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1

Reduction of Sodium Nitrate Liquid Waste in Nuclear Reprocessing Plants  

SciTech Connect

Sodium nitrate solution has been generated from nuclear reprocessing plant as a result of neutralization of nitric acid. The sodium nitrate has been immobilized by bitumen, cement or other material in the site and waste packages have been produced. In order to reduce an environmental impact of the waste packages from the reprocessing plant, it is preferable to decompose nitrate ion to harmless gases such as nitrogen. A combination of formic acid and catalyst has been proposed for this purpose. But, the method is inadequate for a full decomposition of the nitrate ion. In addition, a mixture of NO and NO{sub 2} is produced during the reaction. Formaldehyde and hydrazine were selected as reductants and a combined use of Pd-Cu catalyst was tried to decompose the nitrate ion. As a result, the nitrate ion can almost entirely be decomposed without any generation of NO and NO{sub 2}. The test was conducted by 1 L flask. In case of formaldehyde, nitrate ion concentration can be reduced from 0.017 mol/l to 3.9x10{sup -4} mol/l. In case of hydrazine, nitrate concentration can be decreased from 2.8 mol/l to 9.5 x 10{sup -3} mol/l and ammonium ion is detected. The ammonium ion concentration in the final solution is 0.12 mol/l when 2.8 mol/l nitrate is reduced by hydrazine. Chemical reactions for formaldehyde on the Pd-Cu catalyst are estimated as combination of: NO{sub 3-} + HCHO = NO{sub 2-} + HCOOH; 2NO{sub 2-} + 3HCOOH = N{sub 2} + 3CO{sub 2} + 2H{sub 2}O + 2OH-; 4NO{sub 2-} + 3HCHO = 2N{sub 2} + 3CO{sub 2} + H{sub 2}O + 4OH-. the other hand, for hydrazine with the Pd-Cu catalyst: 3N{sub 2}H{sub 4} = 2NH{sub 3} + 2N{sub 2} + 3H{sub 2}; NO{sub 3-} + H{sub 2} = NO{sub 2-} + H{sub 2}O; NO{sub 2-} + NH{sub 3} = N{sub 2} + H{sub 2}O + OH-. The fundamental research shows that the combination usage of the Pd-Cu catalyst and formaldehyde or hydrazine is applicable for the reduction of nitrate liquid waste in the nuclear reprocessing plant. (authors)

Numata, M.; Mihara, S.; Kojima, S.; Ito, H. [JGC Corporation, Technologies Research Center, 2205, Narita-cho, Oarai-machi, Higashiibarakigun, Ibaraki Pref., 311-1313 (Japan); Kato, T. [JGC Corporation, Yokohama World Operation Center, 2-3-1, Minato Mirai, Nishi-ku, Yokohama, Kanagawa Pref., 220-6001 (Japan)

2006-07-01

2

Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants  

SciTech Connect

This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m/sup 3//MTU for no treatment to as low as 0.02 m/sup 3//MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs.

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01

3

10 CFR Appendix F to Part 50 - Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities  

Code of Federal Regulations, 2013 CFR

10 Energy 1 2013-01-01...Reprocessing Plants and Related Waste Management Facilities...Appendix F to Part 50 Energy NUCLEAR REGULATORY...The Department of Energy will take title to the radioactive waste material upon...

2013-01-01

4

HTGR reprocessing wastes and development needs  

Microsoft Academic Search

The objectives of this report are: to provide current estimates on quantities and composition of estimated HTGR reprocessing wastes; to compare these with similar data from LWR reprocessing for long-range waste management planning; to identify waste management development needs for HTGR wastes; and to compare these development needs with those of LWR reprocessing for possible consolidation of efforts to reduce

Pence

1976-01-01

5

HTGR reprocessing wastes and development needs  

Microsoft Academic Search

Characterization of the expected types and quantities of HTGR fuel reprocessing waste is not complete but is about as complete as is practicable at the present. The GA computer programs that predict the distribution of fission and activation products are presently undergoing an updating, and the new numbers will probably differ somewhat from those presented. But the differences are expected

Pence

1976-01-01

6

WATER REUSE IN A PAPER REPROCESSING PLANT  

EPA Science Inventory

This project was undertaken to determine the feasibility of water reuse in a paper reprocessing plant with the goal being to 'close the loop' or to demonstrate zero discharge technology. Before the project began, Big Chief Roofing Company at Ardmore, OK, was discharging 7.89 1/se...

7

International safeguards for reprocessing plants. Final report  

SciTech Connect

Proliferation risks inherent in reprocessing show the need to employ technically effective safeguards which can detect, with a high degree of assurance and on a timely basis, the diversion of significant quantities of fissionable material. A balance must be struck between what is technically feasible and effective and what is institutionally acceptable. Purpose of this report is to examine the several technical approaches to safeguards in light of their prospective acceptability. This study defines the economic, political and institutional nature of the safeguards problem; surveys generically alternative technical approaches to international safeguards including their effectiveness and relative development; characterizes the institutional implications and uncertainties associated with the acceptance and implementation of each technical alternative; and integrates these assessments into a set of overall judgments on feasible directions for reprocessing plant safeguards systems.

Kratzer, M.; Scheinman, L.; Sievering, N.; Wonder, E.; Lipman, D.; Immerman, W.; Elliott, J.M.; Crane, F.

1981-04-01

8

Behaviour and lifetime of electrolyzers electrolysing enriched tritium containing waste water from reprocessing  

Microsoft Academic Search

In order to define a representative waste composition for the experimental tests, the different streams of tritiated waste water which are expected to arise from the operation of the Wackersdorf reprocessing plant were identified as well as their chemical and radiochemical composition. Results obtained by pretreatment applying distillation and the decontamination factors thus achieved will be presented, as well as

H. J. Riedel; W. Ullrich

1988-01-01

9

Simplified PUREX process - perspective SNF reprocessing technology for the plant of the next generation  

Microsoft Academic Search

According to a planning building of NPP in Russia the accumulating of wastes will increase, so the foundation of reprocessing plant of new generation becomes required. The most prepared place for the new plant is the area of MCC (Krasnoyarskij region) that lies in the heart of Russian territory and far from oceans. Because of this the demands to the

V. V. Bondin; P. M. Gavrilov; Yu. A. Revenko; B. Ya. Zilberman; V. N. Romanovskij; Yu. S. Fedorov; A. Yu. Shadrin; E. G. Kudryavcev; A. V. Haperskaja

2007-01-01

10

Evaluation of radioactivity release at Rokkasho reprocessing plant  

SciTech Connect

JNFL have been conducting Active Test with spent fuels at Rokkasho Reprocessing Plant (RRP). In Active Test, the evaluation of radioactivity release to the environment (atmosphere and sea) was obtained. (authors)

Sugiyama, Hiroshi; Ishihara, Noriyuki; Maki, Akira [Engineering Section, Engineering Department, Reprocessing Plant, Reprocessing Business Division, Japan Nuclear Fuel Limited 4-108, Aza Okitsuke, Oaza Obuchi, Rokkasho-mura, Kamikita-gun, Aomori-ken, 039-3212 (Japan)

2007-07-01

11

10 CFR Appendix B to Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants  

...Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants...Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants...and components of the reactor. Nuclear power plants and fuel...

2014-01-01

12

10 CFR Appendix B to Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants  

Code of Federal Regulations, 2011 CFR

...Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants...Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants...and components of the reactor. Nuclear power plants and fuel...

2011-01-01

13

10 CFR Appendix B to Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants  

Code of Federal Regulations, 2012 CFR

...Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants...Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants...and components of the reactor. Nuclear power plants and fuel...

2012-01-01

14

10 CFR Appendix B to Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants  

Code of Federal Regulations, 2013 CFR

...Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants...Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants...and components of the reactor. Nuclear power plants and fuel...

2013-01-01

15

Process for recovery of palladium from nuclear fuel reprocessing wastes  

DOEpatents

Palladium is selectively removed from spent nuclear fuel reprocessing waste by adding sugar to a strong nitric acid solution of the waste to partially denitrate the solution and cause formation of an insoluble palladium compound. The process includes the steps of: (a) adjusting the nitric acid content of the starting solution to about 10 M; (b) adding 50% sucrose solution in an amount sufficient to effect the precipitation of the palladium compound; (c) heating the solution at reflux temperature until precipitation is complete; and (d) centrifuging the solution to separate the precipitated palladium compound from the supernatant liquid.

Campbell, D.O.; Buxton, S.R.

1980-06-16

16

Process for recovery of palladium from nuclear fuel reprocessing wastes  

DOEpatents

Palladium is selectively removed from spent nuclear fuel reprocessing waste by adding sugar to a strong nitric acid solution of the waste to partially denitrate the solution and cause formation of an insoluble palladium compound. The process includes the steps of: (a) adjusting the nitric acid content of the starting solution to about 10 M, (b) adding 50% sucrose solution in an amount sufficient to effect the precipitation of the palladium compound, (c) heating the solution at reflux temperature until precipitation is complete, and (d) centrifuging the solution to separate the precipitated palladium compound from the supernatant liquid.

Campbell, David O. (Oak Ridge, TN); Buxton, Samuel R. (Wartburg, TN)

1981-01-01

17

Solvent Distillation Studies for a Purex Reprocessing Plant  

Microsoft Academic Search

A distillation system has been developed for regeneration of Purex solvent and will be implemented for the first time in a reprocessing plant. The results are described and analyzed, with emphasis on laboratory experiments which were made with a radioactive plant solvent. Particularly the distillation provides a good separation of solvent degradation products, which was verified by measurements of interfacial

C. Ginisty; B. Guillaume

1990-01-01

18

Equipment specifications for an electrochemical fuel reprocessing plant  

SciTech Connect

Electrochemical reprocessing is a technique used to chemically separate and dissolve the components of spent nuclear fuel, in order to produce new metal fuel. There are several different variations to electrochemical reprocessing. These variations are accounted for by both the production of different types of spent nuclear fuel, as well as different states and organizations doing research in the field. For this electrochemical reprocessing plant, the spent fuel will be in the metallurgical form, a product of fast breeder reactors, which are used in many nuclear power plants. The equipment line for this process is divided into two main categories, the fuel refining equipment and the fuel fabrication equipment. The fuel refining equipment is responsible for separating out the plutonium and uranium together, while getting rid of the minor transuranic elements and fission products. The fuel fabrication equipment will then convert this plutonium and uranium mixture into readily usable metal fuel.

Hemphill, Kevin P [Los Alamos National Laboratory

2010-01-01

19

Status of radioiodine control for nuclear fuel reprocessing plants  

SciTech Connect

This report summarizes the status of radioiodine control in a nuclear fuel reprocessing plant with respect to capture, fixation, and disposal. Where possible, we refer the reader to a number of survey documents which have been published in the last four years. We provide updates where necessary. Also discussed are factors which must be considered in developing criteria for iodine control. For capture from gas streams, silver mordenite and a silver nitrate impregnated silica (AC-6120) are considered state-of-the-art and are recommended. Three aqueous scrubbing processes have been demonstrated: Caustic scrubbing is simple but probably will not give an adequate iodine retention by itself. Mercurex (mercuric nitrate-nitric acid scrubbing) has a number of disadvantages including the use of toxic mercury. Iodox (hyperazeotropic nitric acid scrubbing) is effective but employs a very corrosive and hazardous material. Other technologies have been tested but require extensive development. The waste forms recommended for long-term storage or disposal are silver iodide, the iodates of barium, strontium, or calcium, and silver loaded sorbents, all fixed in cement. Copper iodide in bitumen (asphalt) is a possibility but requires testing. The selection of a specific form will be influenced by the capture process used.

Burger, L.L.; Scheele, R.D.

1983-07-01

20

Active test of separation facility at Rokkasho reprocessing plant  

SciTech Connect

During the second and third steps of Active Test at Rokkasho Reprocessing Plant (RRP), the performances of the Separation Facility have been checked; (A) diluent washing efficiency, (B) plutonium stripping efficiency, (C) decontamination factor of fission products and (D) plutonium and uranium leakage into raffinate and spent solvent. Test results were equivalent to or better than expected. (authors)

Iseki, Tadahiro; Inaba, Makoto; Takahashi, Naoki [Separation Section, Plant Operation Department, Reprocessing Plant, Reprocessing Business Division, Japan Nuclear Fuel Limited, 4-108, Aza Okitsuke, Oaza Obuchi, Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan)

2007-07-01

21

10 CFR Appendix F to Part 50 - Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities  

Code of Federal Regulations, 2012 CFR

...Appendix F to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC...years following separation of fission products from the irradiated...of high-level radioactive fission product waste material will...to high-level radioactive fission product wastes...

2012-01-01

22

10 CFR Appendix F to Part 50 - Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities  

Code of Federal Regulations, 2011 CFR

...Appendix F to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC...years following separation of fission products from the irradiated...of high-level radioactive fission product waste material will...to high-level radioactive fission product wastes...

2011-01-01

23

Outline of human machine interface at Rokkasho reprocessing plant  

SciTech Connect

The Japan Nuclear Fuel Limited (JNFL) has been performing the active tests since the end of March, 2006, for its Rokkasho Reprocessing Plant using the spent fuels retrieved from the Light Water Reactors. At the early stage of the tests relatively low burn-up fuels have been used, and the burn-up will be increased at later stages until the start of commercial operation planned next year. The plant is operated from the main control room in the Control Building, where two types of operator consoles are located for plant monitoring and operation. The Operator Interface Station (OIS) driven by computer systems is chiefly used for instrumentation and control for production activities during normal operation. In addition to this, safety panels composed of hardware circuits are installed for nuclear safety functions such as criticality safety management, explosion protection, and confinement of radioactive materials. This paper outlines the Human Machine Interface features applied to the Rokkasho Reprocessing Plant. (authors)

Niioka, T.; Miyazaki, T.; Fujita, D.; Esashika, A.; Yoshida, Y.; Nakamura, W.; Tochigi, T. [Maintenance Dept., Instrumentation and Control Maintenance Section, Japan Nuclear Fuel Limited, 4-108, Aza Okitsuke, Kamikita-gun, Aomori, 039-3212 (Japan); Yoshimoto, A.; Yokoi, M. [Nuclear Energy Systems and Services Div., Toshiba Corporation, 1-1, Shibaura 1-Chome, Minato-ku, Tokyo, 105-8001 (Japan)

2006-07-01

24

Idaho Nuclear Technology and Engineering Center (INTEC) Sodium Bearing Waste - Waste Incidental to Reprocessing Determination  

SciTech Connect

U.S. Department of Energy Manual 435.1-1, Radioactive Waste Management, Section I.1.C, requires that all radioactive waste subject to Department of Energy Order 435.1 be managed as high-level radioactive waste, transuranic waste, or low-level radioactive waste. Determining the radiological classification of the sodium-bearing waste currently in the Idaho Nuclear Technology and Engineering Center Tank Farm Facility inventory is important to its proper treatment and disposition. This report presents the technical basis for making the determination that the sodium-bearing waste is waste incidental to spent fuel reprocessing and should be managed as mixed transuranic waste. This report focuses on the radiological characteristics of the sodiumbearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements.

Jacobson, Victor Levon

2002-08-01

25

Simplified PUREX process - perspective SNF reprocessing technology for the plant of the next generation  

SciTech Connect

According to a planning building of NPP in Russia the accumulating of wastes will increase, so the foundation of reprocessing plant of new generation becomes required. The most prepared place for the new plant is the area of MCC (Krasnoyarskij region) that lies in the heart of Russian territory and far from oceans. Because of this the demands to the volume of liquid LLW are very stringent. On the base of acquired Russian and international experience the development of the technology for the plant of the next (third) generation conditionally named Simplified PUREX process has begun. This technology must provide the reduction of liquid LLW formation and reduce the total value of reprocessing in comparison with the project of Russian plant RT-2. The building of Experimental-demonstration center (EDC) on MCC is proposed for testing and working through the main aims of new technology (both Simplified Purex and some other technologies).The Simplified Purex technology in comparison with classical liquid-extraction technology contains the substantial amount of thermo-chemical (dry) operations in the head of the process and it allows simplifying the next hydrometallurgical operations to reduce the SNF reprocessing value in general. (authors)

Bondin, V.V.; Gavrilov, P.M.; Revenko, Yu.A. [Mining-chemical combine Geleznogorsk, K. (Russian Federation); Zilberman, B.Ya.; Romanovskij, V.N.; Fedorov, Yu.S.; Shadrin, A.Yu. [Khlopin Radium Institute, Saint-Petersburg (Russian Federation); Kudryavcev, E.G.; Haperskaja, A.V. [Rosatom RF, Moscow (Russian Federation)

2007-07-01

26

Waste management system alternatives for treatment of wastes from spent fuel reprocessing  

SciTech Connect

This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases.

McKee, R.W.; Swanson, J.L.; Daling, P.M.; Clark, L.L.; Craig, R.A.; Nesbitt, J.F.; McCarthy, D.; Franklin, A.L.; Hazelton, R.F.; Lundgren, R.A.

1986-09-01

27

Current status of active tests at Rokkasho reprocessing plant  

SciTech Connect

At Rokkasho Reprocessing Plant (RRP), the first commercial reprocessing plant in Japan, the test operation has been carried out step by step with 'water and steam', 'chemical products', 'depleted uranium' and 'spent fuels' toward the planned start of the commercial operation. Water Test was performed as the final stage of plant construction work and functioning of each equipment was tested with water and steam. In Chemical Test the performance of each equipment and unit was verified with chemical products such as nitric acid. In Uranium Test with depleted uranium, function and performance of equipment such as the sharing machine and the dissolver was verified. All its tests were completed by 22 January 2006. Active Test has been performed with spent fuels for the verification of safety functions and performances of equipment and facilities related to the processing of fission products and of plutonium, which had not been tested previously. Active Test which has been in progress since 31 March 2006 is divided into 5 steps, and Step 1, Step 2 and Step 3 are already completed. (authors)

Nago, Toshihide; Ishihara, Noriyuki; Ohtou, Yoshihiro [Engineering Section, Engineering Department, Reprocessing Plant Reprocessing Business Division, Japan Nuclear Fuel Limited 4-108, Aza Okitsuke, Oaza Obuchi, Rokkasho-mura, Kamikita-gun, Aomori-ken, 039-3212 (Japan)

2007-07-01

28

Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant  

SciTech Connect

The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents.

Perkins, W.C.; Durant, W.S.; Dexter, A.H.

1980-12-01

29

On-Line Monitoring for Control and Safeguarding of Radiochemical Streams at Spent Fuel Reprocessing Plant  

SciTech Connect

Advanced techniques enabling enhanced safeguarding of the spent fuel reprocessing plants are urgently needed. Our approach is based on prerequisite that real time monitoring of the solvent extraction flowsheets provides unique capability to quickly detect unwanted manipulations with fissile isotopes present in the radiochemical streams during reprocessing activities. The methods used to monitor these processes must be robust and must be able to withstand harsh radiation and chemical environments. A new on-line monitoring system satisfying these requirements and featuring Raman spectroscopy combined with a Coriolis and conductivity probes, has been recently developed by our research team. It provides immediate chemical data and flow parameters of high-level radioactive waste streams with high brine content generated during retrieval activities from Hanford nuclear waste storage tanks. The nature of the radiochemical streams at the spent fuel reprocessing plant calls for additional spectroscopic information, which can be gained by the utilization of UV-vis-NIR capabilities. Raman and UV-vis-NIR spectroscopies are analytical techniques that have extensively been extensively applied for measuring the various organic and inorganic compounds including actinides. The corresponding spectrometers used under the laboratory conditions are easily convertible to the process-friendly configurations allowing remote measurements under the flow conditions. A fiber optic Raman probe allows monitoring of the high concentration species encountered in both aqueous and organic phases within the UREX suite of flowsheets, including metal oxide ions, such as uranyl, components of the organic solvent, inorganic oxo-anions, and water. The actinides and lanthanides are monitored remotely by UV-vis-NIR spectroscopy in aqueous and organic phases. In this report, we will present our recent results on spectroscopic measurements of simulant flowsheet solutions and commercial fuels available at PNNL. Measurements are performed at wide range of conditions adjusted to mimic UREX/PUREX processes and to demonstrate the applicability of Raman and vis-NIR spectroscopic analysis for actual dissolver feed solutions.

Bryan, Samuel A.; Levitskaia, Tatiana G.; Billing, Justin M.; Casella, Amanda J.; Johnsen, Amanda M.; Peterson, James M.

2009-10-06

30

MICROBIAL TRANSFORMATIONS OF RADIONUCLIDES RELEASED FROM NUCLEAR FUEL REPROCESSING PLANTS.  

SciTech Connect

Microorganisms can affect the stability and mobility of the actinides U, Pu, Cm, Am, Np, and the fission products Tc, I, Cs, Sr, released from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been investigated, we have only limited information on the effects of microbial processes. The mechanisms of microbial transformations of the major and minor actinides and the fission products under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed.

FRANCIS,A.J.

2006-10-18

31

Materials used in low-level liquid waste reprocessing/treatment studies at Oak Ridge National Laboratory  

SciTech Connect

The importance of effective waste management in the nuclear fuel cycle cannot be overestimated. At Oak Ridge National Laboratory (ORNL), development work in waste reprocessing and treatment includes the testing and use of various additives for the purpose of facilitating adherence to both process and regulatory performance criteria. Three waste reprocessing/treatment technologies and the associated materials are discussed in this paper: (1) suspension and transfer of sludge from waste storage tanks; (2) treatment to render a waste in compliance with regulatory requirements; and (3) fluoride-rich waste reprocessing. 7 refs., 3 figs.

McDaniel, E.W.; Weeren, H.O.; Delzer, D.B.; Sams, T.L.; Tallent, O.K.

1987-01-01

32

Control of radio-iodine at the German reprocessing plant WAK during operation and after shutdown  

SciTech Connect

During 20 years of operation 207 metric tons of oxide fuel from nuclear power reactors with 19 kg of iodine-129 had been reprocessed in the WAK plant near Karlsruhe. In January 1991 the WAK Plant was shut down. During operation iodine releases of the plant as well as the iodine distribution over the liquid and gaseous process streams had been determined. Most of the iodine is evolved into the dissolver off-gas in volatile form. The remainder is dispersed over many aqueous, organic and especially gaseous process and waste streams. After shut down of the plant in January 1991, iodine measurements in the off-gas streams have been continued up to now. Whereas the iodine-129 concentration in the dissolver off-gas dropped during six months after shutdown by three orders of magnitude, the iodine concentrations in the vessel ventilation system of the PUREX process and the cell vent system decreased only by a factor of 10 during the same period. Iodine-129 releases of the liquid high active waste storage tanks did not decrease distinctly. The removal efficiencies of the silver impregnated iodine filters in the different off-gas streams of the WAK plant depend on the iodine concentration in the off-gas. The reason of the observed dependence of the DF on the iodine-129 concentration might be due to the presence of organic iodine compounds which are difficult to remove. 13 refs., 3 figs.

Herrmann, F.J.; Herrmann, B.; Kuhn, K.D. [Wiederaufarbeitungsanlage Karlsruhe (Germany)] [and others

1997-08-01

33

Material balance areas and frequencies for large reprocessing plants  

SciTech Connect

It has long been recognized that facilities with a large nuclear material throughput will probably not meet the International Atomic Energy Agency (IAEA) goal for detecting trickle diversion of plutonium over periods of about one year. The reason is that measurement errors for plutonium concentration and for liquid volume are often approximately relative over a fairly wide range of true values. Therefore, large throughput facilities will tend to have large uncertainties assigned to their annual throughput. By the same argument, if frequent balances are performed over small material balance areas, then the uncertainty associated with each balance period for each balance area will be small. However, trickle diversion would still be difficult to detect statistically. Because the IAEA will soon be faced with safeguarding a new large-scale reprocessing plant in Japan, it is timely to reconsider the advantages and disadvantages of performing frequent material balances over small balance areas (individual tanks where feasible). Therefore, in this paper the authors present some simulation results to study the effect of balance frequency on loss detection probability, and further simulation results to study possibilities introduced by choosing small balance areas. They conclude by recommending frequent balances over small areas.

Burr, T. [Los Alamos National Lab., NM (United States). Safeguards Systems Group

1994-08-01

34

Study on release and transport of aerial radioactive materials in reprocessing plants  

SciTech Connect

The release and transport characteristics of radioactive materials at a boiling accident of the high active liquid waste (HALW) in a reprocessing plant have been studied for improving experimental data of source terms of the boiling accident. In the study, a heating test and a thermogravimetry and differential thermal analysis (TG-DTA) test were conducted. In the heating test using a simulated HALW, it was found that ruthenium was mainly released into the air in the form of gas and that non-volatile elements were released into the air in the form of mist. In the TG-DTA test, the rate constants and reaction heat of thermal decomposition of ruthenium nitrosyl nitrate were obtained from TG and DTA curves. (authors)

Amano, Y.; Tashiro, S.; Uchiyama, G.; Abe, H.; Yamane, Y.; Yoshida, K. [Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki, 319-1195 (Japan); Kodama, T. [Japan Nuclear Fuel Ltd., 4-108 Okitsuke, Obuchi, Rokkasho-mura, Kamikita-gun, Aomori, 039-3212 (Japan)

2013-07-01

35

The transfer of reprocessing wastes from north-west Europe to the Arctic  

Microsoft Academic Search

The discharge of radioactive waste, from nuclear fuel reprocessing facilities, into the coastal waters of north-west Europe has resulted in a significant increase in the inventories of a number of artificial radionuclides in the North Atlantic. Radiocaesium, 90Sr and 99Tc, which behave conservatively in seawater, have been used widely as tracers of water movement through the North Sea, Norwegian Coastal

Peter Kershaw; Amanda Baxter

1995-01-01

36

(Design of nuclear fuel reprocessing plants, Neuherberg, Munich, Hannover and Wackersdorf, FRG, July 5--19, 1989): Foreign trip report  

SciTech Connect

The proposed fuel reprocessing site was characterized as to meteorological and hydrological characteristics and population geographical distribution. Data were gathered characterizing the fuel reprocessing plant licensing procedure currently used in the FRG. Comparisons were made of fuel reprocessing in the FRG, France, and Great Britain.

Fields, D.E.

1989-07-24

37

Control of RadioIodine at the German Reprocessing Plant WAK during Operation and after Shutdown  

Microsoft Academic Search

During 20 years of operation 207 metric tons of oxide fuel from nuclear power reactors with 19 kg of iodine-129 had been reprocessed in the WAK plant near Karlsruhe. In January 1991 the WAK Plant was shut down. During operation iodine releases of the plant as well as the iodine distribution over the liquid and gaseous process streams had been

F. J. Herrmann; B. Herrmann; K. D. Kuhn; A. van Schoor; M. Weishaupt; Wiederaufarbeitungsanlage Karlsruhe; J. Furrer; W. Knoch

38

Hanford Waste Vitrification Plant  

SciTech Connect

The Hanford Waste Vitrification Plant (HWVP) is being designed to immobilize pretreated Hanford high-level waste and transuranic waste in borosilicate glass contained in stainless steel canisters. Testing is being conducted in the HWVP Technology Development Project to ensure that adapted technologies are applicable to the candidate Hanford wastes and to generate information for waste form qualification. Empirical modeling is being conducted to define a glass composition range consistent with process and waste form qualification requirements. Laboratory studies are conducted to determine process stream properties, characterize the redox chemistry of the melter feed as a basis for controlling melt foaming and evaluate zeolite sorption materials for process waste treatment. Pilot-scale tests have been performed with simulated melter feed to access filtration for solids removal from process wastes, evaluate vitrification process performance and assess offgas equipment performance. Process equipment construction materials are being selected based on literature review, corrosion testing, and performance in pilot-scale testing. 3 figs., 6 tabs.

Larson, D.E.; Allen, C.R. (Pacific Northwest Lab., Richland, WA (United States)); Kruger, O.L.; Weber, E.T. (Westinghouse Hanford Co., Richland, WA (United States))

1991-10-01

39

Degradation and stabilization of polyolefins from municipal plastic waste during multiple extrusions under different reprocessing conditions  

Microsoft Academic Search

The recyclability of the two main polyolefins from municipal plastic waste, HDPE and PP, was evaluated. The HDPE\\/PP blend (90:10)—the most commonly found weight proportion—was extruded three times at conventional (150–180 °C) and high (210–250 °C) reprocessing temperatures. The behavior of degradation was evaluated by infrared spectroscopy measurements (carbonyl index), melt flow index (MFI), capillary rheometry and differential scanning calorimetry (oxidation induction

A. S. F Santos; J. A. M Agnelli; D. W Trevisan; S Manrich

2002-01-01

40

Conservatism in effective dose calculations for accident events involving fuel reprocessing waste tanks.  

PubMed

Conservatism in the calculation of the effective dose following an airborne release from an accident involving a fuel reprocessing waste tank is examined. Within the regulatory constraints at the Hanford Site, deterministic effective dose calculations are conservative by at least an order of magnitude. Deterministic calculations should be used with caution in reaching decisions associated with required safety systems and mitigation philosophy related to the accidental release of airborne radioactive material to the environment. PMID:21617391

Bevelacqua, J J

2011-07-01

41

Removal efficiency of silver impregnated filter materials and performance of iodie filters in the off-gas of the Karlsruhe reprocessing plant WAK  

SciTech Connect

An almost quantitative retention of iodine is required in reprocessing plants. For the iodine removal in the off-gas streams of a reprocessing plant various sorption materials had been tested under realistic conditions in the Karlsruhe reprocessing plant WAK in cooperation with the Karlsruhe research center FZK. The laboratory results achieved with different iodine sorption materials justified long time performance tests in the WAK Plant. Technical iodine filters and sorption materials for measurements of iodine had been tested from 1972 through 1992. This paper gives an overview over the most important results, Extended laboratory, pilot plant, hot cell and plant experiences have been performed concerning the behavior and the distribution of iodine-129 in chemical processing plants. In a conventional reprocessing plant for power reactor fuel, the bulk of iodine-129 and iodine-127 is evolved into the dissolver off-gas. The remainder is dispersed over many aqueous, organic and gaseous process and waste streams of the plant. Iodine filters with silver nitrate impregnated silica were installed in the dissolver off-gas of the Karlsruhe reprocessing plant WAK in 1975 and in two vessel vent systems in 1988. The aim of the Karlsruhe iodine research program was an almost quantitative evolution of the iodine during the dissolution process to remove as much iodine with the solid bed filters as possible. After shut down of the WAK plant in December 1990 the removal efficiency of the iodine filters at low iodine concentrations had been investigated during the following years. 12 refs., 2 figs., 2 tabs.

