR

    SciTech Connect

    Not Available

    1980-04-01

    Progress on the Fuel Performance Improvement Program's fuel design tests and demonstration irradiations for October 1979 through March 1980 is reported. Included are the results of out-of-reactor experiments with Zircaloy cladding using a device that simulates the interaction between fuel and cladding. Also included are reports on the irradiation of the advanced LWR fuel designs in the Halden Boiling Water Reactor and in Consumers Power Company's Big Rock Point Reactor. The establishment of the technical bases and licensing requirements for the advanced fuel concepts are also described.

  11. Stability of SiC-Matrix Microencapsulated Fuel Constituents at Relevant LWR Conditions

    SciTech Connect

    Terrani, Kurt A; Katoh, Yutai; Leonard, Keith J; Perez-Bergquist, Alex G; Silva, Chinthaka M; Snead, Lance Lewis

    2014-01-01

    This paper addresses certain key feasibility issues facing the application of SiC-matrix microencapsulated fuels for light water reactor application. Issues addressed are the irradiation stability of the SiC-based nano-powder ceramic matrix under LWR-relevant irradiation conditions, the presence or extent of reaction of the SiC matrix with zirconium-based cladding, the stability of the inner and outer pyrolytic graphite layers of the microencapsulated (TRISO) particle at this uncharacteristically low irradiation temperature, and the state of the particle-matrix interface following irradiation which could possibly effect thermal transport. In the process of determining these feasibility issues microstructural evolution and change in dimension and thermal conductivity was studied. As a general finding the SiC matrix was found to be quite stable with behavior similar to that of CVD SiC. In magnitude the irradiation-induced swelling of the matrix material was slightly higher and irradiation-degraded thermal conductivity was slightly lower as compared to CVD SiC. No significant reaction of this SiC-based nano-powder ceramic matrix material with Zircaloy was observed. Irradiation of the TRISO in the 320-360 C range to a maximum dose of 7.7 1025 n/m2 (E > 0.1 MeV) did not have significant negative impact on the constituent layers of the TRISO fuel. At the highest dose studied layer structure and interface integrity remained essentially unchanged with good apparent thermal transport through the microsphere to the surrounding matrix.

  12. Analysis of the Reuse of Uranium Recovered from the Reprocessing of Commercial LWR Spent Fuel

    SciTech Connect

    DelCul, Guillermo Daniel; Trowbridge, Lee D; Renier, John-Paul; Ellis, Ronald James; Williams, Kent Alan; Spencer, Barry B; Collins, Emory D

    2009-02-01

    This report provides an analysis of the factors involved in the reuse of uranium recovered from commercial light-water-reactor (LWR) spent fuels (1) by reenrichment and recycling as fuel to LWRs and/or (2) by recycling directly as fuel to heavy-water-reactors (HWRs), such as the CANDU (registered trade name for the Canadian Deuterium Uranium Reactor). Reuse is an attractive alternative to the current Advanced Fuel Cycle Initiative (AFCI) Global Nuclear Energy Partnership (GNEP) baseline plan, which stores the reprocessed uranium (RU) for an uncertain future or attempts to dispose of it as 'greater-than-Class C' waste. Considering that the open fuel cycle currently deployed in the United States already creates a huge excess quantity of depleted uranium, the closed fuel cycle should enable the recycle of the major components of spent fuel, such as the uranium and the hazardous, long-lived transuranic (TRU) actinides, as well as the managed disposal of fission product wastes. Compared with the GNEP baseline scenario, the reuse of RU in the uranium fuel cycle has a number of potential advantages: (1) avoidance of purchase costs of 11-20% of the natural uranium feed; (2) avoidance of disposal costs for a large majority of the volume of spent fuel that is reprocessed; (3) avoidance of disposal costs for a portion of the depleted uranium from the enrichment step; (4) depending on the {sup 235}U assay of the RU, possible avoidance of separative work costs; and (5) a significant increase in the production of {sup 238}Pu due to the presence of {sup 236}U, which benefits somewhat the transmutation value of the plutonium and also provides some proliferation resistance.

  13. Proceedings of the First Semiannual Distributed Receiver Program Review

    NASA Technical Reports Server (NTRS)

    1980-01-01

    Point focus and line focus distributed receiver solar thermal technology for the production of electric power and of industrial process heat is addressed. Concentrator, receiver, and power conversion development are covered along with hardware tests and evaluation. Mass production costing, parabolic dish applications, and trough and bowl systems are included.

  14. Characteristics of spent fuel, high-level waste, and other radioactive wastes which may require long-term isolation: Appendix 2A, Physical descriptions of LWR (Light-Water Reactor) fuel assemblies

    SciTech Connect

    Not Available

    1987-12-01

    This appendix includes a four-page Physical Description report for each assembly type identified from the current data. Where available, a drawing of an assembly follows the appropriate Physical Description report. If no drawing is available for an assembly, a cross-reference to a similar assembly is provided if possible. For Advanced Nuclear Fuels, Babcock and Wilcox, Combustion Engineering, and Westinghouse assemblies, information was obtained via subcontracts with these fuel vendors. Data for some assembly types are not available. For such assemblies, the information shown in this report was obtained from the open literature and by inference from reload fuels made by other vendors. Efforts to obtain additional information are continuing. Individual Physical Description reports can be generated interactively through the menu-driven LWR Assemblies Data Base system. These reports can be viewed on the screen or directed to a printer. Special reports and compilations of specific data items can be produced on request.

  15. Evaluation of effects of LWR coolant environments on fatigue life of carbon and low-alloy steels

    SciTech Connect

    Chopra, O.K.; Shack, W.J.

    1996-02-01

    The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figure I-90 of Appendix I to Section III of the Code specifies fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Recent test data indicate a significant decrease in fatigue life of carbon and low-alloy steels in LWR environments when five conditions are satisfied simultaneously, viz., applied strain range, temperature, dissolved oxygen in the water, and sulfur content of the steel are above a minimum threshold level, and the loading strain rate is below a threshold value. Only a moderate decrease in fatigue life is observed when any one of these conditions is not satisfied. This paper summarizes available data on the effects of various material and loading variables such as steel type, dissolved oxygen level, strain range, strain rate, and sulfur content on the fatigue life of carbon and low-alloy steels. The data have been analyzed to define the threshold values of the five critical parameters. Methods for estimating fatigue lives under actual loading histories are discussed.

  16. A fracture mechanics approach for estimating fatigue crack initiation in carbon and low-alloy steels in LWR coolant environments

    SciTech Connect

    Park, H. B.; Chopra, O. K.

    2000-04-10

    A fracture mechanics approach for elastic-plastic materials has been used to evaluate the effects of light water reactor (LWR) coolant environments on the fatigue lives of carbon and low-alloy steels. The fatigue life of such steel, defined as the number of cycles required to form an engineering-size crack, i.e., 3-mm deep, is considered to be composed of the growth of (a) microstructurally small cracks and (b) mechanically small cracks. The growth of the latter was characterized in terms of {Delta}J and crack growth rate (da/dN) data in air and LWR environments; in water, the growth rates from long crack tests had to be decreased to match the rates from fatigue S-N data. The growth of microstructurally small cracks was expressed by a modified Hobson relationship in air and by a slip dissolution/oxidation model in water. The crack length for transition from a microstructurally small crack to a mechanically small crack was based on studies on small crack growth. The estimated fatigue S-N curves show good agreement with the experimental data for these steels in air and water environments. At low strain amplitudes, the predicted lives in water can be significantly lower than the experimental values.

  17. Identification of the impacts of maintenance and testing upon the safety of LWR power plants. Final report

    SciTech Connect

    Husseiny, A. A.; Sabri, Z. A.; Turnage, J. J.

    1980-04-01

    The present study was designed to identify the impact of maintenance and testing (M and T) upon the safety of LWR power plants. The study involved data extraction from various sources reporting safety-related and operation-related nuclear power plant experience. Primary sources reviewed, including Licensee Event Reports (LER's) submitted to the NRC, revealed that only ten percent of events reported could be identified as M and T problems. The collected data were collated in a manner that would allow identification of principal types of problems which are associated with the performance of M and T tasks in LWR power plants. Frequencies of occurrence of events and their general endemic nature were analyzed using data clustering and pattern recognition techniques, as well as chi-square analyses for sparse contingency tables. The results of these analyses identified seven major categories of M and T error modes which were related to individual facilities and reactor type. Data review indicated that few M and T problems were directly related to procedural inadequacies, with the majority of events being attributable to human error.

  18. Semi-annual report of the Department of Energy, Office of Environmental Management, Quality Assessment Program

    SciTech Connect

    Greenlaw, P.D.

    1998-01-01

    This Quality Assessment Program (QAP) is designed to test the quality of the environmental measurements being reported to the Department of Energy by its contractors. Since 1976, real or synthetic environmental samples that have been prepared and thoroughly analyzed at the Environmental Measurements Laboratory (EML) have been distributed at first quarterly and then semi-annually to these contractors. Their results, which are returned to EML within 90 days, are compiled with EML`s results and are reported back to the participating contractors 30 days later. A summary of the reported results is available to the participants 4 days after the reporting deadline via the Internet at www.eml.doe.gov. This report presents the results from the analysis of the 47th set of environmental quality assessment samples (QAP XLVII) that were received on or before December 1, 1997.

  19. NRC regulatory agenda: Semiannual report, January--June 1997. Volume 16, Number 1

    SciTech Connect

    1997-08-01

    The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition. The agenda consists of two sections that have been updated through June 30, 1997. Section 1, ``Rules,`` includes (A) rules on which final action has been taken since December 31, 1996, the closing date of the last NRC Regulatory Agenda; (B) rules published previously as proposed rules on which the Commission has not taken final action; (C) rules published as advance notices of proposed rulemaking for which neither a proposed nor final rule has been issued; and (D) unpublished rules on which the NRC expects to take action. Section 2, ``Petitions for Rulemaking,`` includes (A) petitions denied or incorporated into final rules since December 31, 1996; (B) petitions incorporated into proposed rules; and (C) petitions pending staff review.

  20. Office of Inspector General semiannual report to Congress, October 1, 1997--March 31, 1998

    SciTech Connect

    1998-04-01

    This Office of Inspector General (OIG) Semiannual Report to the Congress covers the period from October 1, 1997, through March 31, 1998. The report summarizes significant audit, inspection, and investigative accomplishments for the reporting period that facilitated Department of Energy (Department) efforts to improve management controls and ensure efficient and effective operation of its programs. This report highlights OIG accomplishments in support of its Strategic Plan. Narratives of the Office`s most significant reports are grouped by the strategic goals against which the OIG measures its performance. To put the OIG accomplishments for this reporting period in context, the following statistical information is provided: audit and inspection reports issued -- 47; recommendations that funds be put to better use -- $356,257,856; management commitment to taking corrective actions -- $289,106,445; criminal indictments/convictions -- 8; fines and recoveries -- $1,612,932; and investigative reports to management recommending positive change -- 21.

  1. TFE Verification Program: Semiannual report for the period ending October 31, 1988

    SciTech Connect

    Not Available

    1989-01-01

    The objective of the semiannual progress report is to summarize the technical results obtained during the latest reporting period. The information presented herein will include evaluated test data, design evaluations, the results of analyses and the significance of results. The program objective is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. The TFE Verification Program builds directly on the technology and data base developed in the 1960s and early 1970s in an AEC/NASA program, and in the SP-100 program conducted in 1983, 1984 and 1985. In the SP-100 program, the attractive features of thermionic power conversion technology were recognized, but concern was expressed over the lack of fast reactor irradiation data. 65 figs., 36 tabs.

  2. Office of Inspector General semiannual report to Congress, April 1--September 30, 1995

    SciTech Connect

    1995-10-01

    This Office of Inspector General Semiannual Report to the Congress covers the period from April 1 through September 30, 1995. The report summarizes significant audit, inspection, and investigative accomplishments for the reporting period, a large portion of which facilitated Department of Energy management efforts to improve management controls and ensure efficient and effective operation of its programs. Narratives of the most significant reports are grouped by six primary performance measures which the Office of Inspector General uses to gauge its attainment of the outcomes established in the Office of Inspector General Strategic Plan. The common thread that ties the performance measures together is their emphasis on supporting Department efforts to produce high quality products at the lowest possible cost to the taxpayer. The six performance measures present outcomes of Office of Inspector General work in terms of improvements in Department programs and operations.

  3. Semi-annual report of the Department of Energy, Office of Environmental Management, Quality Assessment Program

    SciTech Connect

    Greenlaw, P.D.; Minick, S.K.

    1998-07-01

    This Quality Assessment Program (QAP) is designed to test the quality of the environmental measurements being reported to the Department of Energy by its contractors. Since 1976, real or synthetic environmental samples that have been prepared and thoroughly analyzed at the Environmental Measurements Laboratory (EML) have been distributed at first quarterly and then semi-annually to these contractors. Their results, which are returned to EML within 90 days, are compiled with EML`s results and are reported back to the participating contractors 30 days later. This report presents the results from the analysis of the 48th set of environmental quality assessment samples (QAP XLVIII) that were received on or before June 1, 1998.

  4. Fusion reactor materials. Semiannual progress report for period ending September 30, 1993

    SciTech Connect

    Rowcliffe, A.F.; Burn, G.L.; Knee`, S.S.; Dowker, C.L.

    1994-02-01

    This is the fifteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; Special purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the U.S. Department of Energy. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

  5. Equatorial semiannual oscillation in zonally averaged temperature observed by the Nimbus 7 SAMS and LIMS

    NASA Technical Reports Server (NTRS)

    Delisi, Donald P.; Dunkerton, Timothy J.

    1988-01-01

    Zonally averaged equatorial temperatures obtained aboard Nimbus 7 by the stratospheric and mesospheric sounder (SAMS) are compared to comparable data obtained from the limb IR monitor of the stratosphere. The SAMS data are shown to confirm the seasonal asymmetry in semiannual wind regimes previously noted in rocketsonde observations near the equator. Two explanations for the asymmetry are considered: (1) an improved Kelvin and gravity wave transmissivity in stronger equatorial easterlies (resulting from planetary Rossby wave momentum transport), implying stronger westerly mean flow acceleration in the first cycle than in the second; and (2) evidence of strong polar-tropical coupling in the northern winter indicating that mean meridional circulations are present on a global scale.

  6. Semiannual report to Congress on Inspector General audit reports, April 1, 1993--September 30, 1993

    SciTech Connect

    Not Available

    1993-11-01

    This is the Secretary of Energy`s ninth Semiannual Report to Congress to be submitted under the Inspector General Act of 1978, as amended. Pursuant to the Inspector General Act Amendments of 1988 (Public Law 100-504), agency heads are to report to Congress on the status of final action taken on audit report recommendations. This report complements a report prepared by the Department`s Office of Inspector General that provides information on audit reports issued during the period and on the status of management decisions made on Inspector General audit reports. During the period covered by this report, April 1 through September 30, 1993, the Department took final action on four contract and financial assistance audit reports. At the end of the period only three reports awaited final action. With regard to operational, financial, and preaward audits, final action was taken on 41 reports, resulting in 93 audit reports needing final action at the end of the period.

  7. Synodic and semiannual oscillations of argon-40 in the lunar exosphere

    NASA Astrophysics Data System (ADS)

    Hodges, R. Richard; Mahaffy, Paul R.

    2016-01-01

    The neutral mass spectrometer on the Lunar Atmosphere and Dust Environment Explorer (LADEE) spacecraft collected a trove of exospheric data, including a set of high-quality measurements of radiogenic 40Ar over a period of 142 days. Data synthesis studies, using well-established exosphere simulation tools, show that the LADEE argon data are consistent with an exosphere-regolith interaction that is dominated by adsorption and that the desorption process generates the Armand distribution of exit velocities. The synthesis work has uncovered an apparent semiannual oscillation of argon that is consistent with temporal sequestration in the seasonal cold traps created at the poles by the obliquity of the Moon. In addition, the LADEE data provide new insight into the pristine nature of lunar regolith, its spatially varying sorption properties, and the influence of sorption processes on the synodic oscillation of the argon exosphere.

  8. TFE Verification Program: Semiannual report for the period ending September 30, 1987

    SciTech Connect

    Not Available

    1988-03-01

    The objective of the semiannual progress report is to summarize the technical results obtained during the latest reporting period. The information presented herein will include evaluated test data, design evaluations, the results of analyses and the significance of results. The program objective is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. The TFE Verification Program builds directly on the technology and data base developed in the 1960s and early 1970s in an AEC/NASA program, and in the SP-100 program conducted in 1983, 1984 and 1985. In the SP-100 program, the attractive features of thermionic power conversion technology were recognized, but concern was expressed over the lack of fast reactor irradiation data. The TFE Verification Program addresses this concern.

  9. MHD Technology Transfer, Integration and Review Committee. Second semiannual status report, July 1988--March 1989

    SciTech Connect

    Not Available

    1989-10-01

    As part of the MHD Integrated Topping Cycle (ITC) project, TRW was given the responsibility to organize, charter and co-chair, with the Department of Energy (DOE), an MHD Technology Transfer, Integration and Review Committee (TTIRC). The Charter of the TTIRC, which was approved by the DOE in June 1988 and distributed to the committee members, is included as part of this Summary. As stated in the Charter, the purpose of this committee is to: (1) review all Proof-of-Concept (POC) projects and schedules in the national MHD program; to assess their compatibility with each other and the first commercial MHD retrofit plant; (2) establish and implement technology transfer formats for users of this technology; (3) identify interfaces, issues, and funding structures directly impacting the success of the commercial retrofit; (4) investigate and identify the manner in which, and by whom, the above should be resolved; and (5) investigate and assess other participation (foreign and domestic) in the US MHD Program. The DOE fiscal year 1989 MHD Program Plan Schedule is included at the end of this Summary. The MHD Technology Transfer, Integration and Review Committee`s activities to date have focused primarily on the ``technology transfer`` aspects of its charter. It has provided a forum for the dissemination of technical and programmatic information among workers in the field of MHD and to the potential end users, the utilities, by holding semi-annual meetings. The committee publishes this semi-annual report, which presents in Sections 2 through 11 capsule summaries of technical progress for all DOE Proof-of-Concept MHD contracts and major test facilities.

  10. Reactor Safety Research: Semiannual report, July-December 1986

    SciTech Connect

    Not Available

    1987-11-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of the accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance and behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the tehcnology base supporting licensing decisions.

  11. Physics Division semiannual report, July 1-December 31, 1982

    SciTech Connect

    Trela, W.J.

    1983-09-01

    The Physics Division is organized into three major research areas: Fusion Physics, Weapons Physics, and Basic Research. In Fusion Physics, the KrF laser project reached two important milestones: successful testing of a 1-m/sup 2/ electron diode for KrF gas excitation and completion of a combined aperture demonstration showing the feasibility of accurate alignment of spherical mirrors. In the CO/sub 2/ program, the 5-kJ Helios lasers were used to evaluate many physics issues concerning the use of 10-..mu..m light for inertial fusion and the 30- to 40-kJ Antares laser construction projects is on schedule for completion in October 1983. In Weapons Physics, significant progress was made on developing continuous time-dependent imaging systems using tomographic techniques with 400-ps shuttering capability, fiber-optic Cerenkov detector systems for fast fusion measurements, and iron-doped indium-phosphide detectors with 70-ps impulse response. A proposal to build x-ray beam lines at the National Synchrotron Light Source was approved and we expect funding in 1984. In Basic Physics Research, we have begun new initiatives to study biomagnetism in collaboration with the Life Sciences Division and to develop a neutrino physics program. During this period numerous significant experiments were completed in our nuclear physics, condensed matter physics, and thermal physics programs.