Herrmann, F.J.; Herrmann, B.; Hoeflich, V. [Wiederaufarbeitungsanlage Karlsruhe (Germany)] [and others

1997-08-01

42

Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant  

SciTech Connect

The Safety Technology Group is developing methodology that can be used to assess the risk of operating a plant to reprocess spent nuclear fuel. As an early step in the methodology, a preliminary hazards analysis identifies safety-related incidents. In the absence of appropriate safety features, these incidents could lead to significant consequences and risk to onsite personnel or to the public. This report is a compilation of potential safety-related incidents that have been identified in studies at SRL and in safety analyses of various commercially designed reprocessing plants. It is an expanded revision of the version originally published as DP-1558, Published December 1980.

Durant, W.S.; Perkins, W.C.; Lee, R.; Stoddard, D.H.

1982-05-20

43

Materials management in an internationally safeguarded fuels reprocessing plant  

SciTech Connect

The following appendices are included: aqueous reprocessing and conversion technology, reference facilities, process design and operating features relevant to materials accounting, operator's safeguards system structure, design principles of dynamic materials accounting systems, modeling and simulation approach, optimization of measurement control, aspects of international verification problem, security and reliability of materials measurement and accounting system, estimation of in-process inventory in solvent-extraction contactors, conventional measurement techniques, near-real-time measurement techniques, isotopic correlation techniques, instrumentation available to IAEA inspectors, and integration of materials accounting and containment and surveillance. (DLC)

Hakkila, E.A.; Baker, A.L.; Cobb, D.D.

1980-04-01

44

Active Test of Purification Facility at Rokkasho Reprocessing Plant  

SciTech Connect

During the second and third steps of Active Test of the Plutonium Purification unit, the extraction and reextraction performances of pulsed columns and mixer-settlers have been checked. Plutonium losses into wastes have been also checked. As a result, it was confirmed that the expected performances had been achieved. (authors)

Iseki, Tadahiro [Separation Section, Plant Operation Department, Reprocessing Plant Reprocessing Business Division, Japan Nuclear Fuel Limited 4-108, Aza Okitsuke, Oaza Obuchi, Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan); Tsujimura, Akino; Nitta, Takeshi; Matsuda, Takashi [Purification Section, Plant Operation Department, Reprocessing Plant Reprocessing Business Division, Japan Nuclear Fuel Limited 4-108, Aza Okitsuke, Oaza Obuchi, Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan)

2007-07-01

45

Designing and Operating for Safeguards: Lessons Learned From the Rokkasho Reprocessing Plant (RRP)  

SciTech Connect

This paper will address the lessons learned during the implementation of International Atomic Energy Agency (IAEA) safeguards at the Rokkasho Reprocessing Plant (RRP) which are relevant to the issue of ‘safeguards by design’. However, those lessons are a result of a cumulative history of international safeguards experiences starting with the West Valley reprocessing plant in 1969, continuing with the Barnwell plant, and then with the implementation of international safeguards at WAK in Germany and TRP in Japan. The design and implementation of safeguards at RRP in Japan is the latest and most challenging that the IAEA has faced. This paper will discuss the work leading up to the development of a safeguards approach, the design and operating features that were introduced to improve or aid in implementing the safeguards approach, and the resulting recommendations for future facilities. It will provide an overview of how ‘safeguardability’ was introduced into RRP.

Johnson, Shirley J.; Ehinger, Michael

2010-08-07

46

Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: reprocessing of high-temperature gas-cooled reactor fuel containing U-233 and thorium  

Microsoft Academic Search

A cost\\/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model high-temperature gas-cooled reactor (HTGR) fuel reprocessing plant and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist the U. S. Nuclear

W. Jr. Davis; R. E. Blanco; B. C. Finney; G. S. Hill; R. E. Moore; J. P. Witherspoon

2011-01-01

47

Process monitoring for reprocessing plant safeguards: a summary review  

SciTech Connect

Process monitoring is a term typically associated with a detailed look at plant operating data to determine plant status. Process monitoring has been generally associated with operational control of plant processes. Recently, process monitoring has been given new attention for a possible role in international safeguards. International Safeguards Project Office (ISPO) Task C.59 has the goal to identify specific roles for process monitoring in international safeguards. As the preliminary effort associated with this task, a review of previous efforts in process monitoring for safeguards was conducted. Previous efforts mentioned concepts and a few specific applications. None were comprehensive in addressing all aspects of a process monitoring application for safeguards. This report summarizes the basic elements that must be developed in a comprehensive process monitoring application for safeguards. It then summarizes the significant efforts that have been documented in the literature with respect to the basic elements that were addressed.

Kerr, H.T.; Ehinger, M.H.; Wachter, J.W.; Hebble, T.L.

1986-10-01

48

Active test of head-end facility at Rokkasho reprocessing plant  

SciTech Connect

During the first step, the second and the third step of Active Test (AT) at Rokkasho Reprocessing Plant (RRP), the performances of the Head-end Facility were checked, mainly for shearing and dissolution: shearing force and shearing time were the values as expected and concentration of U and Pu in dissolution solution were the values as expected. And safety requirement for acidity in dissolution solution was satisfied. (authors)

Yamamoto, Yoshiro; Tanaka, Satoshi; Kawabe, Shuji; Kamada, Yoshiaki [Head-End Section, Plant Operation Department, Reprocessing Plant Reprocessing Business Division, Japan Nuclear Fuel Limited 4-108, Aza Okitsuke, Oaza Obuchi, Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan)

2007-07-01

49

Lessons Learned in International Safeguards - Implementation of Safeguards at the Rokkasho Reprocessing Plant  

SciTech Connect

The focus of this report is lessons learned at the Rokkasho Reprocessing Plant (RRP). However, the subject of lessons learned for application of international safeguards at reprocessing plants includes a cumulative history of inspections starting at the West Valley (New York, U.S.A.) reprocessing plant in 1969 and proceeding through all of the efforts over the years. The RRP is the latest and most challenging application the International Atomic Energy Agency has faced. In many ways the challenges have remained the same, timely inspection and evaluation with limited inspector resources, with the continuing realization that planning and preparations can never start early enough in the life cycle of a facility. Lessons learned over the years have involved the challenges of using ongoing advances in technology and dealing with facilities with increased throughput and continuous operation. This report will begin with a review of historical developments and lessons learned. This will provide a basis for a discussion of the experiences and lessons learned from the implementation of international safeguards at RRP.

Ehinger, Michael H [ORNL; Johnson, Shirley [Tucker Creek Consulting

2010-02-01

50

Krypton-85 health risk assessment for a nuclear fuel reprocessing plant  

SciTech Connect

The risks involved in the routine release of /sup 85/Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of /sup 85/Kr. Instead of releasing the /sup 85/Kr to the environment when fuel is reprocessed, it can be captured, immobilized and stored. Two alternative methods of capturing /sup 85/Kr (cryogenic distillation and fluorocarbon absorption) and one method of immobilizing the captured gas (ion implantation/sputtering) were theoretically incorporated into a representative fuel reprocessing plant, the Barnwell Nuclear Fuel Plant, even though there are no known plans to start up this facility. Given the uncertainties in the models used to generate lifetime risk numbers (0.02 to 0.027 radiation induced fatal cancers expected in the occupational workforce and 0.017 fatal cancers in the general population), the differences in total risks for the three situations, (i.e., no-capture and two-capture alternatives) cannot be considered meaningful. It is possible that no risks would occur from any of the three situations. There is certainly no reason to conclude that risks from /sup 85/Kr routinely released to the environment are greater than those that would result from the other two situations considered. Present regulations mandate recovery and disposal of /sup 85/Kr from the off gases of a facility reprocessing spent fuel from commercial sources. Because of the lack of a clear-cut indication that recovery woud be beneficial, it does not seem prudent to burden the facilities with a requirement for /sup 85/Kr recovery, at least until operating experience demonstrates the incentive. The probable high aging of the early fuel to be processed and the higher dose resulting from the release of the unregulated /sup 3/H and /sup 14/C also encourage delaying implementation of the /sup 85/Kr recovery in the early plants.

Mellinger, P.J.; Brackenbush, L.W.; Tanner, J.E.; Gilbert, E.S.

1984-08-01

51

Evaluation and development plan of NRTA measurement methods for the Rokkasho Reprocessing Plant  

SciTech Connect

Near-real-time accounting (NRTA) has been proposed as a safeguards method at the Rokkasho Reprocessing Plant (RRP), a large-scale commercial boiling water and pressurized water reactors spent-fuel reprocessing facility. NRTA for RRP requires material balance closures every month. To develop a more effective and practical NRTA system for RRP, we have evaluated NRTA measurement techniques and systems that might be implemented in both the main process and the co-denitration process areas at RRP to analyze the concentrations of plutonium in solutions and mixed oxide powder. Based on the comparative evaluation, including performance, reliability, design criteria, operation methods, maintenance requirements, and estimated costs for each possible measurement method, recommendations for development were formulated. This paper discusses the evaluations and reports on the recommendation of the NRTA development plan for potential implementation at RRP.

Li, T.K.; Hakkila, E.A.; Flosterbuer, S.F. [and others

1995-08-01

52

Intergranular corrosion mechanism of ultra-low carbon type 304 stainless steel in a nuclear reprocessing plant  

SciTech Connect

Corrosion of the components which contains nitric acid solution such as vessels, tanks and pipes is an important problem for a PUREX method nuclear fuel reprocessing plant. In Tokai Reprocessing Plant which was startup in 1977 as the first Japanese plant, several events caused by corrosion have been experienced for about 30 years operation. The second plant in Japan, Rokkasho Reprocessing Plant, will start commercial operation from 2007. For stable operation of Rokkasho plant, maintenance management of components will be important. Therefore, it is necessary to clarify the corrosion mechanism and to reflect the results of the research for a maintenance program of the plant adequately. If high burnup fuel will increase in future nuclear power plants, it will become necessary to reprocess the spent fuel which includes more fission products and transuranium from now. Then the study of corrosion mechanism and life evaluation will become more important problem. Authors were aimed for development of life evaluation method of components and clarification of intergranular corrosion mechanism of ultra-low carbon type 304 stainless steel in a nuclear fuel reprocessing plant. In this report, the results of long-term corrosion test in boiling nitric acid by using ultra-low carbon stainless steel made mock-up test apparatus was described. And then, the relation between corrosion rate change and intergranular corrosion behavior were discussed. (authors)

Ueno, Fumiyoshi; Kato, Chiaki; Motooka, Takafumi; Yamamoto, Masahiro [Japan Atomic Energy Agency Shirakata Shirane 2-4, Tokai-mura, Ibaraki pref., 319-1195 (Japan); Ichikawa, Shiro [Kobelco Research Institute, Inc. 1-5-5, Takatsukadai, Nishi-ku, Kobe city, 651-2271 (Japan)

2007-07-01

53

Potential improvements in materials accounting for an internationally safeguarded fuels reprocessing plant  

SciTech Connect

The effectiveness of improved materials accounting was evaluated using computer modeling, simulation, and analysis techniques for two model reprocessing plants. One plant, sized to 210 MTHM/yr, represents the small plants currently under international safeguards and the other, sized to 1500 MTHM/yr, represents the large plants expected in the future. The study indicates that conventional accounting may meet IAEA goal quantities and detection times for low-enriched uranium in these facilities. Dynamic materials accounting can meet the IAEA goal for detecting abrupt (1 to 3 wk) diversion of 8 kg of plutonium. Current materials accounting techniques probably cannot meet the protracted diversion goal of detecting 8 kg for plutonium in 1 yr. Facility design features that can improve the effectiveness of materials accounting in future plants are discussed.

Hakkila, E.A.; Dayem, H.A.; Cobb, D.D.; Dietz, R.J.; Shipley, J.P.

1980-01-01

54

PRELIMINARY STUDY OF CERAMICS FOR IMMOBILIZATION OF ADVANCED FUEL CYCLE REPROCESSING WASTES  

SciTech Connect

The Savannah River National Laboratory (SRNL) developed a series of ceramic waste forms for the immobilization of Cesium/Lanthanide (CS/LN) and Cesium/Lanthanide/Transition Metal (CS/LN/TM) waste streams anticipated to result from nuclear fuel reprocessing. Simple raw materials, including Al{sub 2}O{sub 3}, CaO, and TiO{sub 2} were combined with simulated waste components to produce multiphase ceramics containing hollandite-type phases, perovskites (particularly BaTiO{sub 3}), pyrochlores, zirconolite, and other minor metal titanate phases. Identification of excess Al{sub 2}O{sub 3} via X-ray Diffraction (XRD) and Scanning Electron Microscopy with Energy Dispersive Spectroscopy (SEM/EDS) in the first series of compositions led to a Phase II study, with significantly reduced Al{sub 2}O{sub 3} concentrations and increased waste loadings. Three fabrication methodologies were used, including melting and crystallizing, pressing and sintering, and Spark Plasma Sintering (SPS), with the intent of studying phase evolution under various sintering conditions. XRD and SEM/EDS results showed that the partitioning of the waste elements in the sintered materials was very similar, despite varying stoichiometry of the phases formed. The Phase II compositions generally contained a reduced amount of unreacted Al{sub 2}O{sub 3} as identified by XRD, and had phase assemblages that were closer to the initial targets. Chemical composition measurements showed no significant issues with meeting the target compositions. However, volatilization of Cs and Mo was identified, particularly during melting, since sintering of the pressed pellets and SPS were performed at lower temperatures. Partitioning of some of the waste components was difficult to determine via XRD. SEM/EDS mapping showed that those elements, which were generally present in small concentrations, were well distributed throughout the waste forms. Initial studies of radiation damage tolerance using ion beam irradiation at Los Alamos National Laboratory (LANL) showed little if any modification of the material after irradiation. Additional study in this area is needed. Chemical durability was briefly studied using the Product Consistency Test (PCT). Most of the elements measured were retained by the ceramic waste forms, indicating good chemical durability. Cs, Mo, and Rb were released at somewhat higher rates as compared to the matrix components, although benchmark compositions and additional characterization are needed in order to qualify the PCT results.

Fox, K.; Billings, A.; Brinkman, K.; Marra, J.

2010-09-22

55

AVLIS production plant waste management plan  

SciTech Connect

Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables.

Not Available

1984-11-15

56

Accumulation of COGEMA-La Hague-derived reprocessing wastes in French salt marsh sediments.  

PubMed

Over the past five decades, authorized low-level discharges from coastal nuclear facilities have released significant quantities of artificial radionuclides into the marine environment. In northwest Europe, the majority of the total discharge has derived from nuclear reprocessing activities at Sellafield in the United Kingdom and COGEMA-La Hague in France. At the Sellafield site, a significant amount of the discharges has been trapped in offshore fine sediment deposits, and notably in local coastal and estuarine sediments, and much research has been focused on understanding the distribution, accumulation, and reworking of long-lived radionuclides in these deposits. In contrast, there are few high-resolution published data on the vertical distribution of radionuclides in fine-grained estuarine sediments near, and downstream of, COGEMA-La Hague. This paper therefore examines the vertical distribution of a range of anthropogenic radionuclides in dated salt marsh cores from two estuaries, one adjacent to, and the other downstream of, the COGEMA-La Hague discharge point (the Havre de Carteret at Barneville-Carteret and the Baie de Somme, respectively). The radionuclides examined show a vertical distribution which predominantly reflects variations in input from COGEMA-La Hague (albeit much more clearly at Barneville-Carteret than at the Baie de Somme site), and Pu isotopic ratios are consistent with a La Hague, rather than weapons' fallout, source. Because of sediment mixing, the marshes apparently retain an integrated record of the La Hague discharges, rather than an exact reproduction of the discharge history. Sorption of radionuclides increases in the order 90Sr < 137Cs < 60Co < 239,240Pu, which is consistent with Kd values reported in the literature. In general, the radionuclide activities observed at the sites studied are low (particularly in comparison with salt marsh sediments near the Sellafield facility), but are similar to those found in areas of fine sedimentation in the central Channel. These marshes are not major sinks for discharged reprocessing wastes. PMID:12523411

Cundy, Andrew B; Croudace, Ian W; Warwick, Phillip E; Oh, Jung-Suk; Haslett, Simon K

2002-12-01

57

Diethylene-triamine-penta-acetate administration protocol for radiological emergency medicine in nuclear fuel reprocessing plants.  

PubMed

Inhalation therapy of diethylene-triamine-penta-acetate (DTPA) should be initiated immediately to workers who have significant incorporation of plutonium, americium or curium in the nuclear fuel reprocessing plant. A newly designed electric mesh nebulizer is a small battery-operated passive vibrating mesh device, in which vibrations in an ultrasonic horn are used to force drug solution through a mesh of micron-sized holes. This nebulizer enables DTPA administration at an early stage in the event of a radiation emergency from contamination from the above radioactive metals. PMID:18274997

Jin, Yutaka

2008-01-01

58

Results of Active Test of Uranium-Plutonium Co-denitration Facility at Rokkasho Reprocessing Plant  

SciTech Connect

In the U-Pu co-denitration facility at Rokkasho Reprocessing Plant (RRP), Active Test which composes of 5 steps was performed by using uranium-plutonium nitrate solution that was extracted from spent fuels. During Active Test, two kinds of tests were performed in parallel. One was denitration performance test in denitration ovens, and expected results were successfully obtained. The other was validation and calibration of non-destructive assay (NDA) systems, and expected performances were obtained and their effectiveness as material accountancy and safeguards system was validated. (authors)

Numao, Teruhiko; Nakayashiki, Hiroshi; Arai, Nobuyuki; Miura, Susumu; Takahashi, Yoshiharu [Denitration Section, Plant Operation Dept., Reprocessing Plant, Reprocessing Business Division, Japan Nuclear Fuel Limited Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan); Nakamura, Hironobu; Tanaka, Izumi [Technical Support Dept., Reprocessing Plant, Reprocessing Business Division, Japan Nuclear Fuel Limited Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan)

2007-07-01

59

Use of process monitoring for verifying facility design of large-scale reprocessing plants  

SciTech Connect

During the decade of the 1990s, the International Atomic Energy Agency (IAEA) faces the challenge of implementing safeguards in large, new reprocessing facilities. The Agency will be involved in the design, construction, checkout and initial operation of these new facilities to ensure effective safeguards are implemented. One aspect of the Agency involvement is in the area of design verification. The United States Support Program has initiated a task to develop methods for applying process data collection and validation during the cold commissioning phase of plant construction. This paper summarizes the results of this task. 14 refs., 1 tab.

Hakkila, E.A.; Zack, N.R. (Los Alamos National Lab., NM (USA)); Ehinger, M.H. (Oak Ridge National Lab., TN (USA)); Franssen, F. (International Atomic Energy Agency, Vienna (Austria))

1991-01-01

60

Historic American Engineering Record, Idaho National Laboratory, Idaho Chemical Processing Plant, Fuel Reprocessing Complex  

SciTech Connect

Just as automobiles need fuel to operate, so do nuclear reactors. When fossil fuels such as gasoline are burned to power an automobile, they are consumed immediately and nearly completely in the process. When the fuel is gone, energy production stops. Nuclear reactors are incapable of achieving this near complete burn-up because as the fuel (uranium) that powers them is burned through the process of nuclear fission, a variety of other elements are also created and become intimately associated with the uranium. Because they absorb neutrons, which energize the fission process, these accumulating fission products eventually poison the fuel by stopping the production of energy from it. The fission products may also damage the structural integrity of the fuel elements. Even though the uranium fuel is still present, sometimes in significant quantities, it is unburnable and will not power a reactor unless it is separated from the neutron-absorbing fission products by a method called fuel reprocessing. Construction of the Fuel Reprocessing Complex at the Chem Plant started in 1950 with the Bechtel Corporation serving as construction contractor and American Cyanamid Company as operating contractor. Although the Foster Wheeler Corporation assumed responsibility for the detailed working design of the overall plant, scientists at Oak Ridge designed all of the equipment that would be employed in the uranium separations process. After three years of construction activity and extensive testing, the plant was ready to handle its first load of irradiated fuel.

Susan Stacy; Julie Braun

2006-12-01

61

Concepts for the reduction of waste volumes from nuclear fuel reprocessing operations  

Microsoft Academic Search

It is desirable, for environmental and economic reasons, to reduce the number and volume of waste streams from nuclear fuel processing operations. Concepts for achieving this end in future plants are reviewed. These include advanced dissolution concepts, simplification of the solvent extraction flowsheet, and the use of alternative separation techniques such as crystallisation, pyrochemistry and ion exchange.

S. T. Arm; R. P. Bush; J. C. Mcgurk

1998-01-01

62

Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container  

E-print Network

Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation Plan Prepared. The Order, at paragraph 22, requires the Permittees to submit a WIPP Nitrate Salt Bearing Waste Container Isolation Plan (Plan) for identified nitrate salt bearing waste disposed in the Waste Isolation Pilot Plant

Napp, Nils

63

Corrosion mechanisms of austenitic stainless steels in nitric media used in reprocessing plants  

NASA Astrophysics Data System (ADS)

Austenitic stainless steels type 304L, 316L and 310Nb are largely used as structural materials for equipments handling nitric acid media in reprocessing plants. In almost all nitric media, these materials, protected by a chromium(III) oxide rich layer, remain in their passive state. However, in some particular nitric media, their corrosion potential may be shifted towards their transpassive domain. In this domain, they can suffer intergranular corrosion, even though they are not sensitized owing to their very low carbon content. The corrosion potential of the steel depends greatly on the cathodic reaction involved in the oxido-reduction process between the elements Fe, Cr, Ni of the steel and the oxidizing species of the medium. Three cases of an increase in the corrosion potential can be found in reprocessing media: pure nitric acid-water solutions, in which the cathodic reaction is the reduction reaction of HNO 3; nitric acid media containing oxidizing species, in which the cathodic reaction is the reaction of reduction of the oxidizing species into the reduced one; nitric media containing metallic elements electrochemically more noble than the steels, causing galvanic coupling. In each case, the mechanism and the relevant situations we experimentally studied are described.

Fauvet, P.; Balbaud, F.; Robin, R.; Tran, Q.-T.; Mugnier, A.; Espinoux, D.

2008-03-01

64

Conceptual designs of NDA instruments for the NRTA system at the Rokkasho Reprocessing Plant  

SciTech Connect

The authors are studying conceptual designs of selected nondestructive assay (NDA) instruments for the near-real-time accounting system at the rokkasho Reprocessing Plant (RRP) of Japan Nuclear Fuel Limited (JNFL). The JNFL RRP is a large-scale commercial reprocessing facility for spent fuel from boiling-water and pressurized-water reactors. The facility comprises two major components: the main process area to separate and produce purified plutonium nitrate and uranyl nitrate from irradiated reactor spent fuels, and the co-denitration process area to combine and convert the plutonium nitrate and uranyl nitrate into mixed oxide (MOX). The selected NDA instruments for conceptual design studies are the MOX-product canister counter, holdup measurement systems for calcination and reduction furnaces and for blenders in the co-denitration process, the isotope dilution gamma-ray spectrometer for the spent fuel dissolver solution, and unattended verification systems. For more effective and practical safeguards and material control and accounting at RRP, the authors are also studying the conceptual design for the UO{sub 3} large-barrel counter. This paper discusses the state-of-the-art NDA conceptual design and research and development activities for the above instruments.

Li, T.K.; Klosterbuer, S.F.; Menlove, H.O. [Los Alamos National Lab., NM (United States). Safeguards Science and Technology Group] [and others

1996-09-01

65

Methodology for Determining the Radiological Status of a Process: Application to Decommissioning of a Fuel Reprocessing Plant  

SciTech Connect

Decommissioning a nuclear facility is subject to various constraints including regulatory safety requirements, but also the obligation to limit the waste volume and toxicity. To meet these requirements the activity level in each component must be known at each stage of decommissioning, from the preliminary studies to the final release of the premises. This document describes a set of methods used to determine the radiological state of a spent fuel reprocessing plant. This approach begins with a bibliographical survey covering the nature of the chemical processes, the operational phases, and the radiological assessments during the plant operating period. In this phase it is also very important to analyze incidents and waste management practices. All available media should be examined, including photos and videos which can provide valuable data and must not be disregarded. At the end of this phase, any items requiring verification or additional data are reviewed to define further investigations. Although it is not unusual at this point to carry out an additional bibliographical survey, the essential task is to carry out in situ measurements. The second phase thus consists in performing in situ measurement campaigns involving essentially components containing significant activity levels. The most routinely used methods combine the results of elementary measurements such as the dose rate or more sophisticated measurements such as gamma spectrometry using CdZnTe detectors and gamma imaging to estimate and localize the radioactivity. Each instrument provides part of the answer (location of a contamination hot spot, standard spectrum, activity). The results are combined and verified through the use of calculation codes: Mercure, Visiplan and Microshield. (authors)

Girones, Ph.; Ducros, C.; Legoaller, C.; Lamadie, F.; Fulconis, J.M.; Thiebaut, V.; Mahe, C. [Commissariat a l'Energie Atomique - CEA (France)

2006-07-01

66

Surveillance system using the CCTV at the fuel transfer pond in the Tokai reprocessing plant  

SciTech Connect

The Fuel Transfer Pond (FTP) in the Tokai Reprocessing Plant (TRP) is a strategic point for safeguards. Spent fuels, therefore, in the FTP have been surveyed by the surveillance system using the underwater CCTV. This system was developed through the improvement of devices composed of cameras and VCRs and the provision of tamper resistance function as one of the JASPAS (Japan Support Program for Agency Safeguards) program. The purpose of this program is to realize the continuous surveillance of the slanted tunnel through which the spent fuel on the conveyor is moved from the FTP to the Mechanical Processing Cell (MPC). This paper reports that, when this surveillance system is applied to an inspection device, the following requirements are needed: To have the ability of continuous and unattended surveillance of the spent fuel on the conveyor path from the FTP to the MPC; To have the tamper resistance function for continuous and unattended surveillance of the spent fuel.

Hayakawa, T.; Fukuhara, J.; Ochiai, K.; Ohnishi, T.; Ogata, Y.; Okamoto, H. (Power Reactor and Nuclear Fuel Development Corp. (JP))

1991-01-01

67

The Nuclear Energy Advanced Modeling and Simulation Safeguards and Separations Reprocessing Plant Toolkit  

SciTech Connect

This report details the progress made in the development of the Reprocessing Plant Toolkit (RPTk) for the DOE Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. RPTk is an ongoing development effort intended to provide users with an extensible, integrated, and scalable software framework for the modeling and simulation of spent nuclear fuel reprocessing plants by enabling the insertion and coupling of user-developed physicochemical modules of variable fidelity. The NEAMS Safeguards and Separations IPSC (SafeSeps) and the Enabling Computational Technologies (ECT) supporting program element have partnered to release an initial version of the RPTk with a focus on software usability and utility. RPTk implements a data flow architecture that is the source of the system's extensibility and scalability. Data flows through physicochemical modules sequentially, with each module importing data, evolving it, and exporting the updated data to the next downstream module. This is accomplished through various architectural abstractions designed to give RPTk true plug-and-play capabilities. A simple application of this architecture, as well as RPTk data flow and evolution, is demonstrated in Section 6 with an application consisting of two coupled physicochemical modules. The remaining sections describe this ongoing work in full, from system vision and design inception to full implementation. Section 3 describes the relevant software development processes used by the RPTk development team. These processes allow the team to manage system complexity and ensure stakeholder satisfaction. This section also details the work done on the RPTk ``black box'' and ``white box'' models, with a special focus on the separation of concerns between the RPTk user interface and application runtime. Section 4 and 5 discuss that application runtime component in more detail, and describe the dependencies, behavior, and rigorous testing of its constituent components.

McCaskey, Alex [ORNL; Billings, Jay Jay [ORNL; de Almeida, Valmor F [ORNL

2011-08-01

68

Collocation and integration of reprocessing and repositories: implications for aqueous flowsheets and waste management  

SciTech Connect

It is an accident of history that the current model of the fuel cycle is a separate set of facilities connected by transportation. The question is whether collocation and integration of reprocessing and fuel fabrication with the repository significantly reduce the costs of a closed fuel cycle while improving system performance in terms of safety and long-term repository performance. This paper examines the question in terms of higher-level functional requirements of reprocessing systems and geological repositories.

Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave., Room 24-207A Cambridge, Massachusetts 02139 (United States); Lewis, L. [Idaho National Laboratory, Idaho Falls, Idaho 83415 (United States)

2013-07-01

69

Iodine Pathways and Off-Gas Stream Characteristics for Aqueous Reprocessing Plants – A Literature Survey and Assessment  

SciTech Connect

Used nuclear fuel is currently being reprocessed in only a few countries, notably France, England, Japan, and Russia. The need to control emissions of the gaseous radionuclides to the air during nuclear fuel reprocessing has already been reported for the entire plant. But since the gaseous radionuclides can partition to various different reprocessing off-gas streams, for example, from the head end, dissolver, vessel, cell, and melter, an understanding of each of these streams is critical. These off-gas streams have different flow rates and compositions and could have different gaseous radionuclide control requirements, depending on how the gaseous radionuclides partition. This report reviews the available literature to summarize specific engineering data on the flow rates, forms of the volatile radionuclides in off-gas streams, distributions of these radionuclides in these streams, and temperatures of these streams. This document contains an extensive bibliography of the information contained in the open literature.

R. T. Jubin; D. M. Strachan; N. R. Soelberg

2013-09-01

70

Case-control study of leukaemia among young people near La Hague nuclear reprocessing plant: the environmental hypothesis revisited.  