  12. Environmental restoration/waste management-applied technology semiannual report, January--June 1992. Volume 1, No. 1

    SciTech Connect

    Adamson, M.; Kline-Simon, K.

    1992-12-31

    This is the first issue from the Lawrence Livermore National Laboratory of The Environmental Restoration/Waste Management-Applied Technology (ER/WM-AT) Semiannual Report, a continuation of the Advanced Processing Technology (APT) Semiannual Report. The name change reflects the consolidation of the APT Program with the Environmental Restoration and Waste Management Program to form the Environmental Restoration/Waste Management-Applied Technology (ER/WM-AT) Program. The Livermore site mirrors, on a small scale, many of the environmental and waste management problems of the DOE Complex. The six articles in this issue cover incineration- alternative technologies, process development for waste minimization, the proposed Mixed Waste Management Facility, dynamic underground stripping, electrical resistance tomography, and Raman spectroscopy for remote characterization of underground tanks.

  13. Secular, annual, and semiannual changes in the baseline level of the earth's magnetic field at North American locations.

    USGS Publications Warehouse

    Campbell, W.H.

    1980-01-01

    Secular, annual, and semiannual changes were obtained from the midnight values of field on specially determined days of quiet magnetospheric conditions. From a selection of North American observatories the latitude variation of these changes was evaluated from 20o to 65o. Results for the active and quiet sun years (1958 and 1965) were compared, and changes at Tucson were traced from 1958 through 1974. The year-to-year variance in the determination of a secular change seemed to be decreased by the present analysis method in comparison to a method which uses the annual mean of hourly values. The annual horizontal field variations were largely northward in early summer and southward in early winter, quiet year amplitudes of 2 to 3 gamma about doubled in the solar active year. The amplitudes of the semiannual field vectors were about one half that of the annual vectors; the directions were apparently inconsistent from year to year. -Authors

  14. Ceramic Technology Project semiannual progress report, April 1992--September 1992

    SciTech Connect

    Johnson, D.R.

    1993-07-01

    This project was developed to meet the ceramic technology requirements of the DOE Office of Transportation Systems` automotive technology programs. Significant progress in fabricating ceramic components for DOE, NASA, and DOE advanced heat engine programs show that operation of ceramic parts in high-temperature engines is feasible; however, addition research is needed in materials and processing, design, and data base and life prediction before industry will have a sufficient technology base for producing reliable cost-effective ceramic engine components commercially. A 5-yr project plan was developed, with focus on structural ceramics for advanced gas turbine and diesel engines, ceramic bearings and attachments, and ceramic coatings for thermal barrier and wear applications in these engines.

  15. ICASE semiannual report, April 1 - September 30, 1989

    NASA Technical Reports Server (NTRS)

    1990-01-01

    The Institute conducts unclassified basic research in applied mathematics, numerical analysis, and computer science in order to extend and improve problem-solving capabilities in science and engineering, particularly in aeronautics and space. The major categories of the current Institute for Computer Applications in Science and Engineering (ICASE) research program are: (1) numerical methods, with particular emphasis on the development and analysis of basic numerical algorithms; (2) control and parameter identification problems, with emphasis on effective numerical methods; (3) computational problems in engineering and the physical sciences, particularly fluid dynamics, acoustics, and structural analysis; and (4) computer systems and software, especially vector and parallel computers. ICASE reports are considered to be primarily preprints of manuscripts that have been submitted to appropriate research journals or that are to appear in conference proceedings.

  16. Fossil Energy Program semiannual progress report, October 1990--March 1991

    SciTech Connect

    Judkins, R.R.

    1992-07-01

    This report covers progress made during the period October 1, 1990, through March 31, 1991, for research and development projects that contribute to the advancement of various fossil energy technologies. Projects on the Fossil Energy Program are supported by the DOE Office of Fossil Energy, the DOE Morgantown Energy Technology Center, the DOE Pittsburgh Energy Technology Center, the DOE Fossil Energy Clean Coal Technology Program, the DOE Office of Basic Energy Sciences, the DOE Fossil Energy Office of Petroleum Reserves, the DOE Fossil Energy Naval Petroleum and Oil Shale Reserves, and the US Agency for International Development. The Fossil, Energy Program organization chart is shown in the appendix. Topics include: alloys, ceramics and composite research and development; corrosion and erosion research; environmental analysis and information systems; coal conversion development; mild gasification product characterization; coal combustion research; strategic petroleum reserve planning and modeling; and coal structure and chemistry.

  17. MHD Technology Transfer, Integration and Review Committee. Fifth semi-annual status report, April 1990--September 1990

    SciTech Connect

    Not Available

    1992-01-01

    This fifth semi-annual status report of the MHD Technology Transfer, Integration, and Review Committee (TTIRC) summarizes activities of the TTIRC during the period April 1990 through September 1990. It includes summaries and minutes of committee meetings, progress summaries of ongoing Proof-of-Concept (POC) contracts, discussions pertaining to technical integration issues in the POC program, and planned activities for the next six months.

  18. Nuclear Technology Programs semiannual progress report, October 1988--March 1989

    SciTech Connect

    Harmon, J.E.

    1990-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1988--March 1989. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories. 127 refs., 76 figs., 103 tabs.

  19. Nuclear technology programs; Semiannual progress report, October 1989--March 1990

    SciTech Connect

    Harmon, J.E.

    1992-01-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1989--March 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of metal fuel and blanket materials of the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned water waste stream generated in production of 2,4,6-trinitrotoluene. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  20. Nuclear Technology Programs semiannual progress report, April-- September 1990

    SciTech Connect

    Harmon, J.E.

    1992-06-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  1. Nuclear technology programs. Semiannual progress report, April--September 1991

    SciTech Connect

    Not Available

    1993-07-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April through September 1991. These programs involve R & D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  2. Nuclear Technology Programs semiannual progress report, October 1990--March 1991

    SciTech Connect

    1992-12-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1990--March 1991. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transpose of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  3. Nuclear Technology Programs semiannual progress report, April-- September 1990

    SciTech Connect

    Harmon, J.E.

    1992-06-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1990. These programs involve R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor, and the properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories.

  4. Ceramic Technology Project. Semiannual progress report, April 1991--September 1991

    SciTech Connect

    Not Available

    1992-03-01

    The Ceramic Technology Project was developed by the USDOE Office of Transportation Systems (OTS) in Conservation and Renewable Energy. This project, part of the OTS`s Materials Development Program, was developed to meet the ceramic technology requirements of the OTS`s automotive technology programs. Significant accomplishments in fabricating ceramic components for the USDOE and NASA advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. These programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and data base and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially. A five-year project plan was developed with extensive input from private industry. In July 1990 the original plan was updated through the estimated completion of development in 1993. The objective is to develop the industrial technology base required for reliable ceramics for application in advanced automotive heat engines. The project approach includes determining the mechanisms controlling reliability, improving processes for fabricating existing ceramics, developing new materials with increased reliability, and testing these materials in simulated engine environments to confirm reliability. Although this is a generic materials project, the focus is on the structural ceramics for advanced gas turbine and diesel engines, ceramic bearings and attachments, and ceramic coatings for thermal barrier and wear applications in these engines. To facilitate the rapid transfer of this technology to US industry, the major portion of the work is being done in the ceramic industry, with technological support from government laboratories, other industrial laboratories, and universities.

  5. Environmentally assisted cracking in light water reactors. Semiannual report, July 1998-December 1998.

    SciTech Connect

    Chopra, O. K.; Chung, H. M.; Gruber, E. E.; Kassner, T. F.; Ruther, W. E.; Shack, W. J.; Smith, J. L.; Soppet, W. K.; Strain; R. V.

    1999-10-01

    This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from July 1998 to December 1998. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of primary pressure boundary materials, (b) irradiation-assisted stress corrosion cracking of austenitic stainless steels (SSs), and (c) EAC of Alloys 600 and 690. Fatigue tests have been conducted to determine the crack initiation and crack growth characteristics of austenitic SSs in LWR environments. Procedures are presented for incorporating the effects of reactor coolant environments on the fatigue life of pressure vessel and piping steels. Slow-strain-rate tensile tests and posttest fractographic analyses were conducted on several model SS alloys irradiated to {approx}0.3 and 0.9 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) in helium at 289 C in the Halden reactor. The results have been used to determine the influence of alloying and impurity elements on the susceptibility of these steels to irradiation-assisted stress corrosion cracking. Fracture toughness J-R curve tests were also conducted on two heats of Type 304 SS that were irradiated to {approx}0.3 x 10{sup 21} n {center_dot} cm{sup -2} in the Halden reactor. Crack-growth-rate tests have been conducted on compact-tension specimens of Alloys 600 and 690 under constant load to evaluate the resistance of these alloys to stress corrosion cracking in LWR environments.

  6. Radiation Damage Assessment in the Reactor Pressure Vessel of the Integral Inherently Safe Light Water Reactor (I2S-LWR)

    NASA Astrophysics Data System (ADS)

    Flaspoehler, Timothy; Petrovic, Bojan

    2016-02-01

    One of the major limiting factors to nuclear reactors lifetime is the radiation-induced material damage in the Reactor Pressure Vessel (RPV). While older reactors were designed assuming a 40-year operating lifetime, new reactor designs are expected to have lifetimes up to 100 years. For safe operation, the integrity of the RPV must be ensured against significant material property changes. In this work, typical neutron damage indicators are calculated in the RPV of the I2S-LWR (Integral Inherently Safe LWR) Power Plant, including DPA (displacements per atom) and fast neutron fluence (>1 MeV and >0.1MeV). I2S-LWR is a PWR of integral design, which means that its wider downcomer provides additional shielding to the vessel. However, its higher core power density and longer lifetime may offset this advantage. In order to accurately represent the neutron environment for RPV damage assessment, a detailed model based on the preliminary design specifications of the I2S-LWR was developed to be used in the MAVRIC (Monaco with Automated Variance Reduction using Importance Calculations) sequence of the Scale6.1 code package. MAVRIC uses the CADIS (Consistent Adjoint-Driven Importance Sampling) methodology to bias a fixed-source MC (Monte Carlo) simulation. To establish the upper limit of a bounding envelope, a flat-source distribution was used. For the low limit, a center-peaked source was generated using the KENO-VI criticality sequence assuming uniform fresh fuel core. Results based on the preliminary I2S-LWR model show that DPA rates and fast fluence rates are conservatively 75% lower than in typical PWRs being operated currently in the US.

  7. Economic incentives and recommended development for commercial use of high burnup fuels in the once-through LWR fuel cycle

    SciTech Connect

    Stout, R.B.; Merckx, K.R.; Holm, J.S.

    1981-01-01

    This study calculates the reduced uranium requirements and the economic incentives for increasing the burnup of current design LWR fuels from the current range of 25 to 35 MWD/Kg to a range of 45 to 55 MWD/Kg. The changes in fuel management strategies which may be required to accommodate these high burnup fuels and longer fuel cycles are discussed. The material behavior problems which may present obstacles to achieving high burnup or to license fuel are identified and discussed. These problems are presented in terms of integral fuel response and the informational needs for commercial and licensing acceptance. Research and development programs are outlined which are aimed at achieving a licensing position and commercial acceptance of high burnup fuels.

  8. Semiannual report

    NASA Technical Reports Server (NTRS)

    1995-01-01

    This report summarizes research conducted at the Institute for Computer Applications in Science and Engineering in applied mathematics, fluid mechanics, and computer science during the period 1 Oct. 1994 - 31 Mar. 1995.

  9. Annual and semi-annual variability in the lower and upper atmosphere-ionosphere coupling processes by observations from Abastumani (41.75 N, 42.82 E)

    NASA Astrophysics Data System (ADS)

    Didebulidze, G. G.; Todua, M.; Javakhishvili, G.

    2015-12-01

    The importance of annual and semi-annual variability in the long-term variations of the ionosphere F2 layer parameters (NmF2, hmF2), the hydroxyl OH bands, the oxygen green 557.7 nm and red 630.0 line intensities observed from Abastumani is noted. The amplitudes of the semi-annual variations of these upper atmosphere-ionosphere parameters with maxima at equinoctial months depend on the value of the planetary geomagnetic Ap index, also observed in the inter-annual distribution of the total ozone content (TOC) and cloud covering over this region of South Caucasus. The observed dependence of semi-annual variations of these parameters on Ap index indicated possible influence of cosmic factors on the lower and upper atmosphere-ionosphere coupling processes.

  10. Database interfaces on NASA's heterogeneous distributed database system

    NASA Technical Reports Server (NTRS)

    Huang, Shou-Hsuan Stephen

    1989-01-01

    The syntax and semantics of all commands used in the template are described. Template builders should consult this document for proper commands in the template. Previous documents (Semiannual reports) described other aspects of this project. Appendix 1 contains all substituting commands used in the system. Appendix 2 includes all repeating commands. Appendix 3 is a collection of DEFINE templates from eight different DBMS's.

  11. Semiannual report to Congress on Inspector General audit reports, October 1, 1996--March 31, 1997

    SciTech Connect

    1997-05-01

    This is the Secretary of Energy`s sixteenth Semiannual Report to Congress submitted under the Inspector General Act of 1978, as amended. Pursuant to the Inspector General Act Amendments of 1988 (Public law 100-504), agency heads are to report to Congress on the status of final action taken on audit report recommendations. This report complements a report prepared by the Department`s Office of Inspector General that provides information on audit reports issued during the period and on the status of management decisions made on Inspector General audit reports. During the period covered by this report, October 1, 1996, through March 31, 1997, the Department took final action on 31 operational, financial, and preaward audit reports. At the end of the period 74 reports awaited final action. Final action was taken on 11 contract and financial assistance audits, leaving no reports requiring final action at the end of the period. This report has three sections. The first section outlines significant audit resolution and followup accomplishments achieved by the Department during the reporting period. The second section contains the statistical tables that illustrate the status of final action on Inspector General audit reports. The third lists the audit reports that are one year or more past management decision and have not completed final action. This section also provides the status of corrective actions on each of those reports.

  12. Semiannual report to Congress on Inspector General audit reports: April 1--September 30, 1997

    SciTech Connect

    1997-11-01

    This is the Secretary of Energy`s seventeenth Semiannual Report to Congress submitted under the Inspector General Act of 1978, as amended. Pursuant to the Inspector General Act Amendments of 1988 (Public Law 100-504), agency heads are to report to Congress on the status of final action taken on audit report recommendations. This report complements a report prepared by the Department`s Office of Inspector General that provides information on audit reports issued during the period and on the status of management decisions made on Inspector General audit reports. During the period covered by this report, April 1 through September 30, 1997, the Department took final action on 29 operational, financial, and preaward audit reports. At the end of the period 72 reports awaited final action. Final action was taken on five contract and financial assistance audits, leaving two reports requiring final action at the end of the period. This report has three sections. The first section outlines significant audit resolution and followup accomplishments achieved by the Department during the reporting period. The second section contains the statistical tables that illustrate the status of final action on Inspector General audit reports. The third lists the audit reports that are one year or more past management decision and have not completed final action. This section also provides the status of corrective actions on each of those reports.

  13. Semiannual report to Congress on Inspector General audit reports: October 1, 1995--March 31, 1996

    SciTech Connect

    1996-05-01

    This is the Secretary of Energy`s fourteenth Semiannual Report to Congress submitted under the Inspector General Act of 1978, as amended. Pursuant to the Inspector General Act Amendments of 1988 (Public Law 100-504), agency heads are to report to Congress on the status of final action taken on audit report recommendations. This report complements a report prepared by the Department`s Office of Inspector General that provides information on audit reports issued during the period and on the status of management decisions made on Inspector General audit reports. During the period covered by this report, October 1, 1995, through March 31, 1996, the Department took final action on 35 operational, financial, and preaward audit reports. At the end of the period 92 reports awaited final action. Final action was taken on two contract and financial assistance audits, leaving two reports requiring final action at the end of the period. This report has three sections. The first section outlines significant audit resolution and followup accomplishments achieved by the Department during the reporting period. The second section contains the statistical tables that illustrate the status of final action on Inspector General audit reports. The third lists the audit reports that are one year or more past management decision and have not completed final action. This section also provides the status of corrective actions on each of these reports.

  14. Degraded Piping Program: Phase 2, Semiannual report, April 1986-September 1986

    SciTech Connect

    Wilkowski, G.M.; Ahmad, J.; Barnes, C.R.; Brust, F.; Guerrieri, D.; Kiefner, J.; Kramer, G.; Kulhowvick, G.; Landow, M.; Marschall, C.W.

    1987-04-01

    Presented herein is the Fifth Semiannual Report of the US NRC's Degraded Piping Program - Phase II. The intent of this program is to experimentally validate and enhance available analytical methods for evaluating the mechanical behavior of nuclear power plant piping containing circumferentially-oriented defects. Fifty-one pipe experiments have been conducted to date. These and approximately 42 additional pipe experiments from other programs have been analyzed. In the analytical effort, a screening criterion has been developed to show when the net-section-collapse analysis is valid. This shows that even tough materials such as stainless steel can fail at less than net-section-collapse loads if the pipe diameter is sufficiently large. Numerous predictive J-estimation schemes have been evaluated and modified. A finite length surface cracked pipe estimation scheme has also been developed. Finite element analyses of specimens with welds suggest that the size of the weld relative to the specimen or structure size can affect the deformation J values. Supporting research efforts involve investigating geometry effects on J-R curves, as well as characterizing the material properties for each pipe tested.

  15. TFE Verification Program semiannual report for the period ending March 31, 1990

    SciTech Connect

    Not Available

    1990-07-01

    The objective of the semiannual progress report is to summarize the technical results obtained during the latest reporting period. The information presented herein will include evaluated test data, design evaluations, the results of analyses and the significance of results. The program objective is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. The TFE Verification Program builds directly on the technology and data base developed in the 1960s and early 1970s in an AEC/NASA program, and in the SP-100 program conducted in 1983, 1984 and 1985. In the SP-100 program, the attractive features of thermionic power conversion technology were recognized but concern was expressed over the lack of fast reactor irradiation data. The TFE Verification Program addresses this concern. 6 refs., 67 figs., 37 tabs.

  16. Fusion materials semiannual progress report for the period ending December 31, 1997

    SciTech Connect

    Burn, G.

    1998-03-01

    This is the twenty-third in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Materials Program is a national effort involving several national laboratories, universities, and industries. A large fraction of this work, particularly in relation to fission reactor experiments, is carried out collaboratively with their partners in Japan, Russia, and the European Union. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  17. Fusion materials semiannual progress report for the period ending December 31, 1996

    SciTech Connect

    1997-04-01

    This is the twenty-first in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The report covers the following topics: vanadium alloys; silicon carbide composite materials; ferritic/martensitic steels; copper alloys and high heat flux materials; austenitic stainless steels; insulating ceramics and optical materials; solid breeding materials; radiation effects, mechanistic studies and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; and irradiation facilities, test matrices, and experimental methods.

  18. Fusion reactor materials semiannual progress report for the period ending March 31, 1991

    SciTech Connect

    none,

    1991-07-01

    This is the tenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: alloy development for irradiation performance; damage analysis and fundamental studies; special purpose materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of program participants, and to provide a means of communicating the efforts of materials scientists to the test of the fusion community, both nationally and worldwide.