PubMed Central

OBJECTIVE: To investigate the association between childhood leukaemia and established risk factors or other factors related to La Hague nuclear waste reprocessing plant. DESIGN: Case-control study. SETTING: Area within a 35 km radius of La Hague, Normandy, France. SUBJECTS: Twenty seven cases of leukaemia diagnosed during the period 1978-93 in people aged under 25 years and 192 controls matched for sex, age, place of birth, and residence at time of diagnosis. MAIN OUTCOME MEASURES: Antenatal and postnatal exposure to x rays and viral infections, occupational exposure of parents (particularly ionising radiation), living conditions, lifestyle of parents and children. RESULTS: Increased trends were found for use of local beaches by mothers and children (P < or = 0.01); relative risks 2.87 (95% confidence intervals 1.05 to 8.72) and 4.49 (1.52 to 15.23) when categories were aggregated in two levels (more or less than once a month). Consumption of local fish and shellfish also showed an increased trend (P 0.01); relative risk 2.66 (0.91 to 9.51) when categories were grouped in two levels (more or less than once a week). A relative risk of 1.18 a year (1.03 to 1.42) was observed for length of residence in a granite-built house or in a granitic area. No association was shown with occupational radiation exposure in parents. CONCLUSIONS: There is some convincing evidence in childhood leukaemia of a causal role for environmental radiation exposure from recreational activities on beaches. New methods for identifying the environmental pathways, focusing on marine ecosystems, are warranted. PMID:9006467

Pobel, D.; Viel, J. F.

1997-01-01

71

Characterization of past and present solid waste streams from the Plutonium-Uranium Extraction Plant  

SciTech Connect

During the next two decades the transuranic wastes, now stored in the burial trenches and storage facilities at the Hanford Site, are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Over 7% of the transuranic waste to be retrieved for shipment to the Waste Isolation Pilot Plant has been generated at the Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this report is to characterize the radioactive solid wastes generated by PUREX using process knowledge, existing records, and oral history interviews. The PUREX Plant is currently operated by the Westinghouse Hanford Company for the US Department of Energy and is now in standby status while being prepared for permanent shutdown. The PUREX Plant is a collection of facilities that has been used primarily to separate plutonium for nuclear weapons from spent fuel that had been irradiated in the Hanford Site`s defense reactors. Originally designed to reprocess aluminum-clad uranium fuel, the plant was modified to reprocess zirconium alloy clad fuel elements from the Hanford Site`s N Reactor. PUREX has provided plutonium for research reactor development, safety programs, and defense. In addition, the PUREX was used to recover slightly enriched uranium for recycling into fuel for use in reactors that generate electricity and plutonium. Section 2.0 provides further details of the PUREX`s physical plant and its operations. The PUREX Plant functions that generate solid waste are as follows: processing operations, laboratory analyses and supporting activities. The types and estimated quantities of waste resulting from these activities are discussed in detail.

Pottmeyer, J.A.; Weyns, M.I.; Lorenzo, D.S.; Vejvoda, E.J. [Los Alamos Technical Associates, Inc., NM (US); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (US)

1993-04-01

72

Waste Management Trends in Texas Industrial Plants  

E-print Network

, including reporting. Some reporting is required of all industrial plants, but the reporting requirements and procedures differ in accordance with the type and amount of waste generated. Future changes in federal and state laws regarding waste management...

Smith, C. S.; Heffington, W. M.

73

Deactivation of hydrophobic Pt/SDBC-catalyst for H{sub 2}/HTO-exchange reaction destined for tritium removal in reprocessing plant  

SciTech Connect

Deactivation of a hydrophobic Pt/SDBC catalyst for the H{sub 2}/HTO isotopic exchange reaction used to remove tritium from the waste water generated in a nuclear-fuel reprocessing plant has been studied experimentally. The catalyst was poisoned reversibly by a small amount of HNO{sub 3} and could be regenerated by washing with water followed by drying in an inert gas. As a countermeasure against this poisoning, the neutralization of the waste water was found to be effective. The presence of I{sub 2} in the waste water caused a sharp decrease in the activity of the catalyst, due to the irreversible adsorption of I{sub 2} onto the catalyst surface. The I{sub 2} poisoning could be prevented by the conversion of I{sub 2} into I{sup -} or IO{sub 3}{sup -} by neutralization or redox reaction. TBP and the neutral nitrate salts of fission products such as Sr(NO{sub 3}){sub 2} showed negligible poisoning effects on the catalyst. 10 refs., 8 figs., 1 tab.

Wei, Y.Z.; Takeshita, K.; Kumagai, M.; Takashima, Y. [Inst. of Research and Innovation, Chiba (Japan); Matsumoto, S. [Saitama Univ. (Japan); Shimizu, M. [Isotope Science Lab., Kanagawa (Japan)

1995-10-01

74

DEVELOPMENT OF CRYSTALLINE CERAMICS FOR IMMOBILIZATION OF ADVANCED FUEL CYCLE REPROCESSING WASTES  

Microsoft Academic Search

The Savannah River National Laboratory (SRNL) is developing crystalline ceramic waste forms to incorporate CS\\/LN\\/TM high Mo waste streams consisting of perovskite, hollandite, pyrochlore, zirconolite, and powellite phase assemblages. Simple raw materials, including AlO, CaO, and TiO were combined with simulated waste components to produce multiphase crystalline ceramics. Fiscal Year 2011 (FY11) activities included (i) expanding the compositional range by

K. Fox; K. Brinkman

2011-01-01

75

Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan  

SciTech Connect

The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented.

Randklev, E.H.

1993-06-01

76

Component failure-rate data with potential applicability to a nuclear fuel reprocessing plant  

SciTech Connect

Approximately 1223 pieces of component failure-rate data, under 136 subject categories, have been compiled from published literature and computer searches of a number of data bases. Component selections were based on potential applicability to facilities for reprocessing spent nuclear fuels. The data will be useful in quantifying fault trees for probabilistic safety analyses and risk assessments.

Dexter, A.H.; Perkins, W.C.

1982-07-01

77

Disposal of Savannah River Plant Waste Salt.  

National Technical Information Service (NTIS)

Approximately 26-million gallons of soluble low-level waste salts will be produced during solidification of 6-million gallons of high-level defense waste in the proposed Defense Waste Processing Facility (DWPF) at the Savannah River Plant (SRP). Soluble w...

M. D. Dukes

1982-01-01

78

Study of seed-reprocessing systems for open-cycle coal-fired MHD power plants.  

NASA Astrophysics Data System (ADS)

Of the several processes that are capable of separating sulfur from potassium sulfate, the process developed by Pittsburgh Energy Research Center (PERC), and the Formate process were selected for the detailed mass and energy balance calculations. As a basis for the calculations, an MHD power plant of 450 Mwt size and burning Illinois no. 6 coal was selected. In the mass balance calculations, the role played by various trace impurities was included to the extent of current knowledge about such impurities and their impacts on process chemistry. The results given should be considered as preliminary values because various simplifying assumptions were made and factors such as heat losses and component efficiencies were excluded. On the basis of net energy requirements, the Formate process showed a slight advantage; however, it produced a potentially unacceptable sludge as the sulfur containing waste.

Sheth, A.

1980-07-01

79

DEVELOPMENT OF CRYSTALLINE CERAMICS FOR IMMOBILIZATION OF ADVANCED FUEL CYCLE REPROCESSING WASTES  

SciTech Connect

The Savannah River National Laboratory (SRNL) is developing crystalline ceramic waste forms to incorporate CS/LN/TM high Mo waste streams consisting of perovskite, hollandite, pyrochlore, zirconolite, and powellite phase assemblages. Simple raw materials, including Al{sub 2}O{sub 3}, CaO, and TiO{sub 2} were combined with simulated waste components to produce multiphase crystalline ceramics. Fiscal Year 2011 (FY11) activities included (i) expanding the compositional range by varying waste loading and fabrication of compositions rich in TiO{sub 2}, (ii) exploring the processing parameters of ceramics produced by the melt and crystallize process, (iii) synthesis and characterization of select individual phases of powellite and hollandite that are the target hosts for radionuclides of Mo, Cs, and Rb, and (iv) evaluating the durability and radiation stability of single and multi-phase ceramic waste forms. Two fabrication methods, including melting and crystallizing, and pressing and sintering, were used with the intent of studying phase evolution under various sintering conditions. An analysis of the XRD and SEM/EDS results indicates that the targeted crystalline phases of the FY11 compositions consisting of pyrochlore, perovskite, hollandite, zirconolite, and powellite were formed by both press and sinter and melt and crystallize processing methods. An evaluation of crystalline phase formation versus melt processing conditions revealed that hollandite, perovskite, zirconolite, and residual TiO{sub 2} phases formed regardless of cooling rate, demonstrating the robust nature of this process for crystalline phase development. The multiphase ceramic composition CSLNTM-06 demonstrated good resistance to proton beam irradiation. Electron irradiation studies on the single phase CaMoO{sub 4} (a component of the multiphase waste form) suggested that this material exhibits stability to 1000 years at anticipated self-irradiation doses (2 x 10{sup 10}-2 x 10{sup 11} Gy), but that its stability may be rate dependent, therefore limiting the activity of the waste for which it can be employed. Overall, these preliminary results indicate good radiation damage tolerance for the crystalline ceramic materials. The PCT results showed that, for all of the waste forms tested, the normalized release values for most of the elements measured, including all of the lanthanides and noble metals, were either very small or below the instrument detection limits. Elevated normalized release values were measured only for Cs, Mo, and Rb. It is difficult to draw further conclusions from these data until a benchmark material is developed for the PCT with this type of waste form. Calcined, simulated CS/LN/TM High Mo waste without additives had relatively low normalized release values for Cs, Mo, and Rb. A review of the chemical composition data for this sample showed that these elements were well retained after the calcination. Therefore, it will be useful to further characterize the calcined material to determine what form these elements are in after calcining. This, along with single phase studies on Cs containing crystal structures such as hollandite, should provide insight into the most ideal phases to incorporate these elements to produce a durable waste form.

Fox, K.; Brinkman, K.

2011-09-22

80

Waste handling and packaging plant project description  

SciTech Connect

ORNL currently has about 300 m{sup 3} of remote handled transuranic (RHTRU) solid waste retrievably stored in trenches and a bunker. This material will be processed through the Waste Handling and Packaging Plant (WHDP) for shipment to the Waste Isolation Pilot Plant (WIPP). Details of siting, construction, and conceptual flow of RHTRU waste through the plant are provided. ORNL also has liquid waste and sludge stored in the Melton Valley Storage Tanks (MVST). The sludge also contains TRU waste, and the WHPP will process an expected volume of 500,000 gallons of a suernatant/sludge slurry for shipment to the WIPP. Specific systems which require more development include the cask transfer system, the linear accelerator-based nondestructive assay and nondestructive evaluation equipment. (MHB)

Turner, D.W.; Moore, J.W.; Conatser, D.A.

1991-01-01

81

Technology and equipment based on induction melters with ``cold'' crucible for reprocessing active metal waste  

NASA Astrophysics Data System (ADS)

The paper discusses specific features of technology, equipment and control of a single stage RAMW decontamination and melting process in an induction furnace equipped with a "cold" crucible. The calculated and experimental data are given on melting high activity level stainless steel and Zr simulating high activity level metal waste. The work is under way in SSC RF VNIINM.

Pastushkov, V. G.; Molchanov, A. V.; Serebryakov, V. P.; Smelova, T. V.; Shestoperov, I. N.

2000-07-01

82

Treatment of molten salt wastes by phosphate precipitation: removal of fission product elements after pyrochemical reprocessing of spent nuclear fuels in chloride melts  

Microsoft Academic Search

The removal of fission product elements from molten salt wastes arising from pyrochemical reprocessing of spent nuclear fuels has been investigated. The experiments were conducted in LiCl–KCl eutectic at 550 °C and NaCl–KCl equimolar mixture at 750 °C. The behavior of the following individual elements was investigated: Cs, Mg, Sr, Ba, lanthanides (La to Dy), Zr, Cr, Mo, Mn, Re

Vladimir A Volkovich; Trevor R Griffiths; Robert C Thied

2003-01-01

83

Report on the NGS3 Working Group on Safeguards by Design For Aqueous Reprocessing Plants  

SciTech Connect

The objective of the Working Group on SBD for Aqueous Reprocessing Facilities was to provide recommendations, for facility operators and designers, which would aid in the coordination and integration of nuclear material accountancy and the safeguards requirements of all concerned parties - operators, state/regional authorities, and the IAEA. The recommendations, which are to be provided to the IAEA, are intended to assist in optimizing facility design and operating parameters to ensure the safeguardability of the facility while minimizing impact on the operations. The one day Working Group session addressed a wide range of design and operating topics.

Johnson, Shirley J.; Ehinger, Michael; Schanfein, Mark

2011-02-01

84

Plutonium finishing plant dangerous waste training plan  

SciTech Connect

This training plan describes general requirements, worker categories, and provides course descriptions for operation of the Plutonium Finish Plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas.

ENTROP, G.E.

1999-05-24

85

Hanford Waste Vitrification Plant capacity increase options  

Microsoft Academic Search

Studies are being conducted by the Hanford Waste Vitrification Plant (HWVP) Project on ways to increase the waste processing capacity within the current Vitrification Building structural design. The Phase 1 study on remote systems concepts identification and extent of capacity increase was completed. The study concluded that the HWVP capacity could be increased to four times the current capacity with

1996-01-01

86

NUCLEAR POWER PLANT WASTE HEAT HORTICULTURE  

EPA Science Inventory

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

87

Determination of the Structure of Vitrified Hydroceramic/CBC Waste Form Glasses Manufactured from DOE Reprocessing Waste  

SciTech Connect

The selection of a glass-making option for the solidification of nuclear waste has dominated DOE waste form programs since the early 1980's. Both West Valley and Savannah River are routinely manufacturing glass logs from the high level waste inventory in tank sludges. However, for some wastes, direct conversion to glass is clearly not the optimum strategy for immobilization. INEEL, for example, has approximately 4400 m{sup 3} of calcined high level waste with an activity that produces approximately 45 watts/m{sup 3}, a rather low concentration of radioactive constituents. For these wastes, there is value in seeking alternatives to glass. An alternative approach has been developed and the efficacy of the process demonstrated that offers a significant savings in both human health and safety exposures and also a lower cost relative to the vitrification option. The alternative approach utilizes the intrinsic chemical reactivity of the highly alkaline waste with the addition of aluminosilicate admixtures in the appropriate proportions to form zeolites. The process is one in which a chemically bonded ceramic is produced. The driving force for reaction is derived from the chemical system itself at very modest temperatures and yet forms predominantly crystalline phases. Because the chemically bonded ceramic requires an aqueous medium to serve as a vehicle for the chemical reaction, the proposed zeolite-containing waste form can more adequately be described as a hydroceramic. The hydrated crystalline materials are then subject to hot isostatic pressing (HIP) which partially melts the material to form a glass ceramic. The scientific advantages of the hydroceramic/CBC approach are: (1) Low temperature processing; (2) High waste loading and thus only modest volumetric bulking from the addition of admixtures; (3) Ability to immobilize sodium; (4) Ability to handle low levels of nitrate (2-3% NO{sub 3}{sup -}); (5) The flexibility of a vitrifiable waste; and (6) A process that is based on an industry with decades of practical experience. The research undertaken in the present investigation builds on a previous study under the NEER program. The earlier studies identified an optimal formulation for the immobilization of the calcine that is both compositionally adequate to retain radionuclides as well as hazardous constituents and which has a reaction rate that will allow the technical employment of the process. The study established in a general way the glass-forming region in the system M{sub 2}O-MO-Al{sub 2}O{sub 3}-SiO{sub 2} (M{sub 2}0 = alkali metal oxides; MO = alkaline earth metal oxide) which provides the base for these hydroceramic/CBC materials (Fig. 1). The objectives of the present program are to track the structural changes that take place during formulation, chemical reaction, and HIPing. Compositions must be varied through the glass-forming region, structures of the crystals and glass matrix of the glass-ceramic determined, and the structural characteristics in turn related to stability and leachability of the final products.

Scheetz, B.E.; White, W. B.; Chesleigh, M.; Portanova, A.; Olanrewaju, J.

2005-05-31

88

Waste minimization at La Hague  

SciTech Connect

The industrial mastery of commercial reprocessing gained by COGEMA is the result of a progressive strategy. Today more than 25 years after the start-up of the facilities which initiated the commercial reprocessing at La Hague, the recovery and recycling of energetic materials are demonstrated and the necessary industrial facilities are available. The second objective of reprocessing, i.e. safe on-line waste conditioning has been achieved in the UP3 plant. At the present time, there are strong incentives to reduce the volumes of HLW and TRU waste, in all countries involved in nuclear electricity generation and COGEMA is making significant progress in reducing the volume of wastes generated in its reprocessing plants to provide the best possible reprocessing service and simplify waste management practices through a continuous policy of progress. When UP3 was designed, it was planned to produce 0.75 glass canisters and 3 bitumen drums per ton of uranium reprocessed. Through changes in the waste management practices and plant modifications, COGEMA will eliminate all bitumen waste forms by 1995. Furthermore, an advanced compaction technology for the hulls and end-pieces will be implemented at the La Hague reprocessing plant in the coming years. Similarly, volumes of technological residues will be reduced from 1,700 liters per MTU to only 200 liters per MTU, with further progress planned in the coming years.

Masson, H.; Roux, P.

1994-12-31

89

Managing nuclear waste from power plants  

Microsoft Academic Search

National strategies to manage nuclear waste from commercial nuclear power plants are analyzed and compared. The current strategy is to try to operate a repository at Yucca Mountain, Nevada, to dispose storage at a centralized facility or next to nuclear power plants. If either of these is pursued now, the analysis assumes that a repository will be built in 2100

Ralph L. Keeney; Detlof Winterfeldt

1994-01-01

90

On-Line Monitoring for Control and Safeguarding of Radiochemical Streams at Spent Fuel Reprocessing Plant  

SciTech Connect

There is a renewed interest worldwide to promote the use of nuclear power and close the nuclear fuel cycle. The long term successful use of nuclear power is critically dependent upon adequate and safe processing and disposition of the spent nuclear fuel Liquid-liquid extraction is a separation technique commonly employed for the processing of the dissolved spent nuclear fuel. Our approach is based on prerequisite that real time monitoring of the solvent extraction flowsheets provides unique capability to quickly detect unwanted manipulations with fissile isotopes present in the radiochemical streams during reprocessing activities. The instrumentation used to monitor these processes must be robust, require little or no maintenance, and be able to withstand harsh environments such as high radiation fields and aggressive chemical matrices. In addition, the ability for continuous on-line monitoring allows for numerous benefits. Our team experimentally assessed the potential of Raman and vis-NIR spectrophotometric techniques for on-line real-time monitoring of the U(VI)/nitrate ion/nitric acid and Pu(IV)/Np(V)/Nd(III), respectively, in solutions relevant to spent fuel reprocessing. Both techniques demonstrated robust performance in the repetitive batch measurements of each analyte in a wide concentration range using simulant and commercial dissolved spent fuel solutions. Static spectroscopic measurements served as training sets for the multivariate data analysis to obtain partial least squares predictive models, which were validated using on-line centrifugal contactor extraction tests. The corresponding spectrometers used under the laboratory conditions are easily convertible to the process-friendly configurations allowing remote measurements under the flow conditions. A fiber optic Raman probe allows monitoring of the high concentration species encountered in both aqueous and organic phases within the PUREX suite of flowsheets, including metal oxide ions, such as uranyl, components of the organic solvent, inorganic oxo-anions, and water. The actinides and lanthanides are monitored remotely by UV-vis-NIR spectroscopy in aqueous and organic phases. This paper summarizes our methodology and shows results of specific examples.

Bryan, Samuel A.; Levitskaia, Tatiana G.; Casella, Amanda J.; Peterson, James M.; Lines, Amanda M.; Jordan, Elizabeth A.; Verdugo, Dawn E.; Skomurski, Frances N.

2011-07-19

91

Neurotoxic effects from residential exposure to chemicals from an oil reprocessing facility and superfund site  

Microsoft Academic Search

Neurotoxicity has been described in workers exposed to solvents, PCBs, certain metals, and polyaromatic hydrocarbons but not often in residents near refineries or factories. We compared the neurobehavioral performance of residents near a plant that reprocessed used motor oil and chemical waste from 1966–1983 to referents from beyond the plant's modeled air dispersal and water drainage zones. Neurophysiological and psychological

Kaye H. Kilburn; Raphael H. Warshaw

1995-01-01

92

Hanford Waste Vitrification Plant applied technology plan  

SciTech Connect

This Applied Technology Plan describes the process development, verification testing, equipment adaptation, and waste form qualification technical issues and plans for resolution to support the design, permitting, and operation of the Hanford Waste Vitrification Plant. The scope of this Plan includes work to be performed by the research and development contractor, Pacific Northwest Laboratory, other organizations within Westinghouse Hanford Company, universities and companies with glass technology expertise, and other US Department of Energy sites. All work described in this Plan is funded by the Hanford Waste Vitrification Plant Project and the relationship of this Plan to other waste management documents and issues is provided for background information. Work to performed under this Plan is divided into major areas that establish a reference process, develop an acceptable glass composition envelope, and demonstrate feed processing and glass production for the range of Hanford Waste Vitrification Plant feeds. Included in this work is the evaluation and verification testing of equipment and technology obtained from the Defense Waste Processing Facility, the West Valley Demonstration Project, foreign countries, and the Hanford Site. Development and verification of product and process models and other data needed for waste form qualification documentation are also included in this Plan. 21 refs., 4 figs., 33 tabs.

Kruger, O.L.

1990-09-01

93

Waste acceptance criteria for the Waste Isolation Pilot Plant  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

NONE

1996-04-01

94

Mechanical compaction of Waste Isolation Pilot Plant simulated waste  

SciTech Connect

The investigation described in this report acquired experimental information about how materials simulating transuranic (TRU) waste compact under axial compressive stress, and used these data to define a model for use in the Waste Isolation Pilot Plant (WIPP) disposal room analyses. The first step was to determine compaction curves for various simultant materials characteristic of TRU waste. Stress-volume compaction curves for various combinations of these materials were than derived to represent the combustible, metallic, and sludge waste categories. Prediction of compaction response in this manner is considered essential for the WIPP program because of the difficulties inherent in working with real (radioactive) waste. Next, full-sized 55-gallon drums of simulated combustible, metallic, and sludge waste were axially compacted. These results provided data that can be directly applied to room consolidation and data for comparison with the predictions obtained in Part 1 of the investigation. Compaction curves, which represent the combustible, metallic, and sludge waste categories, were determined, and a curve for the averaged waste inventory of the entire repository was derived. 9 refs., 31 figs., 12 tabs.

Butcher, B.M. (Sandia National Labs., Albuquerque, NM (United States)); Thompson, T.W.; VanBuskirk, R.G.; Patti, N.C. (Science Applications International Corp., Golden, CO (United States))

1991-06-01

95

Advanced Instrumentation for Reprocessing.  

National Technical Information Service (NTIS)

Recent interest in reprocessing nuclear fuel in the U.S. has led to advanced separations processes that employ continuous processing and multiple extraction steps. These advanced plants will need to be designed with state-of-the-art instrumentation for ma...

B. B. Cipiti

2005-01-01

96

Characterization of Savannah River Plant waste glass  

SciTech Connect

The objective of the glass characterization programs at the Savannah River Laboratory (SRL) is to ensure that glass containing Savannah River Plant high-level waste can be permanently stored in a federal repository, in an environmentally acceptable manner. To accomplish this objective, SRL is carrying out several experimental programs, including: fundamental studies of the reactions between waste glass and water, particularly repository groundwater; experiments in which candidate repository environments are simulated as accurately as possible; burial tests of simulated waste glass in candidate repository geologies; large-scale tests of glass durability; and determination of the effects of process conditions on glass quality. In this paper, the strategy and current status of each of these programs is discussed. The results indicate that waste packages containing SRP waste glass will satisfy emerging regulatory criteria.

Plodinec, M J

1985-01-01

97

Waste Water Plant Operators Manual.  

ERIC Educational Resources Information Center

This manual for sewage treatment plant operators was prepared by a committee of operators, educators, and engineers for use as a reference text and handbook and to serve as a training manual for short course and certification programs. Sewage treatment plant operators have a responsibility in water quality control; they are the principal actors in…

Washington State Coordinating Council for Occupational Education, Olympia.

98

Hanford Waste Vitrification Plant technical manual  

SciTech Connect

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

1996-03-01

99

Waste disposal options report. Volume 1  

SciTech Connect

This report summarizes the potential options for the processing and disposal of mixed waste generated by reprocessing spent nuclear fuel at the Idaho Chemical Processing Plant. It compares the proposed waste-immobilization processes, quantifies and characterizes the resulting waste forms, identifies potential disposal sites and their primary acceptance criteria, and addresses disposal issues for hazardous waste.

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01

100

REPROCESSING OF SHALLOW SEISMIC REFLECTION DATA TO IMAGE FAULTS NEAR A HAZARDOUS WASTE SITE ON THE OAK RIDGE RESERVATION, TENNESSEE  

SciTech Connect

Shallow seismic reflection data from Bear Creek Valley on the Oak Ridge Reservation demonstrates that spectral balancing and tomographic refraction statics can be important processing tools for shallow seismic data. At this site, reprocessing of data which had previously yielded no useable CMP stacked sections was successful after application of these processing techniques.

DOLL, W.E.

1997-12-30

101

Reprocessing of Shallow Seismic Reflection Data to Image Faults Near a Hazardous Waste Site on the Oak Ridge Reservation, Tennessee  

SciTech Connect

Shallow seismic reflection data from Bear Creek Valley on the Oak Ridge Reservation demonstrates that spectral balancing and tomographic refraction statics can be important processing tools for shallow seismic data. At this site, reprocessing of data which had previously yielded no usable CMP stacked sections was successful after application of these processing techniques.

Doll, W.E.

1997-12-31

102

129I in the environment of the La Hague nuclear fuel reprocessing plant--from sea to land.  

PubMed

In recent years, particular attention was paid to the long-lived radionuclides discharged with authorized low-level radioactive liquid and gaseous effluents by the nuclear spent fuel reprocessing plants of La Hague and Sellafield. The knowledge of (129)I (half-life=15.7 x 10(6) a) distribution in the environment is required to assess the radiological impact to the environment and population living in the area under the direct influence of La Hague NRP discharges. Measurement difficulties of (129)I in environmental matrices, where it is usually present at trace level, limited data published on (129)I activity levels in the European and more particularly in the French territory. Studies conducted to qualify a new alternative measurement method, direct gamma-X spectrometry with experimental self-absorption correction, led to test samples collected in the La Hague marine and terrestrial environment : seaweeds, lichens, grass, bovine thyroids, etc. All these results, often already published separately for analytical purposes and treated for intercomparison exercises, are presented here together in a radioecological manner. The levels of (129)I activity and (129)I/(127)I ratios in these samples show the spatial and temporal influence of the La Hague NRP in its local near-field environment as well as at the regional scale along the French Channel coast. PMID:12915059

Fréchou, C; Calmet, D

2003-01-01

103

Plasma-sprayed yttria-stabilized zirconia coatings on type 316L stainless steel for pyrochemical reprocessing plant  

NASA Astrophysics Data System (ADS)

Type 316L stainless steel (SS) is one of the candidate materials proposed for application in pyrochemical reprocessing plants. In the present work, yttria-stabilized zirconia coatings of 300 ?m were applied over type 316L SS with a metallic bond coating of 50 ?m by an optimized plasma spray process, and were assessed for the corrosion behaviour in molten LiCl-KCl medium at 873 K for periods of 5 h, 100 h, 250 h and 500 h. The as-coated and tested samples were examined by optical microscopy and SEM for homogeneity, penetration of molten salt through coating and corrosion of type 316L SS substrate. The results indicated that the yttria-stabilized zirconia coatings performed well without significant degradation and corrosion attack. Laser melting of the coated samples using CO 2 laser was attempted to consolidate the coatings. The development of large grains with segmented cracks was noticed after laser melting, though the coating defects have been eliminated.

Ravi Shankar, A.; Kamachi Mudali, U.; Sole, Ravikumar; Khatak, H. S.; Raj, Baldev

104

Concept of advanced spent fuel reprocessing based on ion exchange  

SciTech Connect

Reprocessing based on ion exchange separation is proposed as a safe, proliferation-resistant technology. Tertiary pyridine resin was developed for ion exchange reprocessing. Working medium of the separation system is not nitric acid but hydrochloric acid aqueous solution. The system does not involve strong oxidizing reagent, such as nitric acid but involve chloride ions which works as the week neutron absorbers. The system can be operated at ambient temperatures and pressure. Thus the HCl-ion-exchange reprocessing is regarded as an inherently safe technology. Another advantage of HCl ion-exchange reprocessing is the proliferation-resistant nature. Both U(VI) and Pu(IV) ions are adsorbed in the pyridine type anion exchange resin at relatively high HCl concentration of 6 M. At this condition, the adsorption distribution coefficient of Pu(IV) is smaller than that of U(VI). When uranium is eluted from the resin in the column, plutonium is simultaneously eluted from the column; Pu is recovered with uranium in the front part of uranium adsorption band. Pu(IV) can not be left in the resin after elution of uranium. The use of HCl in the ion-exchange reprocessing causes the problem of the plant materials. Sophisticated material technology is necessary to realize the ion exchange reprocessing using HCl. The technology is so sophisticated that only highly developed countries can hold the technology, thus the technology holding countries will be limited. The plant, therefore, cannot be built under hidden state. In addition, another merit of the process would be the simplicity in operation. One phase, i.e., ion exchange resin is immobile, and the aqueous solution is the only mobile phase. Plant operation is made by the control of one aqueous solution phase. The plant simplicity would ease the international safeguard inspection efforts to be applicable to this kind of reprocessing plant. The present work shows the basic concept of ion exchange reprocessing using HCl medium. Furthermore, the ion exchange is appropriate for multi-element mutual separation rather than single element extraction. In the future, ion exchange reprocessing would be expected to be the comprehensive separation process for spent fuels to recover precious and usable elements and to reduce the amount of wastes. (authors)

Suzuki, Tatsuya; Takahashi, Kazuyuki; Nogami, Masanobu; Nomura, Masao; Fujii, Yasuhiko [Tokyo Institute of Technology, 2-12-1 O-okayama, Meguroku, Tokyo 152-8550 (Japan); Ozawa, Masaki [Tokyo Institute of Technology, 2-12-1 O-okayama, Meguroku, Tokyo 152-8550 (Japan)]|[Japan Atomic Energy Agency (Japan); Koyama, Shinichi [Japan Atomic Energy Agency (Japan); Mimura, Hitosi [Tohoku University (Japan); Fujita, Reiko [Toshiba Corporation (Japan)

2007-07-01

105

Waste Isolation Pilot Plant Safety Analysis Report  

SciTech Connect

The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

NONE

1995-11-01

106

The 2010 ERC Directory of Waste-to-Energy Plants  

E-print Network

1 The 2010 ERC Directory of Waste-to-Energy Plants By Ted Michaels The 2010 ERC Directory of Waste-to-Energy Plants provides current information about the waste-to-energy sector in the United States. Since this Directory was last published in 2007, waste-to-energy capacity has increased for the first time in many

Columbia University

107

Nuclear shipping and waste disposal cost estimates  

Microsoft Academic Search

Cost estimates for the shipping of spent fuel from the reactor, shipping of waste from the reprocessing plant, and disposal of reprocessing plant wastes have been made for five reactor types. The reactors considered are the light-water reactor (LWR), the mixed-oxide-fueled light-water reactor (MOX), the Canadian deuterium-uranium reactor (CANDU), the fast breeder reactor (FBR), and the high-temperature gas-cooled reactor (HTGR).