  19. Fusion Reactor Materials semiannual progress report for the period ending March 31, 1992

    SciTech Connect

    Not Available

    1992-07-01

    This is the twelfth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; and Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

  20. Fusion reactor materials: Semiannual progress report for period ending September 30, 1987

    SciTech Connect

    none,

    1988-03-01

    This is the third in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following technical progress reports: Alloy Development for Irradiation Performances; Damage Analysis and Fundamental Studies; Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

  1. Semi-annual technical report, September 30, 1999 - March 31, 2000

    SciTech Connect

    Schumacher, Dorin

    2000-04-01

    The Consortium for Plant Biotechnology Research, Inc. (CPBR) continues to operate according to objectives outlined in the proposal funded through the cooperative agreement. The italicized objectives below are addressed in this report, which covers the period September 30,1999 through March 31, 2000. (1) Update the research agenda using information obtained from member companies. (2) Identify and implement research projects that are deemed by industrial, scientific, and sponsoring agency evaluation to address significantly the problems and future of U.S. energy resources and that are relevant to the Department of Energy's mission. Specifically: (1) Announce research grants competition through a Request for Preproposals. (2) Conduct a dual-stage review process: Stage one--industrial and DOE review of preproposals; and Stage two--peer review, scientific consultants' review, DOE review of full proposals and Project Recommendation Committee evaluation and recommendation for funding. (3) Board of Directors approval of recommended awards. (4) Conduct ongoing project management. (5) Obtain semiannual, annual and final reports for evaluation of research goals and technology transfer. (6) Present reports to DOE.

  2. Semiannual report to Congress on Inspector General audit reports, October 1, 1997--March 31, 1998

    SciTech Connect

    1998-05-01

    This is the Secretary of Energy`s eighteenth Semiannual Report to Congress submitted under the Inspector General Act of 1978, as amended. Pursuant to the Inspector General Act Amendments of 1988 (Public Law 100-504), agency heads are to report to Congress on the status of final action taken on audit report recommendations. This report complements a report prepared by the Department`s Office of Inspector General that provides information on audit reports issued during the period and on the status of management decisions made on Inspector General audit reports. During the period covered by this report, October 1, 1997, through March 31, 1998, the Department took final action on 20 operational, financial, and preaward audit reports. At the end of the period 80 reports awaited final action. Final action was taken on one contract and financial assistance audit, leaving two reports requiring final action at the end of the period. This report has three sections. The first section outlines significant audit resolution and followup accomplishments achieved by the Department during the reporting period. The second section contains the statistical tables that illustrate the status of final action on Inspector General audit reports. The third lists the audit reports that are one year or more past management decision and have not completed final action. This section also provides the status of corrective actions on each of those reports.

  3. Semiannual report to Congress on Inspector General audit reports, April 1, 1995--September 30, 1995

    SciTech Connect

    1995-11-01

    This is the Secretary of Energy`s thirteenth Semiannual Report to Congress submitted under the Inspector General Act of 1978, as amended. Pursuant to the Inspector General Act Amendments of 1988 (Public Law 100-504), agency heads are to report to Congress on the status of final action taken on audit report recommendations. This report complements a report prepared by the Department`s Office of Inspector General that provides information on audit reports issued during the period and on the status of management decisions made on Inspector General audit reports. During the period covered by this report, April 1, 1995, through September 30, 1995, the Department took final action on 33 operational, financial, and preaward audit reports. At the end of the period 96 reports awaited final action. Final action was taken on 2 contract and financial assistance audits, leaving 2 reports requiring final action at the end of the period. This report has three sections. The first section outlines significant audit resolution and followup accomplishments achieved by the Department during the reporting period. The second section contains the statistical tables that illustrate the status of final action on Inspector General audit reports. The third lists the audit reports that are one year or more past management decision and have not completed final action. This section also provides the status of corrective actions on each of these reports.

  4. Fusion reactor materials semiannual progress report for the period ending September 30, 1989

    SciTech Connect

    none,

    1989-01-01

    This is the seventh in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following technical progress reports: alloy development for irradiation performance, damage analysis and fundamental studies, and special purpose materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

  5. Fusion materials semiannual progress report for the period ending March 31, 1995

    SciTech Connect

    1995-07-01

    This is the eighteenth in a series of semiannual technical progress reports on fusion materials. This report combines research and development activities which were previously reported separately in the following progress reports: {sm_bullet} Alloy Development for Irradiation Performance. {sm_bullet} Damage Analysis and Fundamental Studies. {sm_bullet} Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide. This report has been compiled and edited under the guidance of A.F. Rowcliffe by Gabrielle Burn, Oak Ridge National Laboratory. Their efforts, and the efforts of the many persons who made technical contributions, are gratefully acknowledged.

  6. Interaction of the quasi-biennial oscillation and stratopause semiannual oscillation

    NASA Astrophysics Data System (ADS)

    Dunkerton, Timothy J.; Delisi, Donald P.

    1997-11-01

    Analysis of rawinsonde and rocketsonde data at Ascension Island (7.6°S, 14.4°W) and Kwajalein (8.7°N, 167°E) in 1962-1991 suggests that the quasi-biennial oscillation (QBO) in the middle stratosphere is synchronized with the seasonal cycle and that descending westerly phases of the stratopause semiannual oscillation (SAO) are strongly influenced by the underlying QBO. The effect of the seasonal cycle on the QBO in the middle stratosphere is revealed in two, perhaps unrelated, observations: first, a tendency for deseasonalized QBO westerly maxima to occur in local winter (or to avoid local summer); second, a smooth, uninterrupted connection between descending SAO westerly shear zones and the formation of a new QBO westerly shear zone aloft. The timing of deseasonalized QBO westerly maxima in the middle stratosphere allows a simple composite of 2- and 3-year cycles to be constructed from the data, illustrating the effect of the QBO on descending westerly phases of the stratopause SAO.

  7. Preparing for a Semiannual IACUC Inspection of a Satellite Zebrafish (Danio rerio) Facility

    PubMed Central

    Koerber, Amy S; Kalishman, Jennifer

    2009-01-01

    Institutions worldwide have experienced a rapid growth in the use of zebrafish as a research model for a variety of molecular and genetic studies of vertebrate development. This expansion in zebrafish research essentially has outpaced the establishment of specific recommendations for the care and use of fish in research. In some cases, this situation has created a dilemma where an Institutional Animal Care and Use Committee, which is responsible for oversight of vertebrate animal research, is not fully prepared to undertake this role for a decentralized zebrafish facility. IACUC inspectors will be more equipped to ask pertinent questions by understanding the basic principles of zebrafish health and facility management. Concurrently, zebrafish facility managers can contribute to the progress of a semiannual facility inspection by maintaining fully accessible operating records. In the context of presenting a well-established and useful model of zebrafish management and recordkeeping to the zebrafish facility operator, the information we present here also prepares a potential IACUC inspector to conduct a constructive and positive inspection. PMID:19245754

  8. TFE Verification Program. Semiannual report for the period ending March 31, 1993

    SciTech Connect

    Not Available

    1993-05-01

    The objective of the semiannual progress report is to summarize the technical results obtained during the latest reporting period. The information presented herein will include evaluated test data, design evaluations, the results of analyses and the significance of results. The program objective is to demonstrate the technology readiness of a TFE (thermionic fuel element) suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. The TFE Verification Program builds directly on the technology and data base developed in the 1960s and early 1970s in an AEC/NASA program, and in the SP-100 program conducted in 1983, 1984 and 1985. In the SP-100 program, the attractive features of thermionic power conversion technology were recognized but concern was expressed over the lack of fast reactor irradiation data. The TFE Verification Program addresses this concern.

  9. Semiannual report to Congress on Inspector General Audit Reports, October 1, 1994--March 31, 1995

    SciTech Connect

    1995-05-01

    This is the Secretary of Energy`s twelfth Semiannual Report to Congress submitted under the Inspector General Act of 1978, as amended. Pursuant to the Inspector General Act Amendments of 1988 (Public Law 100-504), agency heads are to report to Congress on the status of final action taken on audit report recommendations. This report complements a report prepared by the Department`s Office of Inspector General that provides information on audit reports issued during the period and on the status of management decisions made on Inspector General audit reports. During the period covered by this report, October 1, 1994 through March 31, 1995, the Department took final action on 32 operational, financial, and preaward audit reports. At the end of the period 90 reports awaited final action. Final action was taken on four contract and financial assistance audits, leaving four reports requiring final action at the end of the period. This report has three sections. The first section outlines significant audit resolution and followup accomplishments achieved by the Department during the reporting period. The second section contains the statistical tables that illustrate the status of final action on Inspector General audit reports. The third lists the audit reports that are one year or more past management decision and have not completed final action. This section also provides the status of corrective actions on each of these reports.

  10. The semiannual variation of geomagnetic activity: Phases and profiles for 130 years of aa data

    NASA Astrophysics Data System (ADS)

    Cliver, E. W.; Kamide, Y.; Ling, A. G.

    2001-05-01

    We determined the phases of the maxima (spring, fall) and minima (summer, winter) in the curve of smoothed daily averages of the aa geomagnetic index, available from 1868-1998. The dates we obtained are consistent with the equinoctial hypothesis which has aberration-adjusted theoretical maxima on 25 March (experimentally determined to be 27 March) and 27 September (27 September) and minima on 26 June (26 June) and 26 December (27 December). We also show that the overall shape of the modulation curve throughout the year (broad minima, narrow peaks) bears greater fidelity (r = -0.96) to the solar declination D (the controlling angle for the seasonal variation under the equinoctial hypothesis) than to the solar B angle (r = 0.83; axial hypothesis) or the solar P angle (r = 0.80; Russell-McPherron effect). Lastly, a three-parameter fit of the smoothed annual variation of the aa data with a function consisting of the sum of the smoothed yearly curves for the D, B, and P angles yielded an amplitude of 0.58 for the D component vs. 0.20 for B and 0.16 for P. Generally similar results for each of these analyses (timing, shape, relative contributions) were obtained for shorter intervals of data for the ap and am indices. We conclude that the semiannual modulation of average values of mid-latitude range indices such as aa and ap is primarily controlled by the equinoctial hypothesis.

  11. NRC regulatory agenda: Semiannual report, January--June 1995. Volume 14, Number 1

    SciTech Connect

    1995-09-01

    The Regulatory Agenda is a semiannual compilation of all rules on which the NRC has recently completed action, or has proposed action, or is considering action, and of all petitions for rulemaking that the NRC has received that are pending disposition. The agenda consists of two sections that have been updated through June 30, 1995. Section 1, ``Rules,`` includes (A) rules on which final action has been taken since December 30, 1994, the closing date of the last NRC Regulatory Agenda; (B) rules published previously as proposed rules on which the Commission has not taken final action; (C) rules published as advance notices of proposed rulemaking for which neither a proposed nor final rule has been issued; and (D) unpublished rules on which the NRC expects to take action. Section 2, ``Petitions for Rulemaking,`` includes (A) petitions denied or incorporated into final rules since December 30, 1994; (B) petitions incorporated into proposed rules; (C) petitions pending staff review, and (D) petitions with deferred action.

  12. Fusion reactor materials semiannual progress report for period ending September 30, 1990

    SciTech Connect

    Not Available

    1991-04-01

    This is the ninth in series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following technical progress reports: Alloy Development of Irradiation Performance; Damage Analysis and Fundamental Studies; and Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

  13. Environmentally assisted cracking in light water reactors : semiannual report, July 2000 - December 2000.

    SciTech Connect

    Chopra, O. K.; Chung, H. M.; Gruber, E. E.; Shack, W. J.; Soppet, W. K.; Strain, R. V.; Energy Technology

    2002-04-01

    This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from July 2000 to December 2000. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of primary pressure boundary materials, (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steels (SSs), and (c) EAC of Alloys 600 and 690. The fatigue strain-vs.-life data are summarized for the effects of various material, loading, and environmental parameters on the fatigue lives of carbon and low-alloy steels and austenitic SSs. Effects of the reactor coolant environment on the mechanism of fatigue crack initiation are discussed. Two methods for incorporating the effects of LWR coolant environments into the ASME Code fatigue evaluations are presented. Slow-strain-rate tensile tests and posttest fractographic analyses were conducted on several model SS alloys irradiated to {approx}0.9 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) in He at 289 C in the Halden reactor. The results were used to determine the influence of alloying and impurity elements on the susceptibility of these steels to IASCC. A fracture toughness J-R curve test was conducted on a commercial heat of Type 304 SS that was irradiated to {approx}2.0 x 10{sup 21} n {center_dot} cm{sup -2} in the Halden reactor. The results were compared with the data obtained earlier on steels irradiated to 0.3 and 0.9 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) (0.45 and 1.35 dpa). Neutron irradiation at 288 C was found to decrease the fracture toughness of austenitic SSs. Tests were conducted on compact-tension specimens of Alloy 600 under cyclic loading to evaluate the enhancement of crack growth rates in LWR environments. Then, the existing fatigue crack growth data on Alloys 600 and 690 were analyzed to establish the effects of temperature, load ratio, frequency, and stress intensity range

  14. LMBFR and LWR in-core thermal-hydraulic codes: the state-of-the-art and research and development needs

    SciTech Connect

    Khan, E.U.; Coomes, E.P.; Rowe, D.S.; Trent, D.S.

    1981-04-01

    A review of analytical design methods used for predicting reactor core flow and temperature distributions is presented with emphasis on LMFBR's. The paper also briefly describes and contrasts the methods used for LWR's. These methods are global analysis, subchannel analysis, distributed parameter, and hybrid analysis. The evolution of the local and subchannel analysis methods is presented. Data used for code validation are also presented. Current research and development needs are identified and discussed. Areas identified for future research and development include methods and expermental data for analysis of distorted bundles and natural convection. Methods that have been developed for predicting the safety performance of LMFBR's and LWR's are not within the scope of this paper.

  15. MHD Technology Transfer, Integration and Review Committee. Seventh semi-annual status report, April 1991--September 1991

    SciTech Connect

    Not Available

    1993-02-01

    This seventh semi-annual status report of the MHD Technology Transfer, Integration and Review Committee (TTIRC) summarizes activities of the TTIRC during the period April 1991 through September 1991. It includes a summary and minutes of the General Committee meeting, progress summaries of ongoing POC contracts, discussions pertaining to technical integration issues in the POC program, and planned activities for the next six months. The meeting included test plan with Western coal, seed regeneration economics, power management for the integrated topping cycle and status of the Clean Coal Technology Proposal activities. Appendices cover CDIF operations HRSR development, CFFF operations etc.

  16. U.S. Department of Education, Office of the Inspector General Semiannual Report to Congress: No. 50, October 1, 2004-March 31, 2005

    ERIC Educational Resources Information Center

    US Department of Education, 2005

    2005-01-01

    This document presents the 50th semiannual report on the activities and accomplishments of the Office of Inspector General (OIG), U.S. Department of Education (Department). During this reporting period, the OIG issued 123 audits, inspection reports and memoranda, and closed 95 investigations. As detailed in this report, this office continues to…

  17. Semi-Annual Report to Congress: April 1, 1981-September 30, 1981. No. 3. (Submitted Pursuant to Public Law 95-452).

    ERIC Educational Resources Information Center

    Office of Inspector General (ED), Washington, DC.

    The Office of Inspector General (OIG), mandated to provide audit, investigation, fraud detection and prevention, and some security services to the U.S. Department of Education, presents its third semi-annual report in this document. OIG audit activities are recounted in the first section, which details audit accomplishments and highlights audits…

  18. Semi-Annual Report to Congress: April 1, 1984-September 30, 1984. No. 9. (Submitted Pursuant to Public Law 95-452).

    ERIC Educational Resources Information Center

    Office of Inspector General (ED), Washington, DC.

    This ninth semiannual report issued by the United States Department of Education's Office of Inspector General (OIG) summarizes the activities and accomplishments of that office during a 6-month period ending September 30, 1984. A condensation of audits of Department of Education aid programs presents statistics on OIG activities and the…

  19. Semi-Annual Report to Congress: October 1, 1982-March 31, 1983; No. 6. (Submitted pursuant to Public Law 95-452).

    ERIC Educational Resources Information Center

    Office of Inspector General (ED), Washington, DC.

    The United States Department of Education (ED), Office of Inspector General (OIG), describes in its semiannual report its provisions for audit, investigation, fraud detection and prevention, as well as other activities. The first section reviews management improvement and preventive activities including recommended changes to legislation and…

  20. The development of coal-based technologies for Department of Defense Facilities. Semiannual technical progress report, March 28, 1993--September 27, 1993

    SciTech Connect

    Miller, B.G.; Morrison, J.L.; Sharifi, R.

    1993-12-17

    The US DOD, through an Interagency Agreement with the US DOE, has initiated a three-phase program with the Consortium for Coal-Water Slurry Fuel Technology, with the aim of decreasing DOD`s reliance on imported oil by increasing its use of coal. The program is being conducted as a cooperative agreement between the Consortium and DOE and the first phase of the program is underway. A team of researchers has been assembled from Penn State, ABB Combustion Engineering Systems (CE), AMAX Research and Development Center (AMAX), and Energy and Environmental Research Corporation (EER). These four organizations are the current members of the Consortium. Phase 1 activities are focused on developing clean, coal-based combustion technologies for the utilization of both micronized coal-water slurry fuels (MCWSFs) and dry, micronized coal (DMC) in fuel oil-designed industrial boilers. Phase 2 research and development activities will continue to focus on industrial boiler retrofit technologies by addressing emissions control and pre-combustion strategies for the utilization of high ash, high sulfur coals. Phase 3 activities will examine coal-based fuel combustion systems that cofire wastes. Each phase includes an engineering cost analysis and technology assessment. The activities and status of Phase 1 are described in this report. The objective of Phase 1 is to deliver fully engineered retrofit options for a fuel oil-designed watertube boiler located on a DOD installation to fire either MCWSF or DMC. This will be achieved through a program of the following tasks: (1) Coal Beneficiation and Preparation; (2) Combustion Performance Evaluation; (3) Engineering Design; (4) Engineering and Economic Analysis; and (5) Final Report/Submission of Design Package. Miscellaneous activities are reported. Activities planned for the next semiannual period are listed. The project schedule, with a description of milestones, is included.

  1. Advanced Processing Technology semiannual report, March--December 1991. Volume 1, Number 1

    SciTech Connect

    Adamson, M.; Kline-Simon, K.

    1991-12-31

    This first issue of the APT Semiannual Report focuses on APT`s defense-related technologies. These technologies are a continuation of the research, development, and engineering work performed by LLNLs Special Isotope Separation (SIS) Program. SIS was the first large-scale DOE venture that had environmentally conscious manufacturing processes and facilities as its deliverables. The objectives were to create a facility where the only outputs were either usable products or disposable wastes, and to comply with existing and anticipated federal, state, and local regulations related to safeguards, security, health and safety. To meet these objectives, revolutionary changes were needed in plutonium processing operations, chemistry, and equipment. New processes had to be developed that enhanced worker safety, minimized operator radiation dose, minimized waste at the point of generation, and provided for built-in recycling of residues. The SIS Program developed and demonstrated the technology (both chemistry and physics) necessary to provide plutonium with individual isotopic tailoring. This process made it possible to transform fuel-grade plutonium into weapon-grade material. However, due to the changing world political climate, the country`s need for plutonium to make new weapons has decreased dramatically. As a result, the planned SIS plutonium-separation plant will not be built. After the SIS Program was canceled in 199 1, Congress directed that the plutonium processing technologies under development for the SIS Program be redirected to the weapons program. APT took over the development of the innovative SIS technologies and is applying them to the development of a new, reconfigured Nuclear Weapons Complex -- Complex 21. ``Close Out of the SIS Program`` describes the completion of the SIS research and development work, and the transfer of key technologies to support this reconfiguration effort.

  2. Fast, quantitative, and nondestructive evaluation of hydrided LWR fuel cladding by small angle incoherent neutron scattering of hydrogen

    DOE PAGESBeta

    Yan, Y.; Qian, S.; Littrell, K.; Parish, C. M.; Plummer, L. K.