C. R. II

2009-01-01

108

Aqueous Waste Treatment Plant at Aldermaston  

SciTech Connect

For over half a century the Pangbourne Pipeline formed part of AWE's liquid waste management system. Since 1952 the 11.5 mile pipeline carried pre-treated wastewater from the Aldermaston site for safe dispersal in the River Thames. Such discharges were in strict compliance with the exacting conditions demanded by all regulatory authorities, latterly, those of the Environment Agency. In March 2005 AWE plc closed the Pangbourne Pipeline and ceased discharges of treated active aqueous waste to the River Thames via this route. The ability to effectively eliminate active liquid discharges to the environment is thanks to an extensive programme of waste minimization on the Aldermaston site, together with the construction of a new Waste Treatment Plant (WTP). Waste minimization measures have reduced the effluent arisings by over 70% in less than four years. The new WTP has been built using best available technology (evaporation followed by reverse osmosis) to remove trace levels of radioactivity from wastewater to exceptionally stringent standards. Active operation has confirmed early pilot scale trials, with the plant meeting throughput and decontamination performance targets, and final discharges being at or below limits of detection. The performance of the plant allows the treated waste to be discharged safely as normal industrial effluent from the AWE site. Although the project has had a challenging schedule, the project was completed on programme, to budget and with an exemplary safety record (over 280,000 hours in construction with no lost time events) largely due to a pro-active partnering approach between AWE plc and RWE NUKEM and its sub-contractors. (authors)

Keene, D. [RWE NUKEM, Ltd, 424 Harwell, Didcot, Oxfordshire, OX 110GJ (United Kingdom); Fowler, J.; Frier, S. [AWE plc, Aldermaston, Berkshire RG7 4PR (United Kingdom)

2006-07-01

109

Pretreatment of Hanford PUREX Plant first-cycle waste  

Microsoft Academic Search

A process has been developed to pretreat neutralized, first-cycle high-level waste from the fuels reprocessing facility at the Hanford Site. The process separates solids from the supernate liquid, which contains soluble salts. The solids, including most of the fission products and transuranic elements, may then be vitrified for disposal, while the low-level supernate stream may be processed into a less

M. W. Gibson; D. M. Gerboth; B. B. Peters

1987-01-01

110

Reprocessing RERTR silicide fuels  

Microsoft Academic Search

The Reduced Enrichment Research and Test Reactor Program is one element of the United States Government's nonproliferation effort. High-density, low-enrichment, aluminum-clad uranium silicide fuels may be substituted for the highly enriched aluminum-clad alloy fuels now in use. Savannah River Laboratory has performed studies which demonstrate reprocessability of spent RERTR silicide fuels at Savannah River Plant. Results of dissolution and feed

G. C. Rodrigues; A. P. Gouge

1983-01-01

111

Reprocessing RERTR fuels  

Microsoft Academic Search

The Reduced Enrichment Research and Test Reactor Program is one element of the United States Government's nonproliferation effort. High density, low enrichment aluminum-clad dispersed uranium compound fuels may be substituted for the highly enriched aluminum-clad aluminum-uranium alloy fuels now in use. Savannah River Laboratory has performed studies which demonstrate reprocessability of spent RERTR fuels at Savannah River Plant. Results of

1983-01-01

112

Modelling of the nitric acid reduction process: Application to materials behavior in reprocessing plants  

SciTech Connect

In France, the recycling process of nuclear waste fuels involves the use of hot concentrated nitric acid. The understanding and the prediction of the structural materials (mainly austenitic stainless steels) behaviour requires the determination of the nitric acid reduction process. Nitric acid is indirectly reduced by an autocatalytic mechanism depending on the cathodic overpotential and the acid concentration. This mechanism has been widely studied. All the authors agree on its autocatalytic nature, characterized by the predominant role of the reduction products. It is also generally admitted that nitric acid or the nitrate ion are not the electro-active species. However, uncertainties remain concerning the nature of the electro-active species, the place where the catalytic species regenerates and the thermodynamic and kinetic behaviour of the reaction intermediates. The aim of this study is to clarify some of these uncertainties by performing an electrochemical investigation of the 4 mol.L -1 nitric acid reduction process at 40 deg. C occurring on an inert electrode (platinum or gold). An inert electrode was chosen as a working electrode in a first step in order to avoid its oxidation and focus the research on the reduction mechanism. This experimental work enabled to suggest a coherent sequence of electrochemical and chemical reactions. Then, a kinetic modelling of this sequence was carried out for a gold rotating disk system. In this objective, a thermodynamic study at 25 deg. C led to the evaluation of the composition of liquid and gaseous phases for nitric acid solutions from 0.5 to 22 mol.L -1. The kinetics of the reduction process of nitric acid 4 mol.L -1 was investigated by cyclic voltammetry and chrono-amperometry on an inert electrode at 40 deg. C. A coupling of chrono-amperometry and FTIR in gaseous phase led to the identification of the gaseous reduction products as a function of the cathodic overpotential. These different results showed that for potentials between 0.6 V/NHE and 1.15 V/NHE, the reduction process is autocatalytic. The regeneration of the electro-active species may take place at the surface of the electrode for lower over-potentials, and otherwise in solution. When the potential is lower than 0.6 V/ENH, the fast reduction of nitrogen oxide may lead to the rupture of the autocatalytic cycle. (authors)

Sicsic, D.; Balbaud-Celerier, F. [CEA, DEN SCCME, Laboratoire d'Etude de la Corrosion Non Aqueuse, F-91191 Gif-sur-Yvette (France); Tribollet, B. [Laboratoire Interfaces et Systemes Electrochimiques, UPR15 du CNRS, Universite Pierre et Marie Curie, 4 Place Jussieu, 75252 Paris Cedex 05 (France)

2012-07-01

113

Pyrochemical treatment of Idaho Chemical Processing Plant high-level waste calcine  

SciTech Connect

The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1951 to recover uranium, krypton-85, and isolated fission products for interim treatment and immobilization. The acidic radioactive high-level liquid waste (HLLW) is routinely stored in stainless steel tanks and then, since 1963, calcined to form a dry granular solid. The resulting high-level waste (HLW) calcine is stored in seismically hardened stainless steel bins that are housed in underground concrete vaults. A research and development program has been established to determine the feasibility of treating ICPP HLW calcine using pyrochemical technology.This technology is described.

Todd, T.A.; DelDebbio, J.A.; Nelson, L.O.; Sharpsten, M.R.

1993-06-01

114

Effect of reprocessing on the fatigue strength of a fibreglass reinforced polyamide  

Microsoft Academic Search

The mechanical recycling of short fibre reinforced thermoplastics by granulation and subsequent injection moulding allows for recovery of both post consumer waste and in-plant recycled material in many industrial sectors. Parts made of these materials are often subjected to cyclic loads and therefore need to be designed against fatigue. The fatigue behaviour of reprocessed glass fibre reinforced polyamide 6,6 has

A. Bernasconi; P. Davoli; D. Rossin; C. Armanni

2007-01-01

115

Hanford Waste Vitrification Plant capacity increase options  

SciTech Connect

Studies are being conducted by the Hanford Waste Vitrification Plant (HWVP) Project on ways to increase the waste processing capacity within the current Vitrification Building structural design. The Phase 1 study on remote systems concepts identification and extent of capacity increase was completed. The study concluded that the HWVP capacity could be increased to four times the current capacity with minor design adjustments to the fixed facility design, and the required design changes would not impact the current footprint of the vitrification building. A further increase in production capacity may be achievable but would require some technology development, verification testing, and a more systematic and extensive engineering evaluation. The primary changes included a single advance melter with a higher capacity, new evaporative feed tank, offgas quench collection tank, ejector venturi scrubbers, and additional inner canister closure station,a smear test station, a new close- coupled analytical facility, waste hold capacity of 400,000 gallon, the ability to concentrate out-of-plant HWVP feed to 90 g/L waste oxide concentration, and limited changes to the current base slab construction package.

Larson, D.E.

1996-04-01

116

In-plant management of hazardous waste  

SciTech Connect

One of the earliest sustainable technologies for the management of hazardous industrial wastes, and one of the most successful, is {open_quotes}In-Plant Control{close_quotes} Waste elimination, reuse and/or minimization can encourage improved utilization of resources, decreased environmental degradation and increased profits at individual industrial product ion sites, or within an industry. For new facilities and industries, putting such programs in place is relatively easy. Experience has shown, however, that this may be more difficult to initiate in existing facilities, especially in older and heavier industries. This task can be made easier by promoting a mutually respectful partnership between production and environmental interests within the facility or industry. This permits {open_quotes}common sense{close_quotes} thinking and a cooperative, proactive strategy for securing an appropriate balance between economic growth, environmental protection and social responsibility. Case studies are presented wherein a phased, incremental in-plant system for waste management was developed and employed to good effect, using a model that entailed {open_quotes}Consciousness, Commitment, Training, Recognition, Re-engineering and Continuous Improvement{close_quotes} to promote waste minimization or elimination.

Hall, M.W.; Howell, W.L. Jr. [FAMU/FSU College of Engineering, Tallahassee, FL (United States); [Engelhard Corporation, Savannah, GA (United States)

1995-12-31

117

Laboratory Testing of Waste Isolation Pilot Plant Surrogate Waste Materials  

NASA Astrophysics Data System (ADS)

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy geological repository for the permanent disposal of defense-related transuranic (TRU) waste. The waste is emplaced in rooms excavated in the bedded Salado salt formation at a depth of 655 m below the ground surface. After emplacement of the waste, the repository will be sealed and decommissioned. WIPP Performance Assessment modeling of the underground material response requires a full and accurate understanding of coupled mechanical, hydrological, and geochemical processes and how they evolve with time. This study was part of a broader test program focused on room closure, specifically the compaction behavior of waste and the constitutive relations to model this behavior. The goal of this study was to develop an improved waste constitutive model. The model parameters are developed based on a well designed set of test data. The constitutive model will then be used to realistically model evolution of the underground and to better understand the impacts on repository performance. The present study results are focused on laboratory testing of surrogate waste materials. The surrogate wastes correspond to a conservative estimate of the degraded containers and TRU waste materials after the 10,000 year regulatory period. Testing consists of hydrostatic, uniaxial, and triaxial tests performed on surrogate waste recipes that were previously developed by Hansen et al. (1997). These recipes can be divided into materials that simulate 50% and 100% degraded waste by weight. The percent degradation indicates the anticipated amount of iron corrosion, as well as the decomposition of cellulosics, plastics, and rubbers. Axial, lateral, and volumetric strain and axial and lateral stress measurements were made. Two unique testing techniques were developed during the course of the experimental program. The first involves the use of dilatometry to measure sample volumetric strain under a hydrostatic condition. Bulk moduli of the samples measured using this technique were consistent with those measured using more conventional methods. The second technique involved performing triaxial tests under lateral strain control. By limiting the lateral strain to zero by controlling the applied confining pressure while loading the specimen axially in compression, one can maintain a right-circular cylindrical geometry even under large deformations. This technique is preferred over standard triaxial testing methods which result in inhomogeneous deformation or "barreling". Manifestations of the inhomogeneous deformation included non-uniform stress states, as well as unrealistic Poisson's ratios (> 0.5) or those that vary significantly along the length of the specimen. Zero lateral strain controlled tests yield a more uniform stress state, and admissible and uniform values of Poisson's ratio. Hansen, F.D., Knowles, M.K., et al. 1997. Description and Evaluation of a Mechanistically Based Conceptual Model for Spall. SAND97-1369. Sandia National Laboratories, Albuquerque. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000.

Broome, S.; Bronowski, D.; Pfeifle, T.; Herrick, C. G.

2011-12-01

118

Nuclear Fuel Reprocessing  

SciTech Connect

Reprocessing is essential to closing nuclear fuel cycle. Natural uranium contains only 0.7 percent 235U, the fissile (see glossary for technical terms) isotope that produces most of the fission energy in a nuclear power plant. Prior to being used in commercial nuclear fuel, uranium is typically enriched to 3–5% in 235U. If the enrichment process discards depleted uranium at 0.2 percent 235U, it takes more than seven tonnes of uranium feed to produce one tonne of 4%-enriched uranium. Nuclear fuel discharged at the end of its economic lifetime contains less one percent 235U, but still more than the natural ore. Less than one percent of the uranium that enters the fuel cycle is actually used in a single pass through the reactor. The other naturally occurring isotope, 238U, directly contributes in a minor way to power generation. However, its main role is to transmute into plutoniumby neutron capture and subsequent radioactive decay of unstable uraniumand neptuniumisotopes. 239Pu and 241Pu are fissile isotopes that produce more than 40% of the fission energy in commercially deployed reactors. It is recovery of the plutonium (and to a lesser extent the uranium) for use in recycled nuclear fuel that has been the primary focus of commercial reprocessing. Uraniumtargets irradiated in special purpose reactors are also reprocessed to obtain the fission product 99Mo, the parent isotope of technetium, which is widely used inmedical procedures. Among the fission products, recovery of such expensive metals as platinum and rhodium is technically achievable, but not economically viable in current market and regulatory conditions. During the past 60 years, many different techniques for reprocessing used nuclear fuel have been proposed and tested in the laboratory. However, commercial reprocessing has been implemented along a single line of aqueous solvent extraction technology called plutonium uranium reduction extraction process (PUREX). Similarly, hundreds of types of reactor fuels have been irradiated for different purposes, but the vast majority of commercial fuel is uranium oxide clad in zirconium alloy tubing. As a result, commercial reprocessing plants have relatively narrow technical requirements for used nuclear that is accepted for processing.

Harold F. McFarlane; Terry Todd

2013-11-01

119

Camargo Waste to Energy Power Plant Hamed Zamenian1  

E-print Network

Camargo Waste to Energy Power Plant Hamed Zamenian1 , Eminou Nasser 1 , Matt Ray2 , Tom Iseley3 1 and Technology, IUPUI The Camargo Waste to Energy Power plant project is being proposed to dispose of Municipal are discarded in landfills. The Camargo Waste to Energy (WTE) power station is an opportunity to continue

Zhou, Yaoqi

120

Operating limit evaluation for disposal of uranium enrichment plant wastes  

Microsoft Academic Search

A proposed solid waste landfill at Paducah Gaseous Diffusion Plant (PGDP) will accept wastes generated during normal plant operations that are considered to be non-radioactive. However, nearly all solid waste from any source or facility contains small amounts of radioactive material, due to the presence in most materials of trace quantities of such naturally occurring radionuclides as uranium and thorium.

D. W. Lee; D. C. Kocher; J. C. Wang

1996-01-01

121

UPGRADING OF WASTE-TO-ENERGY PLANT IN BRESCIA, ITALY  

E-print Network

UPGRADING OF WASTE-TO-ENERGY PLANT IN BRESCIA, ITALY Client: ASM Brescia Financed by: The client, Italy Tel.: +39 030-35531 Rambøll is assisting the waste-to-energy plant of ASM Brescia in installing was one of the first cities to have a well-established district heating net- work. Today, the waste-to-energy

Columbia University

122

Advanced instrumentation for reprocessing.  

SciTech Connect

Recent interest in reprocessing nuclear fuel in the U.S. has led to advanced separations processes that employ continuous processing and multiple extraction steps. These advanced plants will need to be designed with state-of-the-art instrumentation for materials accountancy and control. This research examines the current and upcoming instrumentation for nuclear materials accountancy for those most suited to the reprocessing environment. Though this topic has received attention time and again in the past, new technologies and changing world conditions require a renewed look and this subject. The needs for the advanced UREX+ separations concept are first identified, and then a literature review of current and upcoming measuring techniques is presented. The report concludes with a preliminary list of recommended instruments and measurement locations.

Cipiti, Benjamin B.

2005-10-01

123

Waste Toolkit A-Z What is Plant Swap?  

E-print Network

.admin.ox.ac.uk/estates/environment/biodiversity How do I use Plant Swap? To join Swap Shop you need to... · Email kate.aydin@ admin plants, seeds, tools and other garden-related items! University areas that use Plant Swap includeWaste Toolkit A-Z Plant Swap What is Plant Swap? Plant Swap is a virtual reuse scheme

Melham, Tom

124

A glass-encapsulated calcium phosphate wasteform for the immobilization of actinide-, fluoride-, and chloride-containing radioactive wastes from the pyrochemical reprocessing of plutonium metal  

NASA Astrophysics Data System (ADS)

Chloride-containing radioactive wastes are generated during the pyrochemical reprocessing of Pu metal. Immobilization of these wastes in borosilicate glass or Synroc-type ceramics is not feasible due to the very low solubility of chlorides in these hosts. Alternative candidates have therefore been sought including phosphate-based glasses, crystalline ceramics and hybrid glass/ceramic systems. These studies have shown that high losses of chloride or evolution of chlorine gas from the melt make vitrification an unacceptable solution unless suitable off-gas treatment facilities capable of dealing with these corrosive by-products are available. On the other hand, both sodium aluminosilicate and calcium phosphate ceramics are capable of retaining chloride in stable mineral phases, which include sodalite, Na 8(AlSiO 4) 6Cl 2, chlorapatite, Ca 5(PO 4) 3Cl, and spodiosite, Ca 2(PO 4)Cl. The immobilization process developed in this study involves a solid state process in which waste and precursor powders are mixed and reacted in air at temperatures in the range 700-800 °C. The ceramic products are non-hygroscopic free-flowing powders that only require encapsulation in a relatively low melting temperature phosphate-based glass to produce a monolithic wasteform suitable for storage and ultimate disposal.

Donald, I. W.; Metcalfe, B. L.; Fong, S. K.; Gerrard, L. A.; Strachan, D. M.; Scheele, R. D.

2007-03-01

125

Materials management in an internationally safeguarded fuels reprocessing plant. [1500 and 210 metric tons heavy metal per year  

SciTech Connect

The first volume of this report summarizes the results and conclusions for this study of conventional and advanced nuclear materials accounting systems applicable for both large (1500 MTHM/y) and small (210 MTHM/y) spent-fuel reprocessing facilities subject to international verification.

Hakkila, E.A.; Cobb, D.D.; Dayem, H.A.; Dietz, R.J.; Kern, E.A.; Markin, J.T.; Shipley, J.P.; Barnes, J.W.; Scheinman, L.

1980-04-01

126

Codigestion of manure and organic wastes in centralized biogas plants  

Microsoft Academic Search

Centralized biogas plants in Denmark codigest mainly manure, together with other organic waste such as industrial organic\\u000a waste, source sorted household waste, and sewage sludge. Today 22 large-scale centralized biogas plants are in operation in\\u000a Denmark, and in 2001 they treated approx 1.2 million tons of manure as well as approx 300,000 of organic industrial waste.\\u000a Besides the centralized biogas

I. Angelidaki; L. Ellegaard

2003-01-01

127

Making Plant-Support Structures From Waste Plant Fiber  

NASA Technical Reports Server (NTRS)

Environmentally benign, biodegradable structures for supporting growing plants can be made in a process based on recycling of such waste plant fiber materials as wheat straw or of such derivative materials as paper and cardboard. Examples of structures that can be made in this way include plant plugs, pots, planter-lining mats, plant fences, and root and shoot barriers. No chemical binders are used in the process. First, the plant material is chopped into smaller particles. The particles are leached with water or steam to remove material that can inhibit plant growth, yielding a fibrous slurry. If the desired structures are plugs or sheets, then the slurry is formed into the desired shapes in a pulp molding subprocess. If the desired structures are root and shoot barriers, pots, or fences, then the slurry is compression-molded to the desired shapes in a heated press. The processed materials in these structures have properties similar to those of commercial pressboard, but unlike pressboard, these materials contain no additives. These structures have been found to withstand one growth cycle, even when wet

Morrow, Robert C.; < oscjmocl. < attjew K/; {ertzbprm. A,amda; Ej (e. Cjad); Hunt, John

2006-01-01

128

Reduction in waste load from a meat processing plant: Beef  

SciTech Connect

;Contents: Introduction (Randolph Packing Company, Meat Plant Wastewaters, Slaughterhouses, Packing Houses, Sources of Wastewater, Secondary Manufacturing Processes, An Example of Water Conservation and Waste Control, Water Conservation Program); Plant Review and Survey (Survey for Product Losses and Wastes, Water Use and Waste Load, Wastewater Discharge Limitations and Costs); Waste Centers, Changes, Costs and Results (In-Plant Control Measures, Water Conservation, Recovery Products, By-Products and Reducing Waste Load, Blood Conservation, Paunch Handling and Processing, Summary of Process Changes, Pretreatment, Advantages and Disadvantages of Pretreatment, Pretreatment Systems).

NONE

1986-10-31

129

FY 1985 summary of WIPP (Waste Isolation Pilot Plant) waste package corrosion and metallurgy laboratory research  

Microsoft Academic Search

This document serves as the technical summary report for all ''waste package interactions technology'' laboratory studies conducted during Fiscal Year 1985 on the topics of nuclear waste container corrosion and metallurgical evaluations. The research focuses predominantly on the ASTM alloy Grade-12 titanium. These studies are part of the Waste Isolation Pilot Plant (WIPP) - Waste Package Performance experimental program. The

M. A. Molecke; J. A. Van Den Avyle

1988-01-01

130

Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2  

SciTech Connect

This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.

NONE

1998-01-23

131

Waste Isolation Pilot Plant, Land Management Plan  

SciTech Connect

To reflect the requirement of section 4 of the Wastes Isolation Pilot Plant Land Withdrawal Act (the Act) (Public Law 102-579), this land management plan has been written for the withdrawal area consistent with the Federal Land Policy and Management Act of 1976. The objective of this document, per the Act, is to describe the plan for the use of the withdrawn land until the end of the decommissioning phase. The plan identifies resource values within the withdrawal area and promotes the concept of multiple-use management. The plan also provides opportunity for participation in the land use planning process by the public and local, State, and Federal agencies. Chapter 1, Introduction, provides the reader with the purpose of this land management plan as well as an overview of the Waste Isolation Pilot Plant. Chapter 2, Affected Environment, is a brief description of the existing resources within the withdrawal area. Chapter 3, Management Objectives and Planned Actions, describes the land management objectives and actions taken to accomplish these objectives.

Not Available

1993-12-01

132

Vitrification of Polyvinyl Chloride Waste from Korean Nuclear Power Plants  

SciTech Connect

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

Sheng, Jiawei [Kyoto University (Japan); Choi, Kwansik [Nuclear Environment Technology Institute (Korea, Republic of); Yang, Kyung-Hwa [Nuclear Environment Technology Institute (Korea, Republic of); Lee, Myung-Chan [Nuclear Environment Technology Institute (Korea, Republic of); Song, Myung-Jae [Nuclear Environment Technology Institute (Korea, Republic of)

2000-02-15

133

Reprocessing RERTR fuels  

SciTech Connect

The Reduced Enrichment Research and Test Reactor Program is one element of the United States Government's nonproliferation effort. High density, low enrichment aluminum-clad dispersed uranium compound fuels may be substituted for the highly enriched aluminum-clad aluminum-uranium alloy fuels now in use. Savannah River Laboratory has performed studies which demonstrate reprocessability of spent RERTR fuels at Savannah River Plant. Results of dissolution and feed preparation tests with both unirradiated and irradiated (up to approximately 90% burnup) fuels are presented. 13 references, 2 figures, 4 tables.

Rodrigues, G.C.

1983-01-01

134

Economic Aspects of Civilian Reprocessing in China  

Microsoft Academic Search

Currently, China is pursuing a long-term expansion of its nuclear power program and plans to reprocess the resulting civilian spent fuel, recycling the plutonium in MOX fuel for LWRs and in fast breeder reactors. China presently operates three civilian nuclear power reactors, but it plans to build about 20 reactors by 2020. A pilot civilian reprocessing plant has been built

Hui Zhang

135

Polymer solidification of mixed wastes at the Rocky Flats Plant  

Microsoft Academic Search

The Rocky Flats Plant is pursuing polymer solidification as a viable treatment option for several mixed waste streams that are subject to land disposal restrictions within the Resource Conservation and Recovery Act provisions. Tests completed to date using both surrogate and actual wastes indicate that polyethylene microencapsulation is a viable treatment option for several mixed wastes at the Rocky Flats

A. M. Faucette; B. W. Logsdon; J. J. Lucerna; R. J. Yudnich

1994-01-01

136

Treatment of molten salt wastes by phosphate precipitation: removal of fission product elements after pyrochemical reprocessing of spent nuclear fuels in chloride melts  

NASA Astrophysics Data System (ADS)

The removal of fission product elements from molten salt wastes arising from pyrochemical reprocessing of spent nuclear fuels has been investigated. The experiments were conducted in LiCl-KCl eutectic at 550 °C and NaCl-KCl equimolar mixture at 750 °C. The behavior of the following individual elements was investigated: Cs, Mg, Sr, Ba, lanthanides (La to Dy), Zr, Cr, Mo, Mn, Re (to simulate Tc), Fe, Ru, Ni, Cd, Bi and Te. Lithium and sodium phosphates were used as precipitants. The efficiency of the process and the composition of the solid phases formed depend on the melt composition. The distribution coefficients of these elements between chloride melts and precipitates were determined. Some volatile chlorides were produced and rhenium metal was formed by disproportionation. Lithium-free melts favor formation of double phosphates. Some experiments in melts containing several added fission product elements were also conducted to study possible co-precipitation reactions. Rare earth elements and zirconium can be removed from both the systems studied, but alkaline earth metal fission product elements (Sr and Ba) form precipitates only in NaCl-KCl based melts. Essentially the reverse behavior was found with magnesium. Some metals form oxide rather than phosphate precipitates and the behavior of certain elements is solvent dependent. Caesium cannot be removed completely from chloride melts by a phosphate precipitation technique.

Volkovich, Vladimir A.; Griffiths, Trevor R.; Thied, Robert C.

2003-11-01

137

An overview of the ORNL waste handling and packaging plant, a major processing facility for remote-handled transuranic waste  

Microsoft Academic Search

The Waste Handling and Packaging Plant (WHPP) is identified as a key element in the US Department of Energy's transuranic (TRU) waste program for both remote handled (RH) and special case (SC) waste. The mission of the facility is to retrieve, receive, repackage, certify, and ship TRU waste to the Waste Isolation Pilot Plant (WIPP) located near Carlsbad, New Mexico.

C. H. Jr. Brown; J. B. Berry; D. W. Turner

1989-01-01

138

Waste analysis plan for T Plant Complex  

SciTech Connect

Washington Administration Code 173-303-300 requires that a waste analysis plan (WAP) be provided by a treatment, storage, and/or disposal (TSD) unit to confirm their knowledge about a dangerous and/or mixed waste to ensure that the waste is managed properly. The specific objectives of the WAP are as follows: Ensure safe management of waste during treatment and storage; Ensure that waste generated during operational activities is properly designated in accordance with regulatory requirements; Provide chemical and physical analysis of representative samples of the waste stored for characterization and/or verification before the waste is transferred to another TSD unit; Ensure compliance with land disposal restriction (LDR) requirements for treated waste; and Provide basis for work plans that describes waste analysis for development of new treatment technologies.

Williams, J.F.

1996-04-12

139

Near-field krypton-85 measurements in stable meteorological conditions around the AREVA NC La Hague reprocessing plant: estimation of atmospheric transfer coefficients.  

PubMed

The aim of this work was to study the near-field dispersion of (85)Kr around the nuclear fuel reprocessing plant at La Hague (AREVA NC La Hague - France) under stable meteorological conditions. Twenty-two (85)Kr night-time experimental campaigns were carried out at distances of up to 4 km from the release source. Although the operational Gaussian models predict for these meteorological conditions a distance to plume touchdown of several kilometers, we almost systematically observed a marked ground signal at distances of 0.5-4 km. The calculated atmospheric transfer coefficients (ATC) show values (1) higher than those observed under neutral conditions, (2) much higher than those proposed by the operational models, and (3) higher than those used in the impact assessments. PMID:25078471

Connan, O; Solier, L; Hébert, D; Maro, D; Lamotte, M; Voiseux, C; Laguionie, P; Cazimajou, O; Le Cavelier, S; Godinot, C; Morillon, M; Thomas, L; Percot, S

2014-11-01

140

Cattle waste reduces plant diversity in vernal pool mesocosms  

Microsoft Academic Search

In California, much of the remaining vernal pool habitat is used for cattle grazing. Some studies suggest that grazing helps promote native plant diversity on grasslands, but the impact of grazing on plants that reside in pool basins is largely unknown. We investigated how one aspect of cattle grazing, the deposition of waste, affects these plant species by adding dung

Russell C. Croel; Jamie M. Kneitel

2011-01-01

141

IR and Raman Spectroscopy of Sodium-Aluminophosphate Glasses for Immobilizing High-Level Wastes from Spent Nuclear Fuel Reprocessing  

NASA Astrophysics Data System (ADS)

The structure of sodium-aluminophosphate glasses containing constituents of high-level wastes (cesium, magnesium, copper, and molybdenum oxides) from uranium-graphite reactors was studied by IR and Raman spectroscopy coupled with x-ray diffraction. The structural network was shown to be composed of short P-O chains with embedded AlO4 tetrahedra. Cross-linking by Mg2+ was possible in the Mg-bearing samples. The effect of the other oxides (Cs2O, MoO3, CuO) on the glass structure was negligible for the occurring amounts. The glasses devitrified partially upon quenching and more strongly upon annealing. This was reflected in splitting of the vibrational bands for bonds in the glass anionic structural motif.

Stefanovsky, S. V.; Myasoedov, B. F.; Remizov, M. B.; Belanova, E. A.

2014-09-01

142

MICROORGANISMS AND HIGHER PLANTS FOR WASTE WATER TREATMENT  

EPA Science Inventory

Batch experiments were conducted to compare the waste water treatment efficiencies of plant-free microbial filters with filters supporting the growth of reeds (Phragmites communis), cattail (Typha latifolia), rush (Juncus effusus), and bamboo (Bambusa multiplex). The experimental...

143

WASTE MANAGEMENT CONTROL HANDBOOK FOR DAIRY FOOD PLANTS  

EPA Science Inventory

Waste control is resource management control in dairy food plant operations. Appreciable reductions can be achieved in product, water, energy, labor, packaging losses and sewer surcharges. A good program in waste control can increase the profit margin by more than 10%, as well as...

144

Nevada Nuclear Waste Storage Investigations Project interim acceptance specifications for Defense Waste Processing Facility and West Valley Demonstration Project waste forms and canisterized waste  

SciTech Connect

The waste acceptance specifications presented in this document represent the first stage of the Nevada Nuclear Waste Storage Investigations Project effort to establish specifications for the acceptance of waste forms for disposal at a nuclear waste repository in Yucca Mountain tuff. The only waste forms that will be dealt with in this document are the reprocessed waste forms resulting from solidification of the Savannah River Plant defense high level waste and the West Valley high level wastes. Specifications for acceptance of spent fuel will be covered in a separate document.

Oversby, V.M.

1984-08-01

145

Fuel Cell Power PlantsFuel Cell Power Plants Renewable and Waste Fuels  

E-print Network

z ETHANOL z WASTE METHANE z BIOGASz BIOGAS z COAL GAS Diversity of Fuels plus High Efficiency ­ HighFuel Cell Power PlantsFuel Cell Power Plants Renewable and Waste Fuels DOE-DOD Workshop WashingtonCell and "DFC" are all registered trademarks (®) of FuelCell Energy, Inc. Fuels Diversity and Efficiency

146

Demonstration of the TRUEX process for the treatment of actual high activity tank waste at the INEEL using centrifugal contactors  

Microsoft Academic Search

The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering and Environmental Laboratory (INEEL), formerly reprocessed spent nuclear fuel to recover fissionable uranium. The radioactive raffinates from the solvent extraction uranium recovery processes were converted to granular solids (calcine) in a high temperature fluidized bed. A secondary liquid waste stream was generated during the course of reprocessing, primarily

J. D. Law; K. N. Brewer; T. A. Todd; L. G. Olson

1997-01-01

147

Waste Isolation Pilot Plant Environmental Monitoring Plan  

SciTech Connect

U.S. Department of Energy (DOE) Order 450.1, Environmental Protection Program, requires each DOE site to conduct environmental monitoring. Environmental monitoring at the Waste Isolation Pilot Plant (WIPP) is conducted in order to: (a) Verify and support compliance with applicable federal, state, and local environmental laws, regulations, permits, and orders; (b) Establish baselines and characterize trends in the physical, chemical, and biological condition of effluent and environmental media; (c) Identify potential environmental problems and evaluate the need for remedial actions or measures to mitigate the problem; (d) Detect, characterize, and report unplanned releases; (e) Evaluate the effectiveness of effluent treatment and control, and pollution abatement programs; and (f) Determine compliance with commitments made in environmental impact statements, environmental assessments, safety analysis reports, or other official DOE documents. This Environmental Monitoring Plan (EMP) has been written to contain the rationale and design criteria for the monitoring program, extent and frequency of monitoring and measurements, procedures for laboratory analyses, quality assurance (QA) requirements, program implementation procedures, and direction for the preparation and disposition of reports. Changes to the environmental monitoring program may be necessary to allow the use of advanced technology and new data collection techniques. This EMP will document any proposed changes in the environmental monitoring program. Guidance for preparation of Environmental Monitoring Plans is contained in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance. The plan will be effective when it is approved by the appropriate Head of Field Organization or their designee. The plan discusses major environmental monitoring and hydrology activities at the WIPP and describes the programs established to ensure that WIPP operations do not have detrimental effects on the environment. This EMP is to be reviewed annually and updated every three years unless otherwise requested by the DOE or contractor.

Washington Regulatory and Environmental Services; Washington TRU Solutions LLC

2004-02-19

148

Waste acceptance criteria for the Waste Isolation Pilot Plant. Revision 4  

SciTech Connect

This Revision 4 of the Waste Acceptance Criteria (WAC), WIPP-DOE-069, identifies and consolidates existing criteria and requirements which regulate the safe handling and preparation of Transuranic (TRU) waste packages for transportation to and emplacement in the Waste Isolation Pilot Plant (WIPP). This consolidation does not invalidate any existing certification of TRU waste to the WIPP Operations and Safety Criteria (Revision 3 of WIPP-DOE--069) and/or Transportation: Waste Package Requirements (TRUPACT-II Safety Analysis Report for Packaging [SARP]). Those documents being consolidated, including Revision 3 of the WAC, currently support the Test Phase.

Not Available

1991-12-01

149

Uptake by plants of radionuclides from FUSRAP waste materials  

SciTech Connect

Radionuclides from FUSRAP wastes potentially may be taken up by plants during remedial action activities and permanent near-surface burial of contaminated materials. In order to better understand the propensity of radionuclides to accumulate in plant tissue, soil and plant factors influencing the uptake and accumulation of radionuclides by plants are reviewed. In addition, data describing the uptake of the principal radionuclides present in FUSRAP wastes (uranium-238, thorium-230, radium-226, lead-210, and polonium-210) are summarized. All five radionuclides can accumulate in plant root tissue to some extent, and there is potential for the translocation and accumulation of these radionuclides in plant shoot tissue. Of these five radionuclides, radium-226 appears to have the greatest potential for translocation and accumulation in plant shoot tissue. 28 references, 1 figure, 3 tables.

Knight, M.J.

1983-04-01

150

AQUATIC PLANTS FOR BIOREMEDIATION OF WASTE WATER  

Microsoft Academic Search

The ability of aquatic plants to accumulate heavy metals was examined in Bahr in El Bakar drain as one of the first sized drains in Egypt heavily polluted with heavy metals. Metal enrichment was found to be dependent on the plant species and metal type. The most efficient plant species in accumulating heavy metals were Eichhornia crassipes (floating plant), Ceratophyllum

Assia A. El Falaky; S. A. Aboulroos; A. A. Saoud; M. A. Ali

151

Facing the challenge of nuclear waste  

Microsoft Academic Search

The Tennessee Valley Authority (TVA) is going ahead with plans to safely store hazardous wastes from its nuclear power plants while national policies are developed for permanent storage. TVA had planned to use temporary open pool storage at the plant site and recycle uranium and plutonium until the reprocessing moratorium was imposed. The storage space has since been redesigned to

DeLaughter

2009-01-01

152

Radiological Monitoring of Waste Treatment Plant  

NASA Astrophysics Data System (ADS)

Scheduled waste in West Malaysia is handled by Concession Company and is stored and then is incinerated. It is known that incineration process may result in naturally occurring radioactive materials (NORM) to be concentrated. In this study we have measured three samples consist of by-product from the operation process such as slag, filter cake and fly ash. Other various environmental media such as air, surface water, groundwater and soil within and around the plant have also been analysed for their radioactivity levels. The concentration of Ra-226, Ac-228 and K-40 in slag are 0.062 Bq/g, 0.016 Bq/g and 0.19 Bq/g respectively. The total activity (Raeq) in slag is 99.5 Bq/kg. The concentration in fly ash is 0.032 Bq/g, 0.16 Bq/g and 0.34 Bq/g for Ra-226, Ac-228 and K-40 respectively resulting in Raeq of 287.0 Bq/kg. For filter cake, the concentration is 0.13 Bq/g, 0.031 Bq/g and 0.33 Bq/g for Ra-226, Ac-228 and K-40 respectively resulting in Raeq of 199.7 Bq/kg. The external radiation level ranges from 0.08 ?Sv/h (Administrative building) to 0.35 ?Sv/h (TENORM storage area). The concentration level of radon and thoron progeny varies from 0.0001 to 0.0016 WL and 0.0006 WL to 0.002 WL respectively. For soil samples, the activity ranges from 0.11 Bq/g to 0.29 Bq/g, 0.06 Bq/g to 0.18 Bq/g and 0.065 Bq/g to 0.38 Bq/g for Ra-226, Ac-228 and K-40 respectively. While activity in water, except for a trace of K-40, it is non-detectable.

Amin, Y. M.; Nik, H. W.

2011-03-01

153

Mobile power plants : waste body heat recovery  

E-print Network

Novel methods to convert waste metabolic heat into useful and useable amounts of electricity were studied. Thermoelectric, magneto hydrodynamic, and piezo-electric energy conversions at the desired scope were evaluated to ...

Gibbons, Jonathan S. (Jonathan Scott), 1979-

2004-01-01

154

Waste Minimization Policy at the Romanian Nuclear Power Plant  

SciTech Connect

The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) in Romania was designed to maintain acceptable levels of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation. In accordance with terminology of the International Atomic Energy Agency (IAEA), this system consists of the ''pretreatment'' of solid and organic liquid radioactive waste, which may include part or all of the following activities: collection, handling, volume reduction (by an in-drum compactor, if appropriate), and storage. Gaseous and aqueous liquid wastes are managed according to the ''dilute and discharge'' strategy. Taking into account the fact that treatment/conditioning and disposal technologies are still not established, waste minimization at the source is a priority environmental management objective, while waste minimization at the disposal stage is presently just a theoretical requirement for future adopted technologies . The necessary operational and maintenance procedures are in place at Cernavoda to minimize the production and contamination of waste. Administrative and technical measures are established to minimize waste volumes. Thus, an annual environmental target of a maximum 30 m3 of radioactive waste volume arising from operation and maintenance has been established. Within the first five years of operations at Cernavoda NPP, this target has been met. The successful implementation of the waste minimization policy has been accompanied by a cost reduction while the occupational doses for plant workers have been maintained at as low as reasonably practicable levels. This paper will describe key features of the waste management system along with the actual experience that has been realized with respect to minimizing the waste volumes at the Cernavoda NPP.

Andrei, V.; Daian, I.

2002-02-26

155

Waste Isolation Pilot Plant (WIPP) fact sheet  

SciTech Connect

Pursuant to the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (RCRA), as amended (42 USC 6901, et seq.), and the New Mexico Hazardous Waste Act (Section 74-4-1 et seq., NMSA 1978), Permit is issued to the owner and operator of the US DOE, WIPP site (hereafter called the Permittee(s)) to operate a hazardous waste storage facility consisting of a container storage unit (Waste Handling Building) and two Subpart X miscellaneous below-ground storage units (Bin Scale Test Rooms 1 and 3), all are located at the above location. The Permittee must comply with all terms and conditions of this Permit. This Permit consists of the conditions contained herein, including the attachments. Applicable regulations cited are the New Mexico Hazardous Waste Management Regulations, as amended 1992 (HWMR-7), the regulations that are in effect on the date of permit issuance. This Permit shall become effective upon issuance by the Secretary of the New Mexico Environment Department and shall be in effect for a period of ten (10) years from issuance. This Permit is also based on the assumption that all information contained in the Permit application and the administrative record is accurate and that the activity will be conducted as specified in the application and the administrative record. The Permit application consists of Revision 3, as well as associated attachments and clarifying information submitted on January 25, 1993, and May 17, 1993.

Not Available

1993-10-01

156

Nuclear fuel reprocessing  

Microsoft Academic Search

Reprocessing of spent nuclear fuel is a relatively simple, well-developed, and successful technology. Large, expensive reprocessing facilities are in use, principally in the UK and France, and are under construction in Japan and the CIS. As in most industrial processes, the viability of the process depends on the usefulness of its function and products, operational costs, and the economics of

Foreman

1992-01-01

157

Water recovery using waste heat from coal fired power plants.  

SciTech Connect

The potential to treat non-traditional water sources using power plant waste heat in conjunction with membrane distillation is assessed. Researchers and power plant designers continue to search for ways to use that waste heat from Rankine cycle power plants to recover water thereby reducing water net water consumption. Unfortunately, waste heat from a power plant is of poor quality. Membrane distillation (MD) systems may be a technology that can use the low temperature waste heat (<100 F) to treat water. By their nature, they operate at low temperature and usually low pressure. This study investigates the use of MD to recover water from typical power plants. It looks at recovery from three heat producing locations (boiler blow down, steam diverted from bleed streams, and the cooling water system) within a power plant, providing process sketches, heat and material balances and equipment sizing for recovery schemes using MD for each of these locations. It also provides insight into life cycle cost tradeoffs between power production and incremental capital costs.

Webb, Stephen W.; Morrow, Charles W.; Altman, Susan Jeanne; Dwyer, Brian P.

2011-01-01

158

Waste Heat Recovery in Cement Plants By Fluidized Beds  

E-print Network

completed an analysis of the potential returns from power pro duction at a cement plant with waste heat recovery. The specific example presented is for an integrated design. The major equipment required are a boiler, a waste heat recovery unit, baghouse... feed water treatment Condenser cooling water ? It Turbine generator Materials Handling ? Baghouse ? In9trumentation ? Utility interconnects ? Site Compatability - A site layout with equipment J required for on-site power generation is shown...

Fraley, L. D.; Ksiao, H. K.; Thunem, C. B.

1984-01-01

159

B Plant low level waste system integrity assessment report  

SciTech Connect

This document provides the report of the integrity assessment activities for the B Plant low level waste system. The assessment activities were in response to requirements of the Washington State Dangerous Waste Regulations, Washington Administrative Code (WAC), 173-303-640. This integrity assessment report supports compliance with Hanford Federal Facility Agreement and Consent Order interim milestone target action M-32-07-T03.

Walter, E.J.

1995-09-01

160

Waste-heat-driven refrigeration plants for freezer trawlers  

SciTech Connect

An analysis is made of the possibility of utilizing waste heat from a proposed gas-turbine fishing-vessel propulsion engine to power a refrigeration plant. On the basis of superior volume, maintenance and reliability, and cost and availability, the ammonia-water absorption system is chosen over the other waste-heat-driven option considered. It is found to be comparable in volume and in maintenance and reliability to the conventional vapor-compression system.

Kellen, A.D.

1986-01-01

161

Assessing pollutions of soil and plant by municipal waste dump  

Microsoft Academic Search

Research is few in the literature regarding the investigation and assessment of pollutions of soil and plant by municipal\\u000a waste dumps. Based upon previous work in seven waste dumping sites (nonsanitary landfills) in Beijing, Shanghai and Shijiazhuang,\\u000a this study expounds the investigation and assessment method and report major pollutants. Using relative background values,\\u000a this study assesses soil pollution degree in

Changli Liu; Yun Zhang; Feng’e Zhang; Sheng Zhang; Miying Yin; Hao Ye; Hongbing Hou; Hua Dong; Ming Zhang; Jianmei Jiang; Lixin Pei

2007-01-01

162

Final environmental impact statement. Waste Isolation Pilot Plant  

SciTech Connect

This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described. (DMC)

Not Available

1980-10-01

163

Hong Kong plans new generation chemical waste plant for 1993  

SciTech Connect

The first comprehensive chemical waste treatment facility in a Pacific Rim country is scheduled for completion in Hong Kong in early 1993. Designed to treat industrial chemical wastes generated in Hong Kong and vicinity, the plant will have an output consisting of environmentally safe materials, energy, and some recovered products. The new waste treatment facility will be located on Tsing-yi Island, which is connected to the New Territories by road, near Ha Kwai Chung. The island is close to the main harbor and western shipping channel, providing immediate access to the Pearl River and Guangzhou (Canton).

Haggin, J. (C and EN, Chicago, IL (US))

1991-02-01

164

Development of Ag°Z for bulk ¹²⁹I removal from nuclear fuel reprocessing plants and PbX for ¹²⁹I storage  

Microsoft Academic Search

Tests were conducted to develop Ag-exchanged mordenite (AgZ) for removal of gaseous ¹²⁹I from nuclear fuel reprocessing plants. The effects of bed depth and hydrogen pretreatment on the elemental (Iâ) iodine loading of AgZ were examined. The tests indicated that reduced AgZ (Ag°Z) had about twice the capacity for iodine as AgZ, and at least 15-cm bed depths should be

T. R. Thomas; B. A. Staples; L. P. Murphy

1978-01-01

165

Transformative monitoring approaches for reprocessing.  

SciTech Connect

The future of reprocessing in the United States is strongly driven by plant economics. With increasing safeguards, security, and safety requirements, future plant monitoring systems must be able to demonstrate more efficient operations while improving the current state of the art. The goal of this work was to design and examine the incorporation of advanced plant monitoring technologies into safeguards systems with attention to the burden on the operator. The technologies examined include micro-fluidic sampling for more rapid analytical measurements and spectroscopy-based techniques for on-line process monitoring. The Separations and Safeguards Performance Model was used to design the layout and test the effect of adding these technologies to reprocessing. The results here show that both technologies fill key gaps in existing materials accountability that provide detection of diversion events that may not be detected in a timely manner in existing plants. The plant architecture and results under diversion scenarios are described. As a tangent to this work, both the AMUSE and SEPHIS solvent extraction codes were examined for integration in the model to improve the reality of diversion scenarios. The AMUSE integration was found to be the most successful and provided useful results. The SEPHIS integration is still a work in progress and may provide an alternative option.

Cipiti, Benjamin B.

2011-09-01

166

An overview of the waste handling and packaging plant, a major processing facility for remote-handled transuranic waste  

Microsoft Academic Search

The Waste Handling and Packaging Plant (WHPP) is a FY 1991 line item project proposed for construction at the Oak Ridge National Laboratory (ORNL). The purpose of the facility is to receive, package, certify and ship remote-handled (RH) and special case (SC) transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The scope of the

D. W. Turner; R. C. Stewart; S. P. du Mont

1988-01-01

167

Preconceptual design study for solidifying high-level waste: Appendices A, B and C West Valley Demonstration Project  

Microsoft Academic Search

This report presents a preconceptual design study for processing radioactive high-level liquid waste presently stored in underground tanks at Western New York Nuclear Service Center (WNYNSC) near West Valley, New York, and for incorporating the radionculides in that waste into a solid. The high-level liquid waste accumulated from the operation of a chemical reprocessing plant by the Nuclear Fuel Services,

Hill

1981-01-01

168

Results from simulated remote-handled transuranic waste experiments at the Waste Isolation Pilot Plant (WIPP)  

Microsoft Academic Search

Multi-year, simulated remote-handled transuranic waste (RH TRU, nonradioactive) experiments are being conducted underground in the Waste Isolation Pilot-Plant (WIPP) facility. These experiments involve the near-reference (thermal and geometrical) testing of eight full size RH TRU test containers emplaced into horizontal, unlined rock salt boreholes. Half of the test emplacements are partially filled with bentonite\\/silica-sand backfill material. All test containers were

Molecke

1992-01-01

169

Waste Energy Analysis Recovery for a Typical Food Processing Plant  

E-print Network

An energy analysis made for the Joan of Arc Food Processing Plant in St. Francisville, Louisiana indicated that a significant quantity of waste heat energy was being released to the atmosphere in the forms of low quality steam and hot flue gases...

Miller, P. H.; Mann, L., Jr.

1980-01-01

170

Determination of transuranium elements in nuclear power plant wastes  

Microsoft Academic Search

During the operation of nuclear reactors, various a-emitting isotopes and activation products, coming from the surface contamination of fuel elements or from the fuel itself due to leaking through possible cracks or damage of the enclosure, may appear in nuclear power plant wastes. It is known that in the case of uranium-based fuel elements, isotopes of uranium, neptunium and plutonium

I. Gresits; S. Tölgyesi; J. Solymosi; R. Chobola; L. G. Nagy; T. Past; L. Szabó; P. Ormai

1996-01-01

171

Rubber lining for FGD scrubbers for waste incinerator plants  

SciTech Connect

Flue gas desulfurization scrubbers for waste incineration plants can be lined with soft rubber or hard rubber for corrosion protection. Hard rubber is cured under high temperature and pressure in an autoclave. The advantage of hard rubber is the excellent temperature and chemical resistance. The authors have experience with hard rubber lined scrubbers that are in service without failures for over 20 years.

Rullmann, H.E. [Smith Corrosion Services, Inc., Houston, TX (United States)

1999-11-01

172

ENVIRONMENTAL CONTROLS FOR WASTE-TO-ENERGY PLANTS  

EPA Science Inventory

The paper provides a literature review of selected, published literature relative to the performance of certain pollution control technologies that have been applied to Waste-to-Energy (WTE) plants. It discusses various environmental standards which have been adopted by three Eur...

173

Treatment of waste water from marine products processing plants  

Microsoft Academic Search

Different types of pollutants produced as by?products in various marine product processing plants are described. A detailed discussion on the effects of these polluting materials on the environment follows. Various technologies available for treating waste water contaminated with the above are introduced. Methods are described for evaluating various processing methods and choosing a method that meets individual processing requirements based

Kazuo Sano

1988-01-01

174

Mitigation of plant penetration into radioactive waste utilizing herbicides  

SciTech Connect

This paper describes the use of herbicides as an effective method of precluding plant root penetration into buried radioactive wastes. The discussed surface applications are selective herbicides to control broadleaf vegetation in grasses; nonselective herbicides, which control all vegetation; and slow-release forms of these herbicides to prolong effectiveness.

Cox, G.R.

1982-01-01

175

Solidification\\/Stabilization of Power Plants Wastes Potential Water Pollutants  

Microsoft Academic Search

The intensive firing of coal in power plants can harm the environment. The problems are caused by the emission of solid particles, sulphur oxides, nitrogen oxides, carbon monoxide, carbon dioxide to the atmosphere, as well as by pollution of the surrounding waters and the degradation of the land due to the disposition of the solid wastes: fly ash, bottom ash

Aleksandra Kosti?-Pulek; Svetlana Popov

176

T:\\013.ffentlichkeitsarbeit\\05.Vortrge\\32.NAWTEC 11 Florida 2003\\A_Ways to Improve the Efficiency of Waste to Energy Plants.doc Ways to Improve the Efficiency of Waste to Energy Plants  

E-print Network

of Waste to Energy Plants.doc Ways to Improve the Efficiency of Waste to Energy Plants for the Production@mvr-hh.de Abstract Up to now the emissions of waste-to-energy plants have been of major concern for the operators of waste incineration plants and the public. In Germany the emission standards for waste incineration

Columbia University

177

78 FR 34380 - Biennial Determination of the Waste Isolation Pilot Plant's Compliance With Applicable Federal...  

Federal Register 2010, 2011, 2012, 2013

...Biennial Determination of the Waste Isolation Pilot Plant's Compliance...submitted by the U.S. Department of Energy (DOE) for the Waste Isolation Pilot Plant (WIPP...as amended. The Secretary of Energy was notified of the...

2013-06-07

178

Laboratory plant study on the melting process of asbestos waste  

SciTech Connect

The melting process was studied as a method of changing asbestos into non-hazardous waste and recovering it as a reusable resource. In an initial effort, the thermal behaviors of asbestos waste in terms of physical and chemical structure have been studied. Then, 10 kg/h-scale laboratory plant experiments were carried out. By X-ray diffraction analysis, the thermal behaviors of sprayed-on asbestos waste revealed that chrysotile asbestos waste change in crystal structure at around 800 C, and becomes melted slag, mainly composed of magnesium silicate, at around 1,500 C. Laboratory plant experiments on the melting process of sprayed-on asbestos have shown that melted slag can be obtained. X-ray diffraction analysis of the melted slag revealed crystal structure change, and SEM analysis showed the slag to have a non-fibrous form. And more, TEM analysis proved the very high treatment efficiency of the process, that is, reduction of the asbestos content to 1/10{sup 6} as a weight basis. These analytical results indicate the effectiveness of the melting process for asbestos waste treatment.

Sakai, Shinichi; Terazono, Atsushi; Takatsuki, Hiroshi [Kyoto Univ. (Japan). Environment Preservation Center; Tsunemi, Takeshi [Osaka Gas Engineering Co., Ltd., Osaka (Japan)

1996-12-31

179

Mixed waste storage facility CDR review, Paducah Gaseous Diffusion Plant; Solid waste landfill CDR review, Paducah Gaseous Diffusion Plant  

SciTech Connect

This report consists of two papers reviewing the waste storage facility and the landfill projects proposed for the Paducah Gaseous Diffusion Plant complex. The first paper is a review of DOE`s conceptual design report for a mixed waste storage facility. This evaluation is to review the necessity of constructing a separate mixed waste storage facility. The structure is to be capable of receiving, weighing, sampling and the interim storage of wastes for a five year period beginning in 1996. The estimated cost is assessed at approximately $18 million. The review is to help comprehend and decide whether a new storage building is a feasible approach to the PGDP mixed waste storage problem or should some alternate approach be considered. The second paper reviews DOE`s conceptual design report for a solid waste landfill. This solid waste landfill evaluation is to compare costs and the necessity to provide a new landfill that would meet State of Kentucky regulations. The assessment considered funding for a ten year storage facility, but includes a review of other facility needs such as a radiation detection building, compactor/baler machinery, material handling equipment, along with other personnel and equipment storage buildings at a cost of approximately $4.1 million. The review is to help discern whether a landfill only or the addition of compaction equipment is prudent.

NONE

1998-08-01

180

Waste Isolation Pilot Plant Biennial Environmental Compliance Report  

SciTech Connect

This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2002, to March 31, 2004. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico.

Washington Regulatory and Environmental Services (WRES)

2004-10-25

181

Regulatory basis for the Waste Isolation Pilot Plant performance assessment  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) is the first operational repository designed for the safe disposal of transuranic (TRU) radioactive waste from the defense programs of the US Department of Energy (DOE). The US Environmental Protection Agency (EPA) is responsible for certifications and regulation of the WIPP facility for the radioactive components of the waste. The EPA has promulgated general radioactive waste disposal standards at 40 CFR Part 191. and WIPP-specific criteria to implement and interpret the generic disposal standards at 40 CFR Part 194. In October 1996. the DOE submitted its Compliance Certification Application (CCA) to the EPA to demonstrate compliance with the disposal standards at Subparts B and C of 40 CFR Part 191. This paper summarizes the development of the overall legal framework for radioactive waste disposal at the WIPP, the parallel development of the WIPP performance assessment (PA), and how the EPA disposal standards and implementing criteria formed the basis for the CCA WIPP PA. The CCA resulted in a certification in May 1998 by the EPA of the WIPP'S compliance with the EPA's disposal standard, thus enabling the WIPP to begin radioactive waste disposal.

HOWARD,BRYAN A.; CRAWFORD,M.B.; GALSON,D.A.; MARIETTA,MELVIN G.

2000-05-22

182

COST-BENEFIT ANALYSIS OF A WASTE TO ENERGY PLANT FOR MONTEVIDEO; AND WASTE TO  

E-print Network

source for the plant will be the gate fee, which currently is US$16/ton, in average, for waste disposal, in order to maintain the current gate fee of US$16/ton, and recover the capital investment over the payback the capital investment over the 23 years, the gate fee must be increased to at least US$25/ton, including

183

Waste Isolation Pilot Plant 1999 Site Environmental Report  

SciTech Connect

The U.S. Department of Energy?s (DOE)Carlsbad Area Office and the Westinghouse Waste Isolation Division (WID) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 1999 Site Environmental Report summarizes environmental data from calendar year 1999 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during calendar year 1999. WIPP received its first shipment of waste on March 26, 1999. In 1999, no evidence was found of any adverse effects from WIPP on the surrounding environment. Radionuclide concentrations in the environment surrounding WIPP were not statistically higher in 1999 than in 1998.

Roy B. Evans, Ph.D.; Randall C. Morris, Ph.D.; Timothy D. Reynolds, Ph.D.; Ronald W. Warren; Westinghouse Waste Isolation Division

2000-09-30

184

Waste Isolation Pilot Plant Biennial Environmental Compliance Report  

SciTech Connect

This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 1998, to March 31, 2000. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, and amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Area Office's (hereinafter the ''CAO'') compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. An issue was identified in the 1998 BECR relating to a potential cross-connection between the fire-water systems and the site domestic water system. While the CAO and its managing and operating contractor (hereinafter the ''MOC'') believe the site was always in compliance with cross-connection control requirements, hardware and procedural upgrades w ere implemented in March 1999 to strengthen its compliance posture. Further discussion of this issue is presented in section 30.2.2 herein. During this reporting period WIPP received two letters and a compliance order alleging violation of certain requirements outlined in section 9(a)(1) of the LWA. With the exception of one item, pending a final decision by the New Mexico Environment Department (NMED), all alleged violations have been resolved without the assessment of fines or penalties. Non-mixed TRU waste shipments began on March 26, 1999. Shipments continued through November 26, 1999, the effective date of the Waste Isolation Pilot Plant Hazardous Waste Facility Permit (NM4890139088-TSDF). No shipments regulated under the Hazardous Waste Facility Permit were received at WIPP during this BECR reporting period.

Westinghouse TRU Solutions

2000-12-01

185

CORAL: a stepping stone for establishing the Indian fast reactor fuel reprocessing technology  

SciTech Connect

The reprocessing of spent fuel from Fast Breeder Test Reactor (FBTR) has been successfully demonstrated in the pilot plant, CORAL (COmpact Reprocessing facility for Advanced fuels in Lead shielded cell). Since commissioning in 2003, spent mixed carbide fuel from FBTR of different burnups and varying cooling period, have been reprocessed in this facility. Reprocessing of the spent fuel with a maximum burnup of 100 GWd/t has been successfully carried out so far. The feed backs from these campaigns with progressively increasing specific activities, have been useful in establishing a viable process flowsheet for reprocessing the Prototype Fast Breeder Reactor (PFBR) spent fuel. Also, the design of various equipments and processes for the future plants, which are either under design for construction, namely, the Demonstration Fast Reactor Fuel Reprocessing Plant (DFRP) and the Fast reactor fuel Reprocessing Plant (FRP) could be finalized. (authors)

Venkataraman, M.; Natarajan, R.; Raj, Baldev [Indira Gandhi Center for Atomic Research, Kalpakkam (India)

2007-07-01

186

Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008  

SciTech Connect

The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2008 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to characterize site environmental management performance; summarize environmental occurrences and responses reported during the calendar year; confirm compliance with environmental standards and requirements; highlight significant facility programs and efforts; and describe how compliance and environmental improvement is accomplished through the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the Waste Isolation Pilot Plant (WIPP). DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit (HWFP) Number NM4890139088-TSDF (treatment, storage, and disposal facility) further requires that the ASER be provided to the New Mexico Environment Department (NMED). The WIPP mission is to safely dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States. In 2008, 5,265 cubic meters (m3) of TRU waste were disposed of at the WIPP facility, including 5,216 m3 of contact-handled (CH) TRU waste and 49 m3 of remote-handled (RH) TRU waste. From the first receipt of waste in March 1999 through the end of 2008, 57,873 m3 of TRU waste had been disposed of at the WIPP facility.

Washington Regulatory and Enviromnetal Services

2009-09-21

187

Remote handling equipment at the hanford waste treatment plant  

SciTech Connect

Cold war plutonium production led to extensive amounts of radioactive waste stored in tanks at the Department of Energy's Hanford Waste Treatment Plant. The storage tanks could potentially leak into the ground water and into the Columbia River. The solution for this risk of the leaking waste is vitrification. Vitrification is a process of mixing molten glass with radioactive waste to form a stable condition for storage. The Department of Energy has contracted Bechtel National, Inc. to build facilities at the Hanford site to process the waste. The waste will be separated into high and low level waste. Four major systems will process the waste, two pretreatment and two high level. Due to the high radiation levels, high integrity custom cranes have been designed to remotely maintain the hot cells. Several critical design parameters were implemented into the remote machinery design, including radiation limitations, remote operations, Important to Safety features, overall equipment effectiveness, minimum wall approaches, seismic constraints, and recovery requirements. Several key pieces of equipment were designed to meet these design requirements - high integrity crane bridges, trolleys, main hoists, mast hoists, slewing hoists, a monorail hoist, and telescoping mast deployed tele-robotic manipulator arms. There were unique and challenging design features and equipment needed to provide the remotely operated high integrity crane/manipulator systems for the Hanford Waste Treatment Plant. The cranes consist of a double girder bridge with various main hoist capacities ranging from one to thirty ton and are used for performing routine maintenance. A telescoping mast mounted tele-robotic manipulator arm with a one-ton hook is deployed from the trolley to perform miscellaneous operations in-cell. A dual two-ton slewing jib hoist is mounted to the bottom of the trolley and rotates 360 degrees around the mast allowing the closest hook wall approaches. Each of the two hoists on this slewer is mounted 180 degrees opposite each other. Another system utilizes a single one-ton slewing jib hoist that can extend and retract as well as rotate 270 degrees around the mast. Yet, another system utilizes an under-hung monorail trolley with one-ton hoist capacity mounted to the bottom of the bridge girder. The main, slewer and monorail hoists each have power-rotating hooks for installing and removing equipment in the hot cell. (authors)

Bardal, M.A. [PaR Systems, Inc., Shoreview, MN, (United States); Roach, J.D. [Bechtel National, Inc., Richland, WA (United States)

2007-07-01

188

Cut waste to reduce surcharges for your dairy plant  

SciTech Connect

Wastewater from most dairy plants is discharged to publicly owned treatment works (POTWs), where the majority of the pollutants are removed before the water is discharged to the environment. Treating the water costs money, and most treatment works charge according to the volume of sewage treated. In addition, they commonly charge extra (apply a surcharge) if the waste load exceeds certain specified levels because it costs more to treat water that contains more pollutants.

Carawan, R.E.

1988-12-31

189

Kinetic study of pyrolysis of waste water treatment plant sludge  

Microsoft Academic Search

Activated sewage sludge samples obtained from two different waste water treatment plants were investigated by thermogravimetric\\u000a analysis. Due to a very high content of water in the sludge samples, these had to be dried at 160°C in an electrical oven\\u000a in order to remove all adsorbed water. To ensure pyrolysis conditions, nitrogen atmosphere was applied. The pyrolysis decomposition\\u000a process was

LukᚠGašparovi?; Ivan Hrablay; Zuzana Vojteková; ?udovít Jelemenský

2011-01-01

190

Waste Isolation Pilot Plant Environmental Monitoring Plan  

SciTech Connect

DOE Order 5400.1, General Environmental Protection Program Requirements (DOE, 1990a), requires each DOE facility to prepare an EMP. This document is prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment (DOE, 1990b); Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) 834, Radiation Protection of the Public and Environment (Draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1 (DOE, 1995), which is the driver for the Annual Site Environmental Report (ASER) and the guidance source for preparing many environmental program documents. The WIPP project is operated by Westinghouse Electric Company, Waste Isolation Division (WID), for the DOE. This plan defines the extent and scope of the WIPP's effluent and environmental monitoring programs during the facility's operational life and also discusses the WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE, 1991). This document references DOE orders and other federal and state regulations affecting environmental monitoring programs at the site. WIPP procedures, which implement the requirements of this program plan, are also referenced. The DOE regulates its own activities for radiation protection of the public under the authority of the Atomic Energy Act of 1954, as amended (42 U.S.C. 2011). The effluent and environmental monitoring activities prescribed by DOE Order 5400.5 and the DOE/EH-0173T guidance manual are designed to ensure that DOE facilities implement standards and regulations to protect members of the public and the environment against undue risk from radiation. Effluent and environmental monitoring also provide 1999 Environmental Monitoring Plan DOE/WIPP 99-2194 the data necessary to demonstrate compliance with applicable environmental protection regulations. Other federal agencies, such as the U.S. Environmental Protection Agency (EPA), are empowered through specific legislation to regulate certain aspects of DOE activities potentially affecting public health and safety or the environment. Presidential Executive Order 12088, Federal Compliance with Pollution Control Standards (43 FR 47707), requires the heads of executive agencies to ensure that all federal facilities and activities comply with applicable pollution control standards and to take all necessary actions for the prevention, control, and abatement of environmental pollution. Beyond statutory requirements, the DOE has established a general environmental protection policy. The Environmental Policy Statement (issued by then Secretary Herrington on January 8, 1986, and extended on January 7, 1987) describes the DOE's commitment to national environmental protection goals in that it conducts operations ''in an environmentally safe and sound manner . . . in compliance with the letter and spirit of applicable environmental statutes, regulations, and standards'' (DOE, 1986). This Environmental Policy Statement also states the DOE's commitment to ''good environmental management in all of its programs and at all of its facilities in order to correct existing environmental problems, to minimize risks to the environment or public health, and to anticipate and address pote

Westinghouse Electric Company Waste Isolation Division

1999-09-29

191

Assessing pollutions of soil and plant by municipal waste dump  

NASA Astrophysics Data System (ADS)

Research is few in the literature regarding the investigation and assessment of pollutions of soil and plant by municipal waste dumps. Based upon previous work in seven waste dumping sites (nonsanitary landfills) in Beijing, Shanghai and Shijiazhuang, this study expounds the investigation and assessment method and report major pollutants. Using relative background values, this study assesses soil pollution degree in the seven dumping sites. Preliminary conclusions are: (1) pollution degrees are moderate or heavy; (2) pollution distance by domestic waste that is dumped on a plane ground is 85 m; (3) the horizontal transport distance of pollutants might be up to 120 m if waste leachates are directly connected with water in saturated soils; (4) vertical transport depth is about 3 m in unsaturated silty clayey soils. Furthermore, using relative background values and hygiene standards of food and vegetable this study assesses the pollutions of different parts of reed, sorghum, watermelon and sweet-melon. It is found: (1) in comparison with the relative background values in a large distance to the waste dumping sites, domestic wastes have polluted the roots and stems of reed and sorghum, whereas fine coal ash has polluted the leaves, rattans and fruits of watermelon and sweet-melon; (2) domestic wastes and fine coal ash have heavily polluted the edible parts of sorghum, water melon and sweet-melon. As, Hg, Pb and F have far exceeded standard values, e.g., Hg has exceeded the standard value by up to 650 1,700 times and Cd by 120 275 times, and the comprehensive pollution index is up to 192.9 369.7; (3) the polluted sorghum, watermelon and sweet-melon are inedible.

Liu, Changli; Zhang, Yun; Zhang, Feng'e.; Zhang, Sheng; Yin, Miying; Ye, Hao; Hou, Hongbing; Dong, Hua; Zhang, Ming; Jiang, Jianmei; Pei, Lixin

2007-04-01

192

Deriving a Planting Medium from Solid Waste Compost and Construction, Demolition and Excavation Waste  

NASA Astrophysics Data System (ADS)

Lebanon's very high population density has been increasing since the end of the war in the early 1990s reaching 416.36 people per square kilometer. Furthermore, the influx of refugees from conflicts in the region has increased the resident population significantly. All these are exerting pressure on the country's natural resources, pushing the Lebanese to convert more forest and agricultural land into roads, buildings and houses. This has led to a building boom and rapid urbanization which in turn has created a demand for construction material - mainly rock, gravel, sand, etc. nearly all of which were locally acquired through quarrying to the tune of three million cubic meters annually. This boom has been followed by a war with Israel in 2006 which resulted in thousands of tonnes of debris. The increase in population has also led to an increase in solid waste generation with 1.57 million tonnes of solid waste generated in Lebanon per year. The combination of construction, demolition and excavation (CDE) waste along with the increase in solid waste generation has put a major stress on the country and on the management of its solid waste problem. Compounding this problem are the issues of quarries closure and rehabilitation and a decrease in forest and vegetative cover. The on-going research reported in this paper aims to provide an integrated solution to the stated problem by developing a "soil mix" derived from a mélange of the organic matter of the solid waste (compost), the CDE waste, and soil. In this mix, native and indicator plants are planted (in pots) from which the most productive mix will be selected for further testing at field level in later experiments. The plant species used are Matiolla, a native Lebanese plant and Zea mays, which is commonly known used as an indicator plant due to its sensitivity to environmental conditions. To ensure sustainability and environmental friendliness of the mix, its physical and chemical characteristics are monitored and assessed. The leachate from the irrigation of the pots is also monitored and assessed to ensure that if selected for field trials, the mix will not pose a threat to water bodies. The presentation at the conference will aim to report the latest results from the on-going experiment.

Farajalla, Nadim; Assaf, Eleni; Bashour, Issam; Talhouk, Salma

2014-05-01

193

Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant  

SciTech Connect

The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source documents from the U.S. Nuclear RegulatoryCommission (NRC) and the New Mexico Environment Department (NMED) for acomprehensive and detailed listing of the requirements.This CH-WAC does not address the subject of waste characterization relating to adetermination of whether the waste is hazardous; rather, the sites are referred to theWaste Analysis Plan (WAP) contained in the WIPP Hazardous Waste Facility Permit fordetails of the sampling and analysis protocols to be used in determining compliance withthe required physical and chemical properties of the waste. Requirements andassociated criteria pertaining to a determination of the radiological properties of thewaste, however, are addressed in appendix A of this document. The collectiveinformation obtained from waste characterization records and acceptable knowledge(AK) serves as the basis for sites to certify that their CH-TRU waste satisfies the WIPPwaste acceptance criteria listed herein.

Washington TRU Solutions LLC

2005-12-29

194

Waste Isolation Pilot Plant 2001 Site Environmental Report  

SciTech Connect

The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment.

Westinghouse TRU Solutions, Inc.

2002-09-20

195

Waste Isolation Pilot Plant CY 2000 Site Environmental Report  

SciTech Connect

The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no evidence was found of any adverse effects from WIPP on the surrounding environment.

Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

2001-12-31

196

A historical review of Waste Isolation Pilot Plant backfill development  

SciTech Connect

Backfills have been part of Sandia National Laboratories' [Sandia's] Waste Isolation Pilot Plant [WIPP] designs for over twenty years. Historically, backfill research at Sandia has depended heavily on the changing mission of the WIPP facility. Early testing considered heat producing, high level, wastes. Bentonite/sand/salt mixtures were evaluated and studies focused on developing materials that would retard brine ingress, sorb radionuclides, and withstand elevated temperatures. The present-day backfill consists of pure MgO [magnesium oxide] in a pelletized form and is directed at treating the relatively low contamination level, non-heat producing, wastes actually being disposed of in the WIPP. Its introduction was motivated by the need to scavenging CO{sub 2} [carbon dioxide] from decaying organic components in the waste. However, other benefits, such as a substantial desiccating capacity, are also being evaluated. The MgO backfill also fulfills a statutory requirement for assurance measures beyond those needed to demonstrate compliance with the US Environmental Protection Agency [EPA] regulatory release limits. However, even without a backfill, the WIPP repository design still operates within EPA regulatory release limits.

KRUMHANSL,JAMES L.; MOLECKE,MARTIN A.; PAPENGUTH,HANS W.; BRUSH,LAURENCE H.

2000-06-05

197

Compliance status report for the Waste Isolation Pilot Plant  

SciTech Connect

The US Department of Energy (DOE) is responsible for the disposition of transuranic (TRU) waste generated through national defense-related activities. Approximately 53,700 m{sup 2} of these wastes have been generated and are currently stored at government defense installations across the country. The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, has been sited and constructed to meet the criteria established by the scientific and regulatory community for the safe, long-term disposal of TRU and TRU-mixed wastes. This Compliance Status Report (CSR) provides an assessment of the progress of the WIPP Program toward compliance with long-term disposal regulations, set forth in Title 40 CFR 191 (EPA, 1993a), Subparts B and C, and Title 40 CFR {section}268.6 (EPA, 1993b), in order to focus on-going and future experimental and engineering activities. The CSR attempts to identify issues associated with the performance of the WIPP as a long-term repository and to focus on the resolution of these issues. This report will serve as a tool to focus project resources on the areas necessary to ensure complete, accurate, and timely submittal of the compliance application. This document is not intended to constitute a statement of compliance or a demonstration of compliance.

Not Available

1994-03-31

198

Waste Isolation Pilot Plant simulated RH TRU waste experiments: Data and interpretation pilot  

SciTech Connect

The simulated, i.e., nonradioactive remote-handled transuranic waste (RH TRU) experiments being conducted underground in the Waste Isolation Pilot Plant (WIPP) were emplaced in mid-1986 and have been in heated test operation since 9/23/86. These experiments involve the in situ, waste package performance testing of eight full-size, reference RH TRU containers emplaced in horizontal, unlined test holes in the rock salt ribs (walls) of WIPP Room T. All of the test containers have internal electrical heaters; four of the test emplacements were filled with bentonite and silica sand backfill materials. We designed test conditions to be ``near-reference`` with respect to anticipated thermal outputs of RH TRU canisters and their geometrical spacing or layout in WIPP repository rooms, with RH TRU waste reference conditions current as of the start date of this test program. We also conducted some thermal overtest evaluations. This paper provides a: detailed test overview; comprehensive data update for the first 5 years of test operations; summary of experiment observations; initial data interpretations; and, several status; experimental objectives -- how these tests support WIPP TRU waste acceptance, performance assessment studies, underground operations, and the overall WIPP mission; and, in situ performance evaluations of RH TRU waste package materials plus design details and options. We provide instrument data and results for in situ waste container and borehole temperatures, pressures exerted on test containers through the backfill materials, and vertical and horizontal borehole-closure measurements and rates. The effects of heat on borehole closure, fracturing, and near-field materials (metals, backfills, rock salt, and intruding brine) interactions were closely monitored and are summarized, as are assorted test observations. Predictive 3-dimensional thermal and structural modeling studies of borehole and room closures and temperature fields were also performed.

Molecke, M.A.; Argueello, G.J.; Beraun, R.

1993-04-01

199

Results from simulated contact-handled transuranic waste experiments at the Waste Isolation Pilot Plant  

SciTech Connect

We conducted in situ experiments with nonradioactive, contact-handled transuranic (CH TRU) waste drums at the Waste Isolation Pilot Plant (WIPP) facility for about four years. We performed these tests in two rooms in rock salt, at WIPP, with drums surrounded by crushed salt or 70 wt % salt/30 wt % bentonite clay backfills, or partially submerged in a NaCl brine pool. Air and brine temperatures were maintained at {approximately}40C. These full-scale (210-L drum) experiments provided in situ data on: backfill material moisture-sorption and physical properties in the presence of brine; waste container corrosion adequacy; and, migration of chemical tracers (nonradioactive actinide and fission product simulants) in the near-field vicinity, all as a function of time. Individual drums, backfill, and brine samples were removed periodically for laboratory evaluations. Waste container testing in the presence of brine and brine-moistened backfill materials served as a severe overtest of long-term conditions that could be anticipated in an actual salt waste repository. We also obtained relevant operational-test emplacement and retrieval experience. All test results are intended to support both the acceptance of actual TRU wastes at the WIPP and performance assessment data needs. We provide an overview and technical data summary focusing on the WIPP CH TRU envirorunental overtests involving 174 waste drums in the presence of backfill materials and the brine pool, with posttest laboratory materials analyses of backfill sorbed-moisture content, CH TRU drum corrosion, tracer migration, and associated test observations.

Molecke, M.A.; Sorensen, N.R.; Krumhansl, J.L.

1993-12-31

200

Towards an ontology of waste water treatment plants: the identification phase  

Microsoft Academic Search

Water pollution in Mexico is an important issue in spite of the benefits obtained by current waste water treatment plants; more heuristic knowledge is required to adequately design and operate new plants. This paper discusses the role of the identification phase in the attainment of a knowledge base to obtain a domain ontology of waste water treatment plants. Two examples

Octavio Cabezut-boo; Antonio Sánchez-aguilar

1999-01-01

201

Critical components of odors in evaluating the performance of food waste composting plants  

Microsoft Academic Search

The current Taiwan government policy toward food waste management encourages composting for resource recovery. This study used olfactometry, gas chromatography–mass spectrometry (GC–MS) and gas detector tubes to evaluate the ambient air at three of the largest food waste composting plants in Taiwan. Ambient air inside the plants, at exhaust outlets and plant boundaries was examined to determine the comprehensive odor

I-Fang Mao; Chung-Jung Tsai; Shu-Hung Shen; Tsair-Fuh Lin; Wang-Kun Chen; Mei-Lien Chen

2006-01-01

202

Hanford Facility Dangerous Waste Permit Application for T Plant Complex  

SciTech Connect

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the T Plant Complex (this document, DOE/RL-95-36). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the T Plant Complex permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents Section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the T Plant Complex permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text.

BARNES, B.M.

2002-09-01

203

Sampling and Analysis Plan - Waste Treatment Plant Seismic Boreholes Project  

SciTech Connect

This sampling and analysis plan (SAP) describes planned data collection activities for four entry boreholes through the sediment overlying the basalt, up to three new deep rotary boreholes through the basalt and sedimentary interbeds, and one corehole through the basalt and sedimentary interbeds at the Waste Treatment Plant (WTP) site. The SAP will be used in concert with the quality assurance plan for the project to guide the procedure development and data collection activities needed to support borehole drilling, geophysical measurements, and sampling. This SAP identifies the American Society of Testing Materials standards, Hanford Site procedures, and other guidance to be followed for data collection activities.

Reidel, Steve P.

2006-05-26

204

Waste Isolation Pilot Plant Annual Site Environmental Report for 2012  

SciTech Connect

The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2012 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year; Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS).

None

2013-09-01

205

Modeling Offgas Systems for the Hanford Waste Treatment Plant  

SciTech Connect

To augment steady-state design calculations, dynamic models of three offgas systems that will be used in the Waste Treatment Plant now under construction at the Hanford Site were developed using Aspen Custom Modeler{trademark}. The offgas systems modeled were those for the High Level Waste (HLW) melters, Low Activity Waste (LAW) melters and HLW Pulse Jet Ventilation (PJV) system. The models do not include offgas chemistry but only consider the two major species in the offgas stream which are air and water vapor. This is sufficient to perform material and energy balance calculations that accurately show the dynamic behavior of gas pressure, temperature, humidity and flow throughout the systems. The models are structured to perform pressure drop calculations across the various unit operations using a combination of standard engineering calculations and empirical data based correlations for specific pieces of equipment. The models include process controllers, gas ducting, control valves, exhaust fans and the offgas treatment equipment. The models were successfully used to analyze a large number of operating scenarios including both normal and off-normal conditions.

Smith, Frank G., III

2005-09-02

206

Waste Isolation Pilot Plant Biennial Environmental Compliance Report  

SciTech Connect

This Biennial Environmental Compliance Report (BECR) documents compliance with environmental regulations at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste. This BECR covers the reporting period from April 1, 2004, to March 31, 2006. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents United States (U.S.) Department of Energy (DOE) compliance with regulations and permits issued pursuant to the following: (1) Title 40 Code of Federal Regulations (CFR) Part 191, Subpart A, "Environmental Standards for Management and Storage"; (2) Clean Air Act (CAA) (42 United States Code [U.S.C.] §7401, et seq.); (3) Solid Waste Disposal Act (SWDA) (42 U.S.C. §§6901-6992, et seq.); (4) Safe Drinking Water Act (SDWA) (42 U.S.C. §§300f, et seq.); (5) Toxic Substances Control Act (TSCA) (15 U.S.C. §§2601, et seq.); (6) Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) (42 U.S.C. §§9601, et seq.); and all other federal and state of New Mexico laws pertaining to public health and safety or the environment.

Washington Regulatory and Environmental Services

2006-10-12

207

Experimental program plan for the Waste Isolation Pilot Plant  

SciTech Connect

The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included.

Not Available

1994-01-01

208

Reprocessing in Luminous Disks  

NASA Technical Reports Server (NTRS)

We develop and investigate a procedure that accounts for disk reprocessing of photons that originate in the disk itself. Surface temperatures and simple, black body spectral energy distributions (SEDs) of protostellar disks are calculated. In disks that flare with radius, reprocessing of stellar photons results in temperature profiles considerably shallower than r(sup -3/4). Including the disk as a radiation source (as in the case of actively secreting disks) along with the stellar source further flattens the temperature profile. Disks that flare strongly near the star and then smoothly curve over and become shadowed at some distance ("decreasing curvature" disks) exhibit nearly power-law temperature profiles which result in power-law infrared SEDs with slopes in agreement with typical observations of young stellar objects. Disk models in which the photospheric thickness is controlled by the local opacity and in which the temperature decreases with radius naturally show this shape. Uniformly flaring models do not match observations as well; progressively stronger reprocessing at larger radii leads to SEDs that flatten toward the infrared or even have a second peak at the wavelength corresponding (through the Wien law) to the temperature of the outer edge of the disk. In FU Orionis outbursting systems, the dominant source of energy is the disk itself. The details of the reprocessing depend sensitively on the assumed disk shape and emitted temperature profile. The thermal instability outburst models of Bell Lin reproduce trends in the observed SEDs of Fuors with T varies as r(sup -3/4) in the inner disk (r approx. less than 0.25au corresponding to lambda approx. less than 10 microns) and T varies as r(sup -1/2) in the outer disk. Surface irradiation during outburst and quiescence is compared in the region of planet formation (1 - 10 au). The contrast between the two phases is diminished by the importance of the reprocessing of photons from the relatively high mass flux outer disk (dot-M = 10(exp -5) solar mass/yr) which is present during both outburst and quiescence.

Bell, K. Robbins; DeVincenzi, Donald L. (Technical Monitor)

1999-01-01

209

Waste Isolation Pilot Plant Site Environmental Report Calendar Year 2002  

SciTech Connect

The United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environment, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2002 Site Environmental Report summarizes environmental data from calendar year 2002 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2002 (DOE Memorandum EH-41: Natoli:6-1336, April 4, 2003). These Orders and the guidance document require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED).

Washington Regulatory and Environmental Services

2003-09-17

210

Waste-to-energy plants--current status  

SciTech Connect

There are two types of resource recovery plants, refuse-derived fuel (RDF) and production and user plants, and mass-burning of municipal waste with energy recovery to generate steam. According to DOE, approximately 5,000 tons per day of refuse are processed in the U.S. from 35 plants. The present status and future plans of 8 of these plants are outlined. An interesting example is the Baltimore County Resource Recovery Facility is operational and processes 800 tons/day, 6 day/week. Several thousand tons of d-RDF have been shipped to Wright-Patterson AFB at /27/ton. Approximately 25 to 30 tons/day of ferrous metals are shipped to Bethlehem Steel at /33/ton. Production of RDF and d-RDF continues on an intermittent basis as required by Wright Patterson AFB and local test markets. During the summer of 1980, the aluminum and glass aggregate recovery systems were operating after a long period of inactivity. A market for the glass product in making fiberglass was being explored.

Greenberg, G.

1982-01-01

211

WASTE MINIMIZATION AUDIT REPORT: CASE STUDIES OF MINIMIZATION OF MERCURY-BEARING WASTES AT A MERCURY CELL CHLORALKALI PLANT  

EPA Science Inventory

The report documents the results of waste minimization audits carried out at two mercury cell chloralkali plants in 1987. The audit addressed to waste streams, K-071-brine purification muds, and K-106-wastewater treatment sludges from Mercury cell processes in chlorine production...

212

Hanford Waste Simulants Created to Support the Research and Development on the River Protection Project - Waste Treatment Plant  

SciTech Connect

The development of nonradioactive waste simulants to support the River Protection Project - Waste Treatment Plant bench and pilot-scale testing is crucial to the design of the facility. The report documents the simulants development to support the SRTC programs and the strategies used to produce the simulants.

Eibling, R.E.

2001-07-26

213

Summary of Waste Calcination at INTEC  

SciTech Connect

Fluidized-bed calcination at the Idaho Nuclear Technologies and Engineering Center (INTEC, formally called the Idaho Chemical Processing Plant) has been used to solidify acidic metal nitrate fuel reprocessing and incidental wastes wastes since 1961. A summary of waste calcination in full-scale and pilot plant calciners has been compiled for future reference. It contains feed compositions and operating conditions for all the processing campaigns for the original Waste Calcining Facility (WCF), the New Waste Calcining Facility (NWCF) started up in 1982, and numerous small scale pilot plant tests for various feed types. This summary provides a historical record of calcination at INTEC, and will be useful for evaluating calcinability of future wastes.

O'Brien, Barry Henry; Newby, Bill Joe

2000-10-01

214

Disposition and Reuse of Waste in a High-Capacity Power Plant  

Microsoft Academic Search

This paper presents a research of the integrated disposition and reuse of solid waste and contaminated water in Fengcheng thermal power station Jiangxi province China. These waste(coal combustion fly ash, bottom slag, flue gas desulfurization sludges and the contaminated water) may cause serious environmental problems. In this paper, the chemical and physical properties of the waste from the power plant

Rui Xu; Changzhu Yang; Fengsheng Hou; Shengrui Qiu

2008-01-01

215

Vermicomposting of distillation waste of citronella plant ( Cymbopogon winterianus Jowitt.) employing Eudrilus eugeniae  

Microsoft Academic Search

Laboratory experiment on vermicomposting of distillation waste of java citronella (Cymbopogon winterianus Jowitt.) was carried out employing Eudrilus eugeniae, in two seasonal trials, covering summer and winter periods. Two vermicomposting treatments were conducted in earthen pots, one with citronella plant waste only (CW) and the other, a mixture of citronella waste and cowdung in the proportion 5:1 (CW+CD). Vermicomposting of

H. Deka; S. Deka; C. K. Baruah; J. Das; S. Hoque; N. S. Sarma

2011-01-01

216

Don't trash waste-to-energy plants By NICKOLAS THEMELIS  

E-print Network

was developed a state-of-the-art waste transfer and recycling station. That landfill, and at least 40 others allDon't trash waste-to-energy plants By NICKOLAS THEMELIS October 21, 2009 2:00 AM Some environmentalists are arguing on behalf of the concept of Zero Waste today. They say if you ban landfills

217

Simulation in Aspen Plus of Power Plant's Circulating Water Waste Heat Recovery System  

Microsoft Academic Search

Power Plant Circulating Water (PPCW) waste heat recycling is an important way of increasing a power plant's primary energy ratio. According to the PPCW waste heat regenerative thermal system, the authors propose two modes of heat pump heat regenerative of the system, ASPEN PLUS, one of the most famous softwares of chemical engineering,was used to stimulatethe process. The measures to

Bi Qingsheng; Ma Yanliang; Bai Zhang

2010-01-01

218

Surface water pollution by herbicides from effluents of waste water treatment plants  

Microsoft Academic Search

Herbicide loads of urban and rural waste water treatment plant effluents were calculated over a one-year period by measuring the herbicide concentrations in 14-day mixed samples. More than three quarters of the total herbicide load of the effluent of the rural waste water treatment plant consists of isoproturon. Particularly large amounts of this substance contribute to the total herbicide load

Walter Schüssler

1998-01-01

219

CEWEP -Confederation of European Waste-to-Energy Plants Boulevard Clovis 12A  

E-print Network

electricity and 12.1 million inhabitants with renewable heat3 . In fact, Waste-to-Energy plants produce TWICECEWEP - Confederation of European Waste-to- Energy Plants Boulevard Clovis 12A B-1000 Brussels Tel policy would be even more ambitious, replacing landfilling). Both the supply of renewable electricity

220

High temperature corrosion in a 65 MW waste to energy plant  

Microsoft Academic Search

Incineration of municipal solid waste is often associated with high temperature corrosion problems. This paper presents results of full-scale corrosion tests in a 65 MW waste fired combined heat and power plant. A failure case indicated alarmingly high corrosion rate of the superheater tubes. Corrosion tests with five different alloys were carried out within this work in order to determine plant

Kristoffer Persson; Markus Broström; Jörgen Carlsson; Anders Nordin; Rainer Backman

2007-01-01

221

Plant uptake and dissipation of PBDEs in the soils of electronic waste recycling sites  

Microsoft Academic Search

Plant uptake and dissipation of weathered PBDEs in the soils of e-waste recycling sites were investigated in a greenhouse study. Eighteen PBDE congeners (tri- through deca-) were detected in the plant tissues. The proportion of lower brominated PBDEs (mono- through hexa-) in plant roots was higher than that in the soils. A concentration gradient was observed of PBDEs in plants

Honglin Huang; Shuzhen Zhang; Peter Christie

2011-01-01

222

Recycling plant, human and animal wastes to plant nutrients in a closed ecological system  

NASA Technical Reports Server (NTRS)

The essential minerals for plant growth are nitrogen, phosphorous, potassium (macronutrients), calcium, magnesium, sulfur (secondary nutrients), iron, manganese, boron, copper, zinc, chlorine, sodium, and molybdenum (micronutrients). The first step in recycling wastes will undoubtedly be oxidation of carbon and hydrogen to CO2 and H2O. Transformation of minerals to plant nutrients depends upon the mode of oxidation to define the state of the nutrients. For the purpose of illustrating the type of processing required, ash and off-gas compositions of an incineration process were assumed and subsequent processing requirements were identified. Several processing schemes are described for separating out sodium chloride from the ash, leading to reformulation of a nutrient solution which should be acceptable to plants.

Meissner, H. P.; Modell, M.

1979-01-01

223

Enviromental impact of a hospital waste incineration plant in Krakow (Poland).  

PubMed

The environmental impact of a hospital waste incineration plant in Krakow was investigated. The objective of this study was to assess the degree of environmental effect of the secondary solid waste generated during the incineration process of medical waste. The analysis of pollution of the air emissions and leaching test of ashes and slag were carried out. The obtained results allowed us to conclude that (i) the hospital waste incineration plant significantly solves the problems of medical waste treatment in Krakow; (ii) the detected contaminant concentrations were generally lower than the permissible values; (iii) the generated ashes and slag contained considerable concentrations of heavy metals, mainly zinc, and chloride and sulfate anions. Ashes and slag constituted 10-15% of the mass of incinerated wastes; they are more harmful for the environment when compared with untreated waste, and after solidification they can be deposited in the hazardous waste disposal. PMID:23640706

Gielar, Agnieszka; Helios-Rybicka, Edeltrauda

2013-07-01

224

Waste receiving and processing plant control system; system design description  

SciTech Connect

The Plant Control System (PCS) is a heterogeneous computer system composed of numerous sub-systems. The PCS represents every major computer system that is used to support operation of the Waste Receiving and Processing (WRAP) facility. This document, the System Design Description (PCS SDD), includes several chapters and appendices. Each chapter is devoted to a separate PCS sub-system. Typically, each chapter includes an overview description of the system, a list of associated documents related to operation of that system, and a detailed description of relevant system features. Each appendice provides configuration information for selected PCS sub-systems. The appendices are designed as separate sections to assist in maintaining this document due to frequent changes in system configurations. This document is intended to serve as the primary reference for configuration of PCS computer systems. The use of this document is further described in the WRAP System Configuration Management Plan, WMH-350, Section 4.1.

LANE, M.P.

1999-02-24

225

CEWEP -Confederation of European Waste-to-Energy Plants Boulevard Clovis 12A  

E-print Network

CEWEP - Confederation of European Waste-to- Energy Plants Boulevard Clovis 12A B-1000 Brussels Tel. : +32 (0)2 770 63 11 Fax : +32 (0)2 770 68 14 info@cewep.eu www.cewep.eu 1 Waste-to-Energy: towards incineration. That means that Waste-to-Energy (WtE) plants would be considered as performing energy recovery

Columbia University

226

Waste Isolation Pilot Plant Annual Site Environmental Report for 2010  

SciTech Connect

The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2010 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: (1) Characterize site environmental management performance. (2) Summarize environmental occurrences and responses reported during the calendar year. (3) Confirm compliance with environmental standards and requirements. (4) Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the WIPP. DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit Number NM4890139088-TSDF (Permit) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

None

2011-09-01

227

Construction and operation of an industrial solid waste landfill at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio  

SciTech Connect

The US Department of Energy (DOE), Office of Waste Management, proposes to construct and operate a solid waste landfill within the boundary of the Portsmouth Gaseous Diffusion Plant (PORTS), Piketon, Ohio. The purpose of the proposed action is to provide PORTS with additional landfill capacity for non-hazardous and asbestos wastes. The proposed action is needed to support continued operation of PORTS, which generates non-hazardous wastes on a daily basis and asbestos wastes intermittently. Three alternatives are evaluated in this environmental assessment (EA): the proposed action (construction and operation of the X-737 landfill), no-action, and offsite shipment of industrial solid wastes for disposal.

NONE

1995-10-01

228

Waste reduction assistance program (WRAP) on-site consultation audit report: Seafood processing plant  

SciTech Connect

The waste audit study was conducted at a seafood processing plant in Alaska. The report discusses process descriptions, waste types and quantities, current waste and materials management practices, and waste reduction alternatives. The company's current practices include use of fish waste, burning of used oil and solvents, and water conservation. Additional opportunities include microfiltration of solvents and oils, recycling of used batteries, inventory control and formation of a waste reduction team. Appendices include a summary of state regulations, a fact sheet on used oil, and a list of vendors and services.

Not Available

1989-07-29

229

The Effect of Congress' Mandate to Create Greater Efficiencies in the Characterization of Transuranic Waste through the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit  

Microsoft Academic Search

Effective December 1, 2003, the U.S. Congress directed the Department of Energy (DOE) to file a permit modification request with the New Mexico Environment Department (NMED) to amend the Hazardous Waste Facility Permit (hereinafter 'the Permit') at the Waste Isolation Pilot Plant (WIPP). This legislation, Section 311 of the 2004 Energy and Water Development Appropriations Act, was designed to increase

Gloria J. Johnson; R. F. Kehrman

2008-01-01

230

The Waste Isolation Pilot Plant (WIPP) Groundwater Monitoring Program  

NASA Astrophysics Data System (ADS)

The development of a groundwater monitoring program is an integral part of any radioactive waste disposal facility. Monitoring improves our understanding of the geologic and hydrologic framework, which improves conceptual models and the quality of groundwater models that provide data input for performance assessment. The purpose of a groundwater monitoring program is to provide objective evidence that the hydrologic system is behaving as expected (i.e., performance confirmation). Monitoring should not be limited to near-field observations but should include the larger natural system in which the repository is situated. The Waste Isolation Pilot Plant (WIPP), a U.S. Department of Energy (DOE) facility designed for the safe disposal of transuranic wastes resulting from U.S. defense programs, can serve as a model for other radioactive waste disposal facilities. WIPP has a long-established groundwater monitoring program that is geared towards meeting compliance certification requirements set forth by the U.S. Environmental Protection Agency (EPA). The primary task of the program is to measure various water parameters (e.g.., water level, pressure head, chemical and physical properties) using a groundwater monitoring network that currently consists of 85 wells in the vicinity of the WIPP site. Wells are completed to a number of water-bearing horizons and are monitored on a monthly basis. In many instances, they are also instrumented with programmable pressure transducers that take high-frequency measurements that supplement the monthly measurements. Results from higher frequency measurements indicate that the hydrologic system in the WIPP vicinity is in a transient state, responding to both natural and anthropogenic stresses. The insights gathered from the monitoring, as well as from hydrologic testing activities, provide valuable information that contributes to groundwater modeling efforts and performance assessment. Sandia is a multi program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under Contract DE-AC04- 94AL85000. This research is funded by WIPP programs administered by the Office of Environmental Management (EM) of the U.S Department of Energy.

Hillesheim, M. B.; Beauheim, R. L.

2006-12-01

231

Data validation and security for reprocessing.  

SciTech Connect

Next generation nuclear fuel cycle facilities will face strict requirements on security and safeguards of nuclear material. These requirements can result in expensive facilities. The purpose of this project was to investigate how to incorporate safeguards and security into one plant monitoring system early in the design process to take better advantage of all plant process data, to improve confidence in the operation of the plant, and to optimize costs. An existing reprocessing plant materials accountancy model was examined for use in evaluating integration of safeguards (both domestic and international) and security. International safeguards require independent, secure, and authenticated measurements for materials accountability--it may be best to design stand-alone systems in addition to domestic safeguards instrumentation to minimize impact on operations. In some cases, joint-use equipment may be appropriate. Existing domestic materials accountancy instrumentation can be used in conjunction with other monitoring equipment for plant security as well as through the use of material assurance indicators, a new metric for material control that is under development. Future efforts will take the results of this work to demonstrate integration on the reprocessing plant model.

Tolk, Keith Michael; Merkle, Peter Benedict; DurÔan, Felicia Angelica; Cipiti, Benjamin B.

2008-10-01

232

Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2  

SciTech Connect

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

Not Available

1993-08-01

233

Safety Evaluation for Hull Waste Treatment Process in JNC  

SciTech Connect

Hull wastes and some scrapped equipment are typical radioactive wastes generated from reprocessing process in Tokai Reprocessing Plant (TRP). Because hulls are the wastes remained in the fuel shearing and dissolution, they contain high radioactivity. Japan Nuclear Cycle Development Institute (JNC) has started the project of Hull Waste Treatment Facility (HWTF) to treat these solid wastes using compaction and incineration methods since 1993. It is said that Zircaloy fines generated from compaction process might burn and explode intensely. Therefore explosive conditions of the fines generated in compaction process were measured. As these results, it was concluded that the fines generated from the compaction process were not hazardous material. This paper describes the outline of the treatment process of hulls and results of safety evaluation.

Kojima, H.; Kurakata, K.

2002-02-26

234

Mechanisms governing the direct removal of wastes from the Waste Isolation Pilot Plant repository caused by exploratory drilling  

SciTech Connect

Two processes are identified that can influence the quantity of wastes brought to the ground surface when a waste disposal room of the Waste Isolation Pilot Plant is inadvertently penetrated by an exploratory borehole. The first mechanism is due to the erosion of the borehole wall adjacent to the waste caused by the flowing drilling fluid (mud); a quantitative computational model based upon the flow characteristics of the drilling fluid (laminar or turbulent) and other drilling parameters is developed and example results shown. The second mechanism concerns the motion of the waste and borehole spall caused by the flow of waste-generated gas to the borehole. Some of the available literature concerning this process is discussed, and a number of elastic and elastic-plastic finite-difference and finite-element calculations are described that confirm the potential importance of this process in directly removing wastes from the repository to the ground surface. Based upon the amount of analysis performed to date, it is concluded that it is not unreasonable to expect that volumes of waste several times greater than that resulting from direct cutting of a gauge borehole could eventually reach the ground surface. No definitive quantitative model for waste removal as a result of the second mechanism is presented; it is concluded that decomposed waste constitutive data must be developed and additional experiments performed to assess further the full significance of this latter mechanism.

Berglund, J.W. [New Mexico Engineering Research Inst., Albuquerque, NM (United States)

1992-12-01

235

Thorium Molten Salt Reactor : from high breeding to simplified reprocessing  

E-print Network

Thorium Molten Salt Reactor : from high breeding to simplified reprocessing L. Mathieu, D. Heuer, A of a great part of the uranium ressources and production of high quantities of nuclear wastes are hardly ac- ceptable. The Thorium Molten Salt Reactor (TMSR) may contribute to solve these problems. The thorium cycle

Paris-Sud XI, Université de

236

Transfer of elements relevant to radioactive waste from soil to five boreal plant species  

Microsoft Academic Search

In long-term safety assessment models for radioactive waste disposal, uptake of radionuclides by plants is an important process with possible adverse effects in ecosystems. Cobalt-60, 59,63Ni, 93Mo, and 210Pb are examples of long-living radionuclides present in nuclear waste. The soil-to-plant transfer of stable cobalt, nickel, molybdenum and lead and their distribution across plant parts were investigated in blueberry (Vaccinium myrtillus),

Päivi Roivainen; Sari Makkonen; Toini Holopainen; Jukka Juutilainen

2011-01-01

237

Warm water aquaculture using waste heat and water from zero discharge power plants in the Great Basin  

Microsoft Academic Search

Two series of experiments were completed to determine (a) toxicity of waste water from power plants on warm water fish and (b) multiple use of waste heat and water for aquatic animal and plant production. All three types of waste water from a typical coal-fired power plant are acceptable for growing catfish and tilapia following aeration. This growth was compared

R. A. Heckmann; R. N. Winget; R. C. Infanger; R. W. Mickelsen; J. M. Hendersen

1984-01-01

238

Potential radiological impact of tornadoes on the safety of Nuclear Fuel Services' West Valley Fuel Reprocessing Plant. Volume I. Tornado effects on head-end cell airflow  

SciTech Connect

This report describes results of a parametric study of the impacts of a tornado-generated depressurization on airflow in the contaminated process cells within the presently inoperative Nuclear Fuel Services fuel reprocessing facility near West Valley, NY. The study involved the following tasks: (1) mathematical modeling of installed ventilation and abnormal exhaust pathways from the cells and prediction of tornado-induced airflows in these pathways; (2) mathematical modeling of individual cell flow characteristics and prediction of in-cell velocities induced by flows from step 1; and (3) evaluation of the results of steps 1 and 2 to determine whether any of the pathways investigated have the potential for releasing quantities of radioactively contaminated air from the main process cells. The study has concluded that in the event of a tornado strike, certain pathways from the cells have the potential to release radioactive materials of the atmosphere. Determination of the quantities of radioactive material released from the cells through pathways identified in step 3 is presented in Part II of this report.

Holloway, L.J.; Andrae, R.W.

1981-09-01

239

Waste Isolation Pilot Plant Groundwater Protection Management Program Plan  

SciTech Connect

The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New MexicoAdministrative Code), "Adoption of 40 CFR [Code of Federal Regulations] Part 264,"specifically 40 CFR §264.90 through §264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] §6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

Washington Regulatory and Environmental Services

2005-07-01

240

76 FR 45268 - Reprocessing of Reusable Medical Devices  

Federal Register 2010, 2011, 2012, 2013

...FDA-2011-N-0294] Reprocessing of Reusable Medical Devices AGENCY: Food and Drug Administration...affecting the reprocessing of reusable medical devices, including reprocessing quality...relates to the reprocessing of reusable medical devices, reprocessing...

2011-07-28

241

Pilot plant for biomethanation of dairy-industry wastes  

SciTech Connect

This project was undertaken to demonstrate the application of two-phase anaerobic digestion (TPAD) for simultaneous stabilization and biomethanation of high-COD cheese-waste-dairy-manure mixtures by a pilot-plant operation in Wellsville, Utah. The TPAD system exhibited a total COD (TCOD) reduction of up to 97% with feed COD concentration of 60,000 to 45,000 mg/l. The TCOD reduction decreased as the variability as well as the strength of the feed increased. A quick surge of the feed TCOD concentration to 125,000 mg/l effected a large drop in TCOD reduction, but the integrity of the methane digester, which produced 78 {approximately}87 mol% methane-content gas, was measured and TPAD system performance could be restored to normal levels by diluting the feed to obtain TCOD concentrations below 70,000 mg/l. The TPAD system exhibited a methane yield of 0.27 m{sup 3}/kg TCOD charged (0.36 m{sup 3}/kg TCOD removed).

Ghosh, S.; Fukushi, K.; Liu, T. [Univ. of Utah, Salt Lake City, UT (United States)] [and others

1994-12-31

242

Characterization of past and present solid waste streams from the plutonium finishing plant  

SciTech Connect

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing (WRAP) Facility, and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico for final disposal. Over 50% of the TRU waste to be retrieved for shipment to the WIPP has been generated at the Plutonium Finishing Plant (PFP), also known as the Plutonium Processing and Storage Facility and Z Plant. The purpose of this report is to characterize the radioactive solid wastes generated by the PFP since its construction in 1947 using process knowledge, existing records, and history-obtained from interviews. The PFP is currently operated by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE).

Duncan, D.R.; Mayancsik, B.A. [Westinghouse Hanford Co., Richland, WA (United States)] [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J.A.; Vejvoda, E.J.; Reddick, J.A.; Sheldon, K.M.; Weyns, M.I. [Los Alamos Technical Associates, Kennewick, WA (United States)] [Los Alamos Technical Associates, Kennewick, WA (United States)

1993-02-01

243

ONDRAF/NIRAS and high-level radioactive waste management in Belgium  

SciTech Connect

The National Agency for Radioactive Waste and Enriched Fissile Materials, ONDRAF/NIRAS, is a public body with legal personality in charge of managing all radioactive waste on Belgian territory, regardless of its origin and source. It is also entrusted with tasks related to the management of enriched fissile materials, plutonium containing materials and used or unused nuclear fuel, and with certain aspects of the dismantling of closed down nuclear facilities. High-level radioactive waste management comprises essentially and for the time being the storage of high-level liquid waste produced by the former EUROCHEMIC reprocessing plant and of high-level and very high-level heat producing waste resulting from the reprocessing in France of Belgian spent fuel, as well as research and development (R and D) with regard to geological disposal in clay of this waste type.

Decamps, F. [ONDRAF/NIRAS, Brussels (Belgium)

1993-12-31

244

Detection, Composition and Treatment of Volatile Organic Compounds from Waste Treatment Plants  

PubMed Central

Environmental policies at the European and global level support the diversion of wastes from landfills for their treatment in different facilities. Organic waste is mainly treated or valorized through composting, anaerobic digestion or a combination of both treatments. Thus, there are an increasing number of waste treatment plants using this type of biological treatment. During waste handling and biological decomposition steps a number of gaseous compounds are generated or removed from the organic matrix and emitted. Different families of Volatile Organic Compounds (VOC) can be found in these emissions. Many of these compounds are also sources of odor nuisance. In fact, odors are the main source of complaints and social impacts of any waste treatment plant. This work presents a summary of the main types of VOC emitted in organic waste treatment facilities and the methods used to detect and quantify these compounds, together with the treatment methods applied to gaseous emissions commonly used in composting and anaerobic digestion facilities. PMID:22163835

Font, Xavier; Artola, Adriana; Sanchez, Antoni

2011-01-01

245

Detection, composition and treatment of volatile organic compounds from waste treatment plants.  

PubMed

Environmental policies at the European and global level support the diversion of wastes from landfills for their treatment in different facilities. Organic waste is mainly treated or valorized through composting, anaerobic digestion or a combination of both treatments. Thus, there are an increasing number of waste treatment plants using this type of biological treatment. During waste handling and biological decomposition steps a number of gaseous compounds are generated or removed from the organic matrix and emitted. Different families of Volatile Organic Compounds (VOC) can be found in these emissions. Many of these compounds are also sources of odor nuisance. In fact, odors are the main source of complaints and social impacts of any waste treatment plant. This work presents a summary of the main types of VOC emitted in organic waste treatment facilities and the methods used to detect and quantify these compounds, together with the treatment methods applied to gaseous emissions commonly used in composting and anaerobic digestion facilities. PMID:22163835

Font, Xavier; Artola, Adriana; Sánchez, Antoni

2011-01-01

246

Development of transuranium elements recovery from high-level radioactive liquid waste  

Microsoft Academic Search

The Transuranium Elements (TRUs) recovery process from High-Level Liquid Waste (HLLW) at a Purex reprocessing plant requires both simple processes and a high yield of TRUs recovery. This paper outlines a new TRUs recovery process which combines an aqueous process and a pyrochemical process. In the first step, TRUs and Rare Earth elements (REs) are precipitated from HLLW to separate

Reiko Fujita; Yoshie Akai

1998-01-01

247

Reprocessing of Reusable Medical Devices  

MedlinePLUS

... acquiring such an infection from an inadequately reprocessed medical device is relatively low given the large number of such devices in use, although the potential for outbreaks of infection associated with their use remains an ...

248

Neutron shielding analysis for remote handled transuranic waste containers in facility casks at the Waste Isolation Pilot Plant  

SciTech Connect

Neutron shielding characteristics of the Waste Isolation Pilot Plant facility cask have been quantified for a variety of combinations of neutron sources and waste matrices which would potentially be handled in waste containers. The neutron attenuation and neutron environment of the waste container and the facility cask have been analyzed to ensure that the design requirement of neutron dose rate will be met under the combinations of the source and waste matrix conditions. The analyses considered the ranges of neutron source spectrum and waste matrices which combine to produce the minimum neutron shielding worth of the facility cask. One-dimensional analyses were performed with discrete ordinate transport theory methods using multigroup neutron cross section data. The results discussed in this report demonstrate the effect of source spectrum and waste container matrix on predicted neutron dose rates adjacent to the unshielded waste container and the surface of the facility cask. An evaluation of the uncertainties in predicted neutron dose rates is provided which results in an assessment of the maximum measured neutron dose rate external to the facility cask. A description of the analytical models developed, the analysis methodology, the neutron source spectra, and the detailed results are described in this report. 10 refs., 50 figs., 39 tabs.

Livingston, J.V.; Disney, R.K.

1984-04-01

249

Plasma coal reprocessing  

NASA Astrophysics Data System (ADS)

Results of many years of investigations of plasma-chemical technologies for pyrolysis, hydrogenation, thermochemical preparation for combustion, gasification, and complex reprocessing of solid fuels and hydrocarbon gas cracking are represented. Application of these technologies for obtaining the desired products (hydrogen, industrial carbon, synthesis gas, valuable components of the mineral mass of coal) corresponds to modern ecological and economical requirements to the power engineering, metallurgy, and chemical industry. Plasma fuel utilization technologies are characterized by the short-term residence of reagents within a reactor and the high degree of the conversion of source substances into the desired products without catalyst application. The thermochemical preparation of the fuel to combustion is realized in a plasma-fuel system presenting a reaction chamber with a plasmatron; and the remaining plasma fuel utilization technologies, in a combined plasma-chemical reactor with a nominal power of 100 kW, whose zone of the heat release from an electric arc is joined with the chemical reaction zone.

Messerle, V. E.; Ustimenko, A. B.

2013-12-01

250

Laboratory and bin-scale tests of gas generation for the Waste Isolation Pilot Plant  

SciTech Connect

The design-basis, defense-related, transuranic (TRU) waste to be emplaced in the Waste Isolation Pilot Plant (WIPP) could, if sufficient H{sub 2}O and nutrients were present, produce as much as 1,500 moles of gas per drum of waste. Anoxic corrosion of Fe and Fe-base alloys and microbial degradation of cellulosics are the processes of greatest concern, but radiolysis of brine could also be important. 19 refs., 1 fig., 1 tab.

Brush, L.H.; Molecke, M.A.; Lappin, A.R. (Sandia National Labs., Albuquerque, NM (United States)); Westerman, R.E. (Pacific Northwest Lab., Richland, WA (United States)); Tong, X.; Black, J.N.P.; Grbic-Galic, D. (Stanford Univ., CA (United States). Dept. of Civil Engineering); Vreeland, R.E. (West Chester Univ., PA (United States). Dept. of Biology); Reed, D.T. (Argonne National Lab., IL (United Stat

1991-01-01

251

Organic Rankine Cycle Systems for Waste Heat Recovery in Refineries and Chemical Process Plants  

E-print Network

The design of a low temperature Rankine cycle system using R-113 working fluid for recovery and conversion of process waste heat is described for typical applications in oil refineries and chemical plants. The system is designed to produce electric...

Meacher, J. S.

1981-01-01

252

Vitrification of HLW Produced by Uranium/Molybdenum Fuel Reprocessing in COGEMA's Cold Crucible Melter  

SciTech Connect

The performance of the vitrification process currently used in the La Hague commercial reprocessing plants has been continuously improved during more than ten years of operation. In parallel COGEMA (industrial Operator), the French Atomic Energy Commission (CEA) and SGN (respectively COGEMA's R&D provider and Engineering) have developed the cold crucible melter vitrification technology to obtain greater operating flexibility, increased plant availability and further reduction of secondary waste generated during operations. The cold crucible is a compact water-cooled melter in which the radioactive waste and the glass additives are melted by direct high frequency induction. The cooling of the melter produces a solidified glass layer that protects the melter's inner wall from corrosion. Because the heat is transferred directly to the melt, high operating temperatures can be achieved with no impact on the melter itself. COGEMA plans to implement the cold crucible technology to vitrify high level liquid waste from reprocessed spent U-Mo-Sn-Al fuel (used in gas cooled reactor). The cold crucible was selected for the vitrification of this particularly hard-to-process waste stream because it could not be reasonably processed in the standard hot induction melters currently used at the La Hague vitrification facilities : the waste has a high molybdenum content which makes it very corrosive and also requires a special high temperature glass formulation to obtain sufficiently high waste loading factors (12 % in molybdenum). A special glass formulation has been developed by the CEA and has been qualified through lab and pilot testing to meet standard waste acceptance criteria for final disposal of the U-Mo waste. The process and the associated technologies have been also being qualified on a full-scale prototype at the CEA pilot facility in Marcoule. Engineering study has been integrated in parallel in order to take into account that the Cold Crucible should be installed remotely in one of the R7 vitrification cell. This paper will present the results obtained in the framework of these qualification programs.

Do Quang, R.; Petitjean, V.; Hollebecque, F.; Pinet, O.; Flament, T.; Prod'homme, A.

2003-02-25

253

WASTE REDUCTION PRACTICES AT TWO CHROMATED COPPER ARSENATE WOOD-TREATING PLANTS  

EPA Science Inventory

Two chromated copper arsenate (CCA) wood-treating plants were assessed for their waste reduction practices. The objectives of this study were to estimate the amount of hazardous wastes that a well-designed and well-main- tained CCA treatment facility would generate and to iden- t...

254

Pembangunan loji insinerasi sisa radioaktif paras rendah. (Development of low level radioactive waste incineration plant).  

National Technical Information Service (NTIS)

A laboratory scale liquid waste incineration plant has been constructed. Preliminary tests were conducted by burning kerosene as the waste. The temperature reached 1200 deg.C. The exhaust gas was analysed for CO and CO sub 2 content. The hydrocarbon conte...

Shaharum bin Ramli Azmir bin Hanafiah

1994-01-01

255

WASTE REDUCTION PRACTICES AT TWO CHROMATED COPPER ARSENATE WOOD-TREATING PLANTS  

EPA Science Inventory

Two chromated copper arsenate (CCA) wood-treating plants were assessed for their waste reduction practices. he objectives of this study were to estimate the amount of hazardous wastes that a well-designed and well-maintained CCA treatment facility would generate and to identify w...

256

Dewatering of coal-clay waste slurries from preparation plants. Report of investigations/1983  

SciTech Connect

The Bureau of Mines is investigating a dewatering technique for coal-clay waste that uses a flocculant, polyethylene oxide (PEO). This flocculant forms strong stable flocs that can be dewatered on a static screen. A field test unit (FTU) using this technique was operated at approximately 400 gal/min, using a waste stream from the flotation circuit of a coal preparation plant.

Brown, P.M.; Scheiner, B.J.

1983-11-01

257

The geologic and hydrogeologic setting of the Waste Isolation Pilot Plant  

Microsoft Academic Search

The Waste Isolation Pilot Plant (WIPP) is a mined repository for the permanent disposal of transuranic wastes. It has been constructed by the United States Department of Energy (DOE) in semiarid, sparsely inhabited rangeland in southeastern New Mexico. The disposal area is 655m below the land surface, in bedded salt of the Late Permian (approximately 255 million-years-old) Salado Formation. The

P. N Swift; T. F Corbet

2000-01-01

258

An overview of the Oak Ridge National Laboratory waste-handling and packaging plant  

Microsoft Academic Search

The Waste-Handling and Packaging Plant (WHPP) has been proposed as a fiscal year (FY) 1993 capital line-item project to be built at the Oak Ridge National Laboratory (ORNL). The mission of this project is to retrieve, receive, repackage, certify, and ship remotely handled (RH) and special case transuranic (TRU) waste. Approximately 90% of the inventory of RH TRU stored at

D. W. Turner; R. S. Stewart; J. W. Moore

1989-01-01

259

UBC Plant Operations, Waste Management Division 2329 West Mall, V6T 1Z4  

E-print Network

UBC Plant Operations, Waste Management Division 2329 West Mall, V6T 1Z4 Tel: 604-822-3827 Web drivers Note: location must be truck accessible Special notes or requests A representative from UBC Waste Management will contact you within one week of receiving this form. Thank you. Request for Event Composting

Handy, Todd C.

260

Metal uptake by xerothermic plants introduced into Zn-Pb industrial wastes  

Microsoft Academic Search

The dusty surfaces of post-flotation wastes contain high concentrations of toxic compounds and spread widely if appropriate\\u000a vegetation is not introduced. It has been previously established that effective restoration of such waste areas are best met\\u000a by xerothermic, mycorrhiza-assisted plants (Turnau et al. Plant and Soil 305:267–280, 2008). The aim of the current study was to improve phytostabilisation practices by

Katarzyna Turnau; Beata Ostachowicz; Grzegorz Wojtczak; Teresa Anielska; ?ukasz Sobczyk

2010-01-01

261

Vitrification of borate waste from nuclear power plant using coal fly ash. (I) Glass formulation development  

Microsoft Academic Search

Borate waste, which is the main liquid waste from daily operation of PWR nuclear power plants, contains a large amount of Na and B. The coal fly ash is a by-product of the coal combustion power plants. The high content of SiO2 and Al2O3 of coal fly ash makes it a desirable glass network former additive; therefore, using the coal

Jiawei Sheng

2001-01-01

262

Development of Nitrogen Oxide Closed System in the Future Reprocessing Process  

SciTech Connect

An aqueous reprocessing for spent fuels generates much wastes mainly including sodium nitrate as secondary waste, which has some kinds of difficulties in disposal. A process with salt-free reagent and complete recycle of nitric acid would resolve the problem, but development for such process is not easy. We propose the treatment system of sodium nitrate waste, which are termed 'Nitrogen Oxide Closed System' (NCS) as mentioned below. The system decomposes nitrate ion, and enables reuse of sodium in sodium nitrate with no generation of sodium nitrate waste. Accordingly, the NCS system allows the use of sodium salt reagents, and generation of excess acid in a reprocessing process. (authors)

Takaoku, Y.; Hattori, I.; Watanabe, T.; Moriya, N.; Sumida, Y.; Araya, S. [Japan Nuclear Fuel Limited, 4-104 Okitsuke, Obuchi, Rokkasho-mura, Kamikita-gun, Aomori 039-3212 (Japan); Homma, S. [Saitama University 255 Shimo-Okubo, Sakura-Ku, Saitama-shi, Saitama 338-8570 (Japan); Suzuki, Y. [JGC Corporation 2205 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki 311-1313 (Japan); Akai, Y. [Toshiba Corporation 4-1Ukishima-Cho, Kawasaki-ku, Kawasaki-shi, Kanagawa 210-08 2 (Japan)

2007-07-01

263

Nuclear waste-form risk assessment for US Defense waste at Savannah River Plant. Annual report FY 1981  

SciTech Connect

Savannah River Plant has been supporting the Lawrence Livermore National Laboratory in its present effort to perform risk assessments of alternative waste forms for defense waste. This effort relates to choosing a suitable combination of solid form and geologic medium on the basis of risk of exposure to future generations; therefore, the focus is on post-closure considerations of deep geologic repositories. The waste forms being investigated include borosilicate glass, SYNROC, and others. Geologic media under consideration are bedded salt, basalt, and tuff. The results of our work during FY 1981 are presented in this, our second annual report. The two complementary tasks that comprise our program, analysis of waste-form dissolution and risk assessment, are described.

Cheung, H.; Edwards, L.L.; Harvey, T.F.; Jackson, D.D.; Revelli, M.A.

1981-12-01

264

Digital Gas Joins Asian Waste-to-Energy Consortium: To Eliminate Coal as a Power Plant Fuel  

E-print Network

Digital Gas Joins Asian Waste-to-Energy Consortium: To Eliminate Coal as a Power Plant Fuel Digital (DEFA) has signed an agreement with US-based Entropic Energy LLC to commercialize breakthrough waste-to-energy with a major Asian city to install a waste-to-energy plant that would process approximately 15,000 tons

Columbia University

265

Waste Isolation Pilot Plant 2005 Site Environmental Report  

SciTech Connect

The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to make WIPP environmental information available to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2004. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through defense activities and programs. TRU waste is defined, in the WIPP LWA, as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting TRU isotopes per gram of waste, with half-lives greater than 20 years except for high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools; sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. TRU waste is eligible for disposal at WIPP if it has been generated in whole or in part by one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] §10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by-products management,defense nuclear materials security and safeguards and security investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated disposal rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel of seven rooms has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. One of the main attributes of salt, as a rock formation in which to isolate radioactive waste, is the ability of the salt to creep, that is, to deform continuously over time. Excavations into which the waste-filled drums are placed will close eventually, flowing around the drums and sealing them within the formation.

Washington Regulatory and Environmental Services

2006-10-13

266

WASTE TREATMENT AND DISPOSAL FROM SEAFOOD PROCESSING PLANTS  

EPA Science Inventory

Examinations of current wastewater and solid waste disposal practices and characterization of the wastewater effluent for seafood processing were carried out in a project within the state of Maryland in order to recommend economical waste treatment and disposal systems for the in...

267

Geopolymerisation of silt generated from construction and demolition waste washing plants.  

PubMed

Recycling plants that size, sort and wash construction and demolition waste can produce high quality aggregate. However, they also produce up to 80ton per hour of filter cake waste containing fine (<63mum) silt particles that is classified as inert waste and normally landfilled. This research investigated the potential to form geopolymers containing silt, which would allow this problematic waste to be beneficially reused as aggregate. This would significantly improve the economic viability of recycling plants that wash wastes. Silt filter cakes have been collected from a number of aggregate washing plants operating in the UK. These were found to contain similar aluminosilicate crystalline phases. Geopolymer samples were produced using silt and silt mixed with either metakaolin or pulverised fuel ash (PFA). Silt geopolymers cured at room temperature had average 7-day compressive strengths of 18.7MPa, while partial substitution of silt by metakaolin or PFA increased average compressive strengths to 30.5 and 21.9MPa, respectively. Curing specimens for 24h at 105 degrees C resulted in a compressive strength of 39.7MPa and microstructural analysis confirmed the formation of dense materials. These strengths are in excess of those required for materials to be used as aggregate, particularly in unbound applications. The implications of this research for the management of waste silt at construction and demolition waste washing plants are discussed. PMID:18579370

Lampris, C; Lupo, R; Cheeseman, C R

2009-01-01

268

Optimization of biological recycling of plant nutrients in livestock waste by utilizing waste heat from cooling water  

SciTech Connect

Results are presented from a 5-year study to develop aquatic methods which beneficially use condenser cooling water from electric generating power plants. A method is proposed which uses a system for aquatic farming. Livestock waste is used to fertilize planktonic algae production and filter-feeding fish are used to biologically harvest the algae, condenser cooling water (simulated) is used to add waste heat to the system, and emergent aquatic plants are used in a flow through series as a bio-filter to improve the water quality and produce an acceptable discharge. Two modes of operation were tested; one uses untreated swine manure as the source of aquatic fertilizer and the other uses anaerobic digester waste as a means of pretreating the manure to produce an organic fertilizer. A set of operating conditions (temperature, retention time, fish stocking rate, fertilizer rates, land and water requirements, suggested fish and plant species, and facility design) were developed from these results. The integrated system allows continual use of power plant condenser cooling water from plants in the southeastern United States.

Maddox, J.J.; Behrends, L.L.; Burch, D.W.; Kingsley, J.B.; Waddell, E.L. Jr.

1982-05-01

269

State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants  

SciTech Connect

A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report.

Not Available

1980-04-01

270

Cold End Inserts for Process Gas Waste Heat Boilers Air Products, operates hydrogen production plants, which utilize large waste heat boilers (WHB)  

E-print Network

Cold End Inserts for Process Gas Waste Heat Boilers Overview Air Products, operates hydrogen production plants, which utilize large waste heat boilers (WHB) to cool process syngas. The gas enters satisfies all 3 design criteria. · Correlations relating our experimental results to a waste heat boiler

Demirel, Melik C.

271

Neurotoxic effects from residential exposure to chemicals from an oil reprocessing facility and superfund site.  

PubMed

Neurotoxicity has been described in workers exposed to solvents, PCBs, certain metals, and polyaromatic hydrocarbons but not often in residents near refineries or factories. We compared the neurobehavioral performance of residents near a plant that reprocessed used motor oil and chemical waste from 1966-1983 to referents from beyond the plant's modeled air dispersal and water drainage zones. Neurophysiological and psychological tests, a Profile of Mood States (POMS) and a symptom questionnaire were administered to 131 subjects exposed at the site who were matched for age, sex, and ethnicity 2:1 with 66 unexposed subjects from 35 km away. Test scores were adjusted for a 1.4-year difference in educational attainment by coefficients from regression equations but not for income as the latter coefficients were not significant. Exposed subjects were significantly impaired for body balance (sway speed) and simple and two choice visual reaction time as compared to referents. Blink reflex latency (R-1) and eye closure speed were normal in both groups. Cognitive function in the exposed was impaired as measured by Culture Fair and by block design from the WAIS. Placing pegs in a grooved board and making of trails (A and B) were also impaired. Group differences in recall and memory were not significant. The exposed group's symptom frequencies and POMS scores for depression, anger, confusion, tension, and fatigue were elevated indicating depression. Confounding from medical and neurological disorders or occupational exposures was minimal. Subjects exposed residentially for up to 17 years to chemicals dispersed from a waste oil reprocessing plant showed neurophysiological and neuropsychological impairment. PMID:7760780

Kilburn, K H; Warshaw, R H

1995-01-01

272

Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility  

SciTech Connect

This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

Bonnema, Bruce Edward

2001-09-01

273

Increased BLSS closure using mineralized human waste in plant cultivation on a neutral substrate  

NASA Astrophysics Data System (ADS)

The purpose of this work was to study the full-scale potential use of human mineralized waste (feces and urine) as a source of mineral elements for plant cultivation in a biological life support system (BLSS). Plants that are potential candidates for a photosynthesizing link were grown on a neutral solution containing human mineralized waste. Spring wheat Triticum aestivum L., peas Pisum sativum L. Ambrosia cultivar and leaf lettuce Lactuca sativa L., Vitaminny variety, were used. The plants were grown hydroponically on expanded clay aggregates in a vegetation chamber in constant environmental conditions. During plant growth, a determined amount of human mineralized waste was added daily to the nutrient solution. The nutrient solution remained unchanged throughout the vegetation period. Estimated plant requirements for macro-elements were based on a total biological productivity of 0.04 kg day -1 m -2. As the plant requirements for potassium exceeded the potassium content of human waste, a water extract of wheat straw containing the required amount of potassium was added to the nutrient solution. The Knop's solution was used in the control experiments. The experimental and control plants showed no significant differences in state or productivity of their photosynthetic apparatus. A small decrease in total productivity of the experimental plants was observed, which might result in some reduction of ? 2 production in a BLSS.

Ushakova, S.; Tikhomirov, A.; Shikhov, V.; Kudenko, Yu.; Anischenko, O.; Gros, J.-B.; Lasseur, Ch.

2009-10-01

274

Physic-Chemical Characterisation of Slag Waste Coming From IGCC Thermal Power Plant  

Microsoft Academic Search

The new Integrated Gasification in Combined Cycle (IGCC) plants produce electricity more efficiently than conventional thermal power plants, but they produce a high quantity of wastes in the form of slag and fly ashes. Nowadays, these by-products are sold as low-value secondary raw material in construction. In order to evaluate the capability of these products to be recycled, with higher

A. Acosta; M. Aineto; I. Iglesias; M. Romero; J. Ma. Rincón; S. Burgos

275

Studies into the preparation of alum from slime waste from the Awaso Bauxite Washing Plant  

Microsoft Academic Search

Bauxite mining has been going on at Awaso in the Western Region of Ghana, West Africa, since 1941. Materials from the pit are usually passed through the washing plant to remove impurities such as plant material, and clay, and fines in the bauxite material. The washing process has generated several thousands of tonnes of slime waste that has been impounded

F. W. Y. Momade; K. Sraku-Lartey

2010-01-01

276

Waste Isolation Pilot Plant Title I operator dose calculations. Final report, LATA report No. 90  

SciTech Connect

The radiation exposure dose was estimated for the Waste Isolation Pilot Plant (WIPP) operating personnel who do the unloading and transporting of the transuranic contact-handled waste. Estimates of the radiation source terms for typical TRU contact-handled waste were based on known composition and properties of the waste. The operations sequence for waste movement and storage in the repository was based upon the WIPP Title I data package. Previous calculations had been based on Conceptual Design Report data. A time and motion sequence was developed for personnel performing the waste handling operations both above and below ground. Radiation exposure calculations were then performed in several fixed geometries and folded with the time and motion studies for individual workers in order to determine worker exposure on an annual basis.

Hughes, P.S.; Rigdon, L.D.

1980-02-01

277

Automated small-scale fuel alcohol plant: A means to add value to food processing waste  

SciTech Connect

A small scale fuel grade alcohol plant was designed, constructed and operated a decade ago. This plant design incorporated several innovative processes and features that are still on the cutting edge for small scale alcohol production. The plant design could be scaled down or up to match the needs of food processing waste streams that contain sugars or starches as BOD. The novel features include automation requiring four hours of labor per 24 hour day and a plug flow low temperature cooking system which solubilizes and liquifies the starch in one step. This plant consistently produced high yield of alcohol. Yields of 2.6 gallons of absolute alcohol were produced from a bushel of corn. Potato waste grain dust and cheese whey were also processed in this plant as well as barley. Production energy for a 190 proof gallon was approximately 32,000 BTU. This paper discusses the design, results, and applicability of this plant to food processing industries.

Wolfram, J.H.; Keller, J. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Wernimont, L.P.

1993-12-31

278

Low Temperature Waste Energy Recovery at Chemical Plants and Refineries  

E-print Network

candidates of waste heat recovery technologies that might have an application in these industries. Four technologies that met the criteria of the Advisory Committee included: organic rankine cycle (ORC), absorption refrigeration and chilling, Kalina cycle...

Ferland, K.; papar, R.; Quinn, J.; Kumar, S.

2013-01-01

279

International investigation of electronic waste recycling plant design  

E-print Network

This thesis investigates the industry of electronic waste recycling industry in three countries: Germany, the United States, and Chile. Despite differences in the legal structure surrounding the industry, there are many ...

Theurer, Jean E

2010-01-01

280

Pinellas Plant contingency plan for the hazardous waste management facility  

SciTech Connect

Subpart D of Part 264 (264.50 through .56) of the Resource Conservation and Recovery Act (RCRA) regulations require that each facility maintain a contingency plan detailing procedures to {open_quotes}minimize hazards to human health or the environment from fires, explosions, or any unplanned sudden or non-sudden release of hazardous waste or hazardous waste constituents to air, soil, or surface water.{close_quotes}

NONE

1988-04-01

281

Plant-growth regulators from common starfish ( Asterias amurensis Lütken) waste  

Microsoft Academic Search

Starfish waste has been shown to be an effective compost material not only in the promotion of plant growth but also in terms\\u000a of having insecticidal activity. In the present study, plant growth regulation by chemicals from starfish was examined. The\\u000a aqueous fraction from a hot water extract of the starfish Asterias amurensis Ltken showed plant-growth activity, while the aqueous

Takahiro Ishii; Tatsufumi Okino; Yosuke Mino; Hiroaki Tamiya; Fuyuhiko Matsuda

2007-01-01

282

Steps of Reprocessing and Equipments  

PubMed Central

With the increasing interest in endoscopy and the rising number of endoscopic examinations in hospitals, the importance of endoscopic reprocessing is also increasing. Cure facilities that are understaffed and ill-equipped are trying to cope with the problems of insufficient cleaning and high infection risks. To prevent endoscopy-associated infection, the endoscope cleaning, and disinfection guidelines prepared by the Korean Society of Gastrointestinal Endoscopy must be followed. In this review, the steps of endoscopic reprocessing and the equipments required in each step are discussed. PMID:23767039

Lee, Yong Kook

2013-01-01

283

BARIUM AND RADIUM IN WATER TREATMENT PLANT WASTES  

EPA Science Inventory

Water treatment plants at nine locations (10 plants) in Illinois and Iowa were studied to determine the characteristics and disposal practices for the sludge, brine, and backwash water containing radium (Ra) and/or barium (Ba). The treatment processes in these ten plants include ...

284

BAR-CODE BASED WEIGHT MEASUREMENT STATION FOR PHYSICAL INVENTORY TAKING OF PLUTONIUM OXIDE CONTAINERS AT THE MINING AND CHEMICAL COMBINE RADIOCHEMICAL REPROCESSING PLANT NEAR KRASNOYARSK, SIBERIA.  

SciTech Connect

This paper describes the technical tasks being implemented to computerize the physical inventory taking (PIT) at the Mining and Chemical Combine (Gorno-Khimichesky Kombinat, GKhK) radiochemical plant under the US/Russian cooperative nuclear material protection, control, and accounting (MPC and A) program. Under the MPC and A program, Lab-to-Lab task agreements with GKhK were negotiated that involved computerized equipment for item verification and confirmatory measurement of the Pu containers. Tasks under Phase I cover the work for demonstrating the plan and procedures for carrying out the comparison of the Pu container identification on the container with the computerized inventory records. In addition to the records validation, the verification procedures include the application of bar codes and bar coded TIDs to the Pu containers. Phase II involves the verification of the Pu content. A plan and procedures are being written for carrying out confirmatory measurements on the Pu containers.

SUDA,S.

1999-09-20

285

Analysis of the implications of the USSR providing reprocessing and MOX fabrication services to other countries  

SciTech Connect

This brief analysis, which is based on unclassified sources, seeks to identify what some of the implications would be if the Soviets started to move actively to try to provide reprocessing and MOX fabrication services to the US and other countries. While information on Soviet intentions is limited, it postulates that the Soviets would offer to reprocess spent LWR at competitive prices, fabricate the plutonium and reenrich the uranium, and sell these products back to the customer. Since it is not known whether they would insist on returning the waste from reprocessing or would be prepared to keep it, we comment briefly on what the implications of either of these actions might be.

NONE

1994-12-31

286

Idaho Chemical Processing Plant Site Development Plan  

SciTech Connect

The Idaho Chemical Processing Plant (ICPP) mission is to receive and store spent nuclear fuels and radioactive wastes for disposition for Department of Energy (DOE) in a cost-effective manner that protects the safety of Idaho National Engineering Laboratory (INEL) employees, the public, and the environment by: Developing advanced technologies to process spent nuclear fuel for permanent offsite disposition and to achieve waste minimization. Receiving and storing Navy and other DOE assigned spent nuclear fuels. Managing all wastes in compliance with applicable laws and regulations. Identifying and conducting site remediation consistent with facility transition activities. Seeking out and implementing private sector technology transfer and cooperative development agreements. Prior to April 1992, the ICPP mission included fuel reprocessing. With the recent phaseout of fuel reprocessing, some parts of the ICPP mission have changed. Others have remained the same or increased in scope.

Ferguson, F.G.

1994-02-01

287

Waste Isolation Pilot Plant Site Environmental Report for calendar year 1989  

SciTech Connect

This is the 1989 Site Environmental Report (SER) for the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP is a government owned and contractor-operated facility. The WIPP project is operated by Westinghouse Electric Corporation for the US Department of Energy (DOE). The mission of the WIPP is to provide a research and development facility to demonstrate the safe disposal of transuranic (TRU) waste generated by the defense activities of the US Government. This report provides a comprehensive description of environmental activities at the WIPP during calendar year 1989. The WIPP facility will not receive waste until all concerns affecting opening the WIPP are addressed to the satisfaction of the Secretary of Energy. Therefore, this report describes the status of the preoperational activities of the Radiological Environmental Surveillance (RES) program, which are outlined in the Radiological Baseline Program for the Waste Isolation Pilot Plant (WTSD-TME-057). 72 refs., 13 figs., 20 tabs.

Not Available

1989-01-01

288

Influence of heat recuperation in ORC power plant on efficiency of waste heat utilization  

NASA Astrophysics Data System (ADS)

The present work is devoted to the problem of utilization of the waste heat contained in the exhaust gases having the temperature of 350 °C. Conversion of the waste heat into electricity using a power plant working with organic fluid cycles is considered. Three Organic Rankine Cycle (ORC) power plant solutions are analysed and compared: a solution with the basic, single thermodynamic conversion cycle, one with internal heat recuperation and one with external heat recuperation. It results from the analysis that it is the proper choice of the working fluid evaporation temperature that fundamentally affects the maximum of the ORC plant output power. Application of the internal heat recuperation in the plant basic cycle results in the output power increase of approx. 5%. Addition of the external heat recuperation to the plant basic cycle, in the form of a secondary supercritical ORC power cycle can rise the output power by approx. 2%.

Borsukiewicz-Gozdur, Aleksandra

2010-10-01

289

Off-design performance of integrated waste-to-energy, combined cycle plants  

Microsoft Academic Search

This paper focuses on the off-design operation of plants where a waste-to-energy (WTE) system fed with municipal solid waste (MSW) is integrated with a natural gas-fired combined cycle (CC). Integration is accomplished by sharing the steam cycle: saturated steam generated in a MSW grate combustor is exported to the heat recovery steam generator (HRSG) of the combined cycle, where it

Stefano Consonni; Paolo Silva

2007-01-01

290

Record new waste-to-energy capacity built in 1990 joins 128 existing plants  

SciTech Connect

The Institute of Resource Recovery reports that waste-to-energy plants will operate at a record setting rate in 1991, handling 14% of the 185 million tons of trash expected to be generated. In addition, 47 plants with a capacity of 57,596 tons per day are in the advanced planning stages. Movement into construction will depend on factors such as financing and securing environmental permits. Some states are working towards integrated facilities that will combine waste reduction, recycling, combustion, and landfilling. Nevertheless, waste-to-energy will be a critical part of workable plans for the following reasons: it reduces the volume of trash up to 90%; it recovers steam and electricity from the combustion process, thus reducing the need for imported energy; present plants have some of the cleanest facilities in the country due to strict air emissions requirements.

Not Available

1991-01-01

291

RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE BY FLUIDIZED BED STEAM REFORMING USING THE BENCH SCALE REFORMER PLATFORM  

SciTech Connect

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of {sup 125/129}I and {sup 99}Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

2012-02-02

292

Assessing Waste Water Treatment Plant Effluent for Thyroid Hormone Disruption  

EPA Science Inventory

Much information has been coming to light on the estrogenic and androgenic activity of chemicals present in the waste water stream and in surface waters, but much less is known about the presence of chemicals with thyroid activity. To address this issue, we have utilized two assa...

293

Alternative solid forms for Savannah River Plant defense waste  

SciTech Connect

Solid forms and processes were evaluated for immobilization of SRP high-level radioactive waste, which contains bulk chemicals such as hydrous iron and aluminium oxides. Borosilicate glass currently is the best overall choice. High-silica glass, tailored ceramics, and coated ceramics are potentially superior products, but require more difficult processes.

Stone, J.A.; Goforth, S.T.; Smith, P.K.

1980-01-01

294

WATER QUALITY RENOVATION OF ANIMAL WASTE LAGOONS UTILIZING AQUATIC PLANTS  

EPA Science Inventory

Duckweeds Spirodela oligorhiza, S. polyrhiza, and Lemna gibba (clone G3) grown on dairy waste lagoons gave an estimated maximum annual yield of 22,023 kg dry wt./ha. S. oligorhiza and L. gibba had higher growth rates in the spring, fall, and winter, with L. gibba growing througho...

295

Processing of nuclear power plant waste streams containing boric acid.  

National Technical Information Service (NTIS)

Boric acid is used in PWR type reactor's primary coolant circuit to control the neutron flux. However, boric acid complicates the control of water chemistry of primary coolant and the liquid radioactive waste produced from NPP. The purpose of this report ...

1996-01-01

296

Meteorology and demography models for risk assessments of accidental atmospheric releases of nuclear waste. Phase 2 methodology  

SciTech Connect

Models are derived for determining the risk of release to the atmosphere of radioactive materials during nuclear waste handling. Such releases might occur in three phases of the nuclear waste handling cycle: (1) at fuel reprocessing plants during handling and interim storage, (2) during transportation to a permanent storage area, or (3) at the permanent disposal area (federal waste repository). Gaussian diffusion equations for both plume- and puff-type releases are used with demographic models to assess relative integrated population doses. Given a unit release and assuming an equal accident probability, we conclude that the largest risk would be from a transportation accident in a metropolitan area. The effect of a release during transportation in a rural area or at a fuel reprocessing plant would be one to two orders of magnitude less, while at a federal waste repository the population dose would be three or more orders of magnitude less than for the metropolitan transportation accident.

Peterson, K.R.; Harvey, T.F.

1980-09-01

297

An overview of metals recovery from thermal power plant solid wastes.  

PubMed

Thermal power plants (TPPs) that burn fossil fuels emit several pollutants linked to the environmental problems of acid rain, urban ozone, and the possibility of global climate change. As coal is burned in a power plant, its noncombustible mineral content is partitioned into bottom ash, which remains in the furnace, and fly ash, which rises with flue gases. Two other by-products of coal combustion air-pollution control technologies are flue gas desulfurization (FGD) wastes and fluidized-bed combustion (FBC) wastes. This paper analyzed and summarized the generation, characteristics and application of TPP solid wastes and discussed the potential effects of such solid wastes on the environment. On this basis, a review of a number of methods for recovery of metals from TPP solid wastes was made. They usually contain a quantity of valuable metals and they are actually a secondary resource of metals. By applying mineral processing technologies and hydrometallurgical and biohydrometallurgical processes, it is possible to recover metals such as Al, Ga, Ge, Ca, Cd, Fe, Hg, Mg, Na, Ni, Pb, Ra, Th, V, Zn, etc., from TPP solid wastes. Recovery of metals from such wastes and its utilization are important not only for saving metal resources, but also for protecting the environment. PMID:20702078

Meawad, Amr S; Bojinova, Darinka Y; Pelovski, Yoncho G

2010-12-01

298

They`re up! They`re down! They`re waste-to-energy plants  

SciTech Connect

Burning garbage - either just to get rid of it, or to recover its latent energy as heat or electricity - has never been a sweet-sounding or -smelling idea. Long before the first boiler and turbine/generator were integrated with a trash incinerator - turning it into a waste-to-energy (WTE) plant - public concern about the air pollution produced by burning municipal solid waste (MSW) began placing an upper bound on the growth of the WTE industry, as it continues to do today. This paper describes some statistics, benefits and problems related to WTE plants.

Varrasi, J.

1996-03-01

299

Mechanical-biological treatment: performance and potentials. An LCA of 8 MBT plants including waste characterization.  

PubMed

In the endeavour of avoiding presence of biodegradable waste in landfills and increasing recycling, mechanical-biological treatment (MBT) plants have seen a significant increase in number and capacity in the last two decades. The aim of these plants is separating and stabilizing the quickly biodegradable fraction of the waste as well as recovering recyclables from mixed waste streams. In this study the environmental performance of eight MBT-based waste management scenarios in Spain was assessed by means of life cycle assessment. The focus was on the technical and environmental performance of the MBT plants. These widely differed in type of biological treatment and recovery efficiencies. The results indicated that the performance is strongly connected with energy and materials recovery efficiency. The recommendation for upgrading and/or commissioning of future plants is to optimize materials recovery through increased automation of the selection and to prioritize biogas-electricity production from the organic fraction over direct composting. The optimal strategy for refuse derived fuel (RDF) management depends upon the environmental compartment to be prioritized and the type of marginal electricity source in the system. It was estimated that, overall, up to ca. 180-190 kt CO2-eq. y(-1) may be saved by optimizing the MBT plants under assessment. PMID:23850761

Montejo, Cristina; Tonini, Davide; Márquez, María del Carmen; Astrup, Thomas Fruergaard

2013-10-15

300

Waste fuel, EMS may save plant $1M yearly  

SciTech Connect

A mixture of paper trash and coal ash fueling an Erie, Pa. General Electric plant and a Network 90 microprocessor-based energy-management system (EMS) to optimize boiler efficiency will cost about $3 million and have a three-to-four-year payback. Over half the savings will come from the avoided costs of burning plant-generated trash. The EMS system will monitor fuel requirements in the boiler and compensate for changes in steam demand. It will also monitor plant electrical needs and control the steam diverted for cogeneration. (DCK)

Barber, J.

1982-05-24

301

The pollution characteristics of odor, volatile organochlorinated compounds and polycyclic aromatic hydrocarbons emitted from plastic waste recycling plants  

Microsoft Academic Search

Plastic waste treatment trends toward recycling in many countries; however, the melting process in the facilities which adopt material recycling method for treating plastic waste may emit toxicants and cause sensory annoyance. The objectives of this study were to analyze the pollution characteristics of the emissions from the plastic waste recycling plants, particularly in harmful volatile organochlorinated compounds, polycyclic aromatic

Chung-Jung Tsai; Mei-Lien Chen; Keng-Fu Chang; Fu-Kuei Chang; I-Fang Mao

2009-01-01

302

Waste-minimization assessment for a bumper-refinishing plant. Environmental research brief  

SciTech Connect

The U.S. Environmental Protection Agency (EPA) has funded a pilot project to assist small- and medium-size manufacturers who want to minimize their generation of hazardous waste but who lack the expertise to do so. Waste Minimization Assessment Centers (WMACs) were established at selected universities and procedures were adapted from the EPA Waste Minimization Opportunity Assessment Manual (EPA/625/7-88/003, July 1988). The WMAC team at Colorado State University inspected a plant refinishing steel, aluminum, and plastic bumpers. The plant is new and already incorporates many hazardous waste management features. After the bumpers are straightened, the processes to remove old plating and coating, the rinsing, the caustic cleaning for steel bumpers and de-smuting for aluminum ones, followed by more rinsing generates significant quantities of waste. Aluminum bumpers are then reanodized at another location; the steel bumpers are soaked in cleaning solutions and rinsed, creating still more waste, before being electrolytically replated with nickel and chromium. The team's report, detailing findings and recommendations, indicated that the greatest waste reduction could occur with the use of additional filtration along with the existing deionization systems. Their use would reduce chromium and nickel levels in rinse waters and other liquid streams to levels acceptable for recycle to the plant. The collected solids would go to a landfill for disposal. Because steel and aluminum bumpers generate the most waste, plastic bumpers were not considered for the purpose of the assessment. The Research Brief was developed by the principal investigators and EPA's Risk Reduction Engineering Laboratory, Cincinnati, OH, to announce key findings of an ongoing research project that is fully documented in a separate report of the same title available from the authors.

Kirsch, F.W.; Looby, G.P.

1991-07-01

303

Management of radioactive waste from nuclear power plants  

SciTech Connect

Even thought risk assessment is an essential consideration in all projects involving radioactive or hazardous waste, its public role is often unclear, and it is not fully utilized in the decision-making process for public acceptance of such facilities. Risk assessment should be an integral part of such projects and should play an important role from beginning to end, i.e., from planning stages to the closing of a disposal facility. A conceptual model that incorporates all potential pathways of exposure and is based on site-specific conditions is key to a successful risk assessment. A baseline comparison with existing standards determines, along with other factors, whether the disposal site is safe