    2015-02-13

    A non-destructive neutron scattering method to precisely measure the uptake of hydrogen and the distribution of hydride precipitates in light water reactor (LWR) fuel cladding was developed. Zircaloy-4 cladding used in commercial LWRs was used to produce hydrided specimens. The hydriding apparatus consists of a closed stainless steel vessel that contains Zr alloy specimens and hydrogen gas. Following hydrogen charging, the hydrogen content of the hydrided specimens was measured using the vacuum hot extraction method, by which the samples with desired hydrogen concentration were selected for the neutron study. Optical microscopy shows that our hydriding procedure results in uniform distributionmore » of circumferential hydrides across the wall. Small angle neutron incoherent scattering was performed in the High Flux Isotope Reactor at Oak Ridge National Laboratory. This study demonstrates that the hydrogen in commercial Zircaloy-4 cladding can be measured very accurately in minutes by this nondestructive method over a wide range of hydrogen concentrations from a very small amount ( 20 ppm) to over 1000 ppm. The hydrogen distribution in a tube sample was obtained by scaling the neutron scattering rate with a factor determined by a calibration process using standard, destructive direct chemical analysis methods on the specimens. This scale factor will be used in future tests with unknown hydrogen concentrations, thus providing a nondestructive method for absolute hydrogen concentration determination.« less

  3. Fast, quantitative, and nondestructive evaluation of hydrided LWR fuel cladding by small angle incoherent neutron scattering of hydrogen

    SciTech Connect

    Yan, Y.; Qian, S.; Littrell, K.; Parish, C. M.; Plummer, L. K.

    2015-02-13

    A non-destructive neutron scattering method to precisely measure the uptake of hydrogen and the distribution of hydride precipitates in light water reactor (LWR) fuel cladding was developed. Zircaloy-4 cladding used in commercial LWRs was used to produce hydrided specimens. The hydriding apparatus consists of a closed stainless steel vessel that contains Zr alloy specimens and hydrogen gas. Following hydrogen charging, the hydrogen content of the hydrided specimens was measured using the vacuum hot extraction method, by which the samples with desired hydrogen concentration were selected for the neutron study. Optical microscopy shows that our hydriding procedure results in uniform distribution of circumferential hydrides across the wall. Small angle neutron incoherent scattering was performed in the High Flux Isotope Reactor at Oak Ridge National Laboratory. This study demonstrates that the hydrogen in commercial Zircaloy-4 cladding can be measured very accurately in minutes by this nondestructive method over a wide range of hydrogen concentrations from a very small amount ( 20 ppm) to over 1000 ppm. The hydrogen distribution in a tube sample was obtained by scaling the neutron scattering rate with a factor determined by a calibration process using standard, destructive direct chemical analysis methods on the specimens. This scale factor will be used in future tests with unknown hydrogen concentrations, thus providing a nondestructive method for absolute hydrogen concentration determination.

  4. Processing of the GALILEOTM fuel rod code model uncertainties within the AREVA LWR realistic thermal-mechanical analysis methodology

    NASA Astrophysics Data System (ADS)

    Mailhe, P.; Barbier, B.; Garnier, Ch.; Landskron, H.; Sedlacek, R.; Arimescu, I.; Smith, M.; Bellanger, Ph.

    2014-06-01

    The availability of reliable tools and associated methodology able to accurately predict the LWR fuel behavior in all conditions is of great importance for safe and economic fuel usage. For that purpose, AREVA has developed its new global fuel rod performance code GALILEOTM along with its associated realistic thermal-mechanical analysis methodology. This realistic methodology is based on a Monte Carlo type random sampling of all relevant input variables. After having outlined the AREVA realistic methodology, this paper will be focused on the GALILEOTM code benchmarking process on its extended experimental database and the GALILEOTM model uncertainties assessment. The propagation of these model uncertainties through the AREVA realistic methodology is also presented. This GALILEOTM model uncertainties processing is of the utmost importance for accurate fuel design margin evaluation as illustrated on some application examples. With the submittal of Topical Report for GALILEOTM to the U.S. NRC in 2013, GALILEOTM and its methodology are on the way to be industrially used in a wide range of irradiation conditions.

  5. Issues for Conceptual Design of AFCF and CFTC LWR Spent Fuel Separations Influencing Next-Generation Aqueous Fuel Reprocessing

    SciTech Connect

    D. Hebditch; R. Henry; M. Goff; K. Pasamehmetoglu; D. Ostby

    2007-09-01

    In 2007, the U.S. Department of Energy (DOE) published the Global Nuclear Energy Partnership (GNEP) strategic plan, which aims to meet US and international energy, safeguards, fuel supply and environmental needs by harnessing national laboratory R&D, deployment by industry and use of international partnerships. Initially, two industry-led commercial scale facilities, an advanced burner reactor (ABR) and a consolidated fuel treatment center (CFTC), and one developmental facility, an advanced fuel cycle facility (AFCF) are proposed. The national laboratories will lead the AFCF to provide an internationally recognized R&D center of excellence for developing transmutation fuels and targets and advancing fuel cycle reprocessing technology using aqueous and pyrochemical methods. The design drivers for AFCF and the CFTC LWR spent fuel separations are expected to impact on and partly reflect those for industry, which is engaging with DOE in studies for CFTC and ABR through the recent GNEP funding opportunity announcement (FOA). The paper summarizes the state-of-the-art of aqueous reprocessing, gives an assessment of engineering drivers for U.S. aqueous processing facilities, examines historic plant capital costs and provides conclusions with a view to influencing design of next-generation fuel reprocessing plants.

  6. Regulatory instrument review: Aging management of LWR cables, containment and basemat, reactor coolant pumps, and motor-operated valves

    SciTech Connect

    Werry, E.V.; Somasundaram, S.

    1995-09-01

    The results of Stage 2 of the Regulatory Instrument Review are presented in this volume. Selected regulatory instruments, such as the Code of Federal Regulations (CFR), US Nuclear Regulatory Commission (NRC), Regulatory Guides, and ASME Codes, were investigated to determine the extent to which these regulations apply aging management to selected safety-related components in nuclear power plants. The Regulatory Instrument Review was funded by the NRC under the Nuclear Plant Aging Research (NPAR) program. Stage 2 of the review focused on four safety-related structures and components; namely, cables, containment and basemat, reactor coolant pumps, and motor-operated valves. The review suggests that the primary-emphasis of the regulatory instruments was on the design, construction, start-up, and operation of a nuclear power plant, and that aging issues were primarily addressed after an aging-related problem was recognized. This Stage 2 review confirms the results of the prior review; (see Regulatory Instrument Review: Management of Aging of LWR Major Safety-Related Components NUREG/CR-5490. The observations indicate that the regulations generally address management of age-related degradation indirectly. Specific age-related degradation phenomena frequently are dealt with in bulletins and notices or through generic issues, letters, etc. The major recommendation of this report, therefore, is that the regulatory instruments should more directly and explicitly address the aging phenomenon and the management of the age-related degradation process.

  7. Energy-efficiency testing activities of the Mobile Energy Laboratory - Semiannual Report: April 1, 1990, Through September 30, 1990

    SciTech Connect

    Parker, G.B.; Currie, J.W.

    1991-03-01

    This report summarizes energy-efficiency testing activities applying the Mobile Energy Laboratory (MEL) testing capabilities during the third and fourth quarters of fiscal year (FY) 1990. The MELs, developed by the US Department of Energy (DOE) Federal Energy Management Program (FEMP), are administered by Pacific Northwest Laboratory (PNL) and the Naval Energy and Environmental Support Activity (NEESA) for energy testing and energy conservation program support functions at federal facilities. MELs are equipped for the on-site evaluation of energy use efficiency. The using agencies principally fund MEL applications, while DOE/FEMP funds program administration and capability enhancement activities. This report fulfills the requirements established in Section 8 of the MEL Use Plan (PNL-6861) for semiannual reporting on energy-efficiency testing activities using the MEL capabilities. The MEL Use Committee, formally established in 1989, developed the MEL Use Plan and meets semiannually to establish priorities for energy-efficient testing applications using the MEL capabilities. This report describes the testing, test results, and suggested courses of action.

  8. Occultation studies of the Solar system. Semiannual status report, 1 July-31 December 1986

    SciTech Connect

    Millis, R. L.

    1987-02-01

    The planetary occultation program began at Lowell Observatory in 1973 with a worldwide campaign to observe mutual occultations and eclipses of the Galilean Satellites. Then the temperature profile of the Martian atmosphere was measured from data taken during the occultation of epsilon Geminorum, the Rings of Uranus were discovered as they occulted SAO 158687, and the dimensions of Pallas were measured when that minor planet occulted SAO 85009. In 1979 the present grant was initiated, providing funds for portable photometric instrumentation used to observe occultations by asteroids as well as by Uranus and Neptune. Software for predicting occultations of catalog stars by asteroids, planets, and comets was written in 1983. Lowell currently provides most of the available predictions for asteroid occultations. Realizing in 1983 that the lack of a high-quality astrometric telescope dedicated to occultation work was limiting progress, an 18-inch, F/8 lens was acquired and adapted to an existing mounting at Lowell. Although acquisition of the lens and implementation of the new telescope has been accomplished primarily with non-grant funds, the instrument makes a major contribution to occultation research.

  9. Propulsion system materials program. Semiannual progress report, October 1995--March 1996

    SciTech Connect

    Johnson, D.R.

    1996-07-01

    This portion of the program is identified as program element 1.0 within the work breakdown structure (WBS). It contains five subelements: (1) Monolithics, (2) Ceramic Composites, (3) Thermal and Wear Coatings, (4) Joining, and (5) Ceramic Machining. Ceramic research conducted within the Monolithics subelement currently includes work activities on low Cost Si{sub 3}N{sub 4} powder, green state ceramic fabrication, characterization, and densification, and on structural, mechanical, and physical properties of these ceramics. Research conducted within the Ceramic Composites subelement currently includes silicon nitride and oxide-based composites, and low expansion materials. Research conducted in the Thermal and Wear Coatings subelement is currently limited to oxide-based coatings and involves coating synthesis, characterization, and determination of the mechanical and physical properties of the coatings. Research conducted in the Joining subelement currently includes studies of processes to produce strong, stable joints between zirconia ceramics and iron-base alloys. As part of an expanded effort to reduce the cost of ceramic components, a new initiative in cost effective machining has been started. A major objective of the research in the Materials and Processing program element is to systematically advance the understanding of the relationships between ceramic raw materials such as powders and reactant gases, the processing variables involved in producing the ceramic materials, and the resultant microstructures and physical and mechanical properties of the ceramic materials. Success in meeting this objective will provide U.S. companies with new or improved ways for producing economical, highly reliable ceramic components for advanced heat engines.

  10. 40 CFR 63.136 - Process wastewater provisions-individual drain systems.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... Chemical Manufacturing Industry for Process Vents, Storage Vessels, Transfer Operations, and Wastewater... drain system shall be inspected initially, and semi- annually thereafter, for improper work practices... tightly fitting cap or plug shall be visually inspected initially, and semi-annually thereafter, to...

  11. 40 CFR 63.136 - Process wastewater provisions-individual drain systems.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... Chemical Manufacturing Industry for Process Vents, Storage Vessels, Transfer Operations, and Wastewater... drain system shall be inspected initially, and semi- annually thereafter, for improper work practices... tightly fitting cap or plug shall be visually inspected initially, and semi-annually thereafter, to...

  12. 40 CFR 63.136 - Process wastewater provisions-individual drain systems.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... Chemical Manufacturing Industry for Process Vents, Storage Vessels, Transfer Operations, and Wastewater... drain system shall be inspected initially, and semi- annually thereafter, for improper work practices... tightly fitting cap or plug shall be visually inspected initially, and semi-annually thereafter, to...

  13. 40 CFR 63.136 - Process wastewater provisions-individual drain systems.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... Chemical Manufacturing Industry for Process Vents, Storage Vessels, Transfer Operations, and Wastewater... drain system shall be inspected initially, and semi- annually thereafter, for improper work practices... tightly fitting cap or plug shall be visually inspected initially, and semi-annually thereafter, to...

  14. NEUTRON MULTIPLICITY AND ACTIVE WELL NEUTRON COINCIDENCE VERIFICATION MEASUREMENTS PERFORMED FOR MARCH 2009 SEMI-ANNUAL DOE INVENTORY

    SciTech Connect

    Dewberry, R.; Ayers, J.; Tietze, F.; Klapper, K.

    2010-02-05

    The Analytical Development (AD) Section field nuclear measurement group performed six 'best available technique' verification measurements to satisfy a DOE requirement instituted for the March 2009 semi-annual inventory. The requirement of (1) yielded the need for SRNL Research Operations Department Material Control & Accountability (MC&A) group to measure the Pu content of five items and the highly enrich uranium (HEU) content of two. No 14Q-qualified measurement equipment was available to satisfy the requirement. The AD field nuclear group has routinely performed the required Confirmatory Measurements for the semi-annual inventories for fifteen years using sodium iodide and high purity germanium (HpGe) {gamma}-ray pulse height analysis nondestructive assay (NDA) instruments. With appropriate {gamma}-ray acquisition modeling, the HpGe spectrometers can be used to perform verification-type quantitative assay for Pu-isotopics and HEU content. The AD nuclear NDA group is widely experienced with this type of measurement and reports content for these species in requested process control, MC&A booking, and holdup measurements assays Site-wide. However none of the AD HpGe {gamma}-ray spectrometers have been 14Q-qualified, and the requirement of reference 1 specifically excluded a {gamma}-ray PHA measurement from those it would accept for the required verification measurements. The requirement of reference 1 was a new requirement for which the Savannah River National Laboratory (SRNL) Research Operations Department (ROD) MC&A group was unprepared. The criteria for exemption from verification were: (1) isotope content below 50 grams; (2) intrinsically tamper indicating or TID sealed items which contain a Category IV quantity of material; (3) assembled components; and (4) laboratory samples. Therefore all (SRNL) Material Balance Area (MBA) items with greater than 50 grams total Pu or greater than 50 grams HEU were subject to a verification measurement. The pass

  15. Solar Rotational Periodicities and the Semiannual Variation in the Solar Wind, Radiation Belt, and Aurora

    NASA Technical Reports Server (NTRS)

    Emery, Barbara A.; Richardson, Ian G.; Evans, David S.; Rich, Frederick J.; Wilson, Gordon R.

    2011-01-01

    The behavior of a number of solar wind, radiation belt, auroral and geomagnetic parameters is examined during the recent extended solar minimum and previous solar cycles, covering the period from January 1972 to July 2010. This period includes most of the solar minimum between Cycles 23 and 24, which was more extended than recent solar minima, with historically low values of most of these parameters in 2009. Solar rotational periodicities from S to 27 days were found from daily averages over 81 days for the parameters. There were very strong 9-day periodicities in many variables in 2005 -2008, triggered by recurring corotating high-speed streams (HSS). All rotational amplitudes were relatively large in the descending and early minimum phases of the solar cycle, when HSS are the predominant solar wind structures. There were minima in the amplitudes of all solar rotational periodicities near the end of each solar minimum, as well as at the start of the reversal of the solar magnetic field polarity at solar maximum (approx.1980, approx.1990, and approx. 2001) when the occurrence frequency of HSS is relatively low. Semiannual equinoctial periodicities, which were relatively strong in the 1995-1997 solar minimum, were found to be primarily the result of the changing amplitudes of the 13.5- and 27-day periodicities, where 13.5-day amplitudes were better correlated with heliospheric daily observations and 27-day amplitudes correlated better with Earth-based daily observations. The equinoctial rotational amplitudes of the Earth-based parameters were probably enhanced by a combination of the Russell-McPherron effect and a reduction in the solar wind-magnetosphere coupling efficiency during solstices. The rotational amplitudes were cross-correlated with each other, where the 27 -day amplitudes showed some of the weakest cross-correlations. The rotational amplitudes of the > 2 MeV radiation belt electron number fluxes were progressively weaker from 27- to 5-day periods

  16. Short-Run Learning Dynamics under a Test-Based Accountability System: Evidence from Pakistan. Policy Research Working Paper 5465

    ERIC Educational Resources Information Center

    Barrera-Osorio, Felipe; Raju, Dhushyanth

    2010-01-01

    Low student learning is a common finding in much of the developing world. This paper uses a relatively unique dataset of five semiannual rounds of standardized test data to characterize and explain the short-term changes in student learning. The data are collected as part of the quality assurance system for a public-private partnership program…

  17. Identification of significant problems related to light water reactor piping systems

    SciTech Connect

    1980-07-01

    Work on the project was divided into three tasks. In Task 1, past surveys of LWR piping system problems and recent Licensee Event Report summaries are studied to identify the significant problems of LWR piping systems and the primary causes of these problems. Pipe cracking is identified as the most recurring problem and is mainly due to the vibration of pipes due to operating pump-pipe resonance, fluid-flow fluctuations, and vibration of pipe supports. Research relevant to the identified piping system problems is evaluated. Task 2 studies identify typical LWR piping systems and the current loads and load combinations used in the design of these systems. Definitions of loads are reviewed. In Task 3, a comparative study is carried out on the use of nonlinear analysis methods in the design of LWR piping systems. The study concludes that the current linear-elastic methods of analysis may not predict accurately the behavior of piping systems under seismic loads and may, under certain circumstances, result in nonconservative designs. Gaps at piping supports are found to have a significant effect on the response of the piping systems.

  18. Systematic technology evaluation program for SiC/SiC composite-based accident-tolerant LWR fuel cladding and core structures: Revision 2015

    SciTech Connect

    Katoh, Yutai; Terrani, Kurt A.

    2015-08-01

    Fuels and core structures in current light water reactors (LWR’s) are vulnerable to catastrophic failure in severe accidents as unfortunately evidenced by the March 2011 Fukushima Dai-ichi Nuclear Power Plant Accident. This vulnerability is attributed primarily to the rapid oxidation kinetics of zirconium alloys in a water vapor environment at very high temperatures. Zr alloys are the primary material in LWR cores except for the fuel itself. Therefore, alternative materials with reduced oxidation kinetics as compared to zirconium alloys are sought to enable enhanced accident-tolerant fuels and cores.

  19. F-Area Hazardous Waste Management Facility Semiannual Corrective Action Report, First and Second Quarter 1998, Volume I and II

    SciTech Connect

    Chase, J.

    1998-10-30

    This report addresses groundwater quality and monitoring data during first and second quarter 1998 for the F-Area Hazardous Waste management Facility (HWMF). The report fulfills the semiannual reporting requirements of Module III, Section D, of the 1995 Resource Conservation and Recovery Act (RCRA) Renewal Permit (South Carolina Hazardous and Mixed Waste Permit SC1-890-008-989), effective October 5, 1995 (hereafter referred to as the RCRA permit), and Section C of the Underground Injection Control Permit Application hereafter referred to as the Section C of the Underground Injection Control Permit Application (hereafter referred to as the UIC permit). The HWMF is described in the Introduction to Module III, Section C, of the RCRA permit.

  20. Semi-annual report of the Department of Energy, Office of Environmental Restoration and Waste Management, Quality Assessment Program

    SciTech Connect

    Sanderson, C.G.; Klusek, C.S.

    1993-07-01

    This Quality Assessment Program (QAP) is designed to test the quality of the environmental measurements being reported to the Department of Energy by its contractors. Since 1976, real or synthetic environmental samples that have been prepared and thoroughly analyzed at the Environmental Measurements Laboratory (EML) have been distributed at first quarterly and then semi-annually to these contractors. Their results, which are returned to EML within 90 days, are compiled with EML`s results and are reported back to the participating contractors 30 days later. A summary of the reported results is available to the participants 3 days after the reporting deadline via a modem-telephone connection to the EML computer. This report presents the results from the analysis of the 38th set of environmental quality assessment samples (QAP XXXVIII) that were received on or before June 2, 1993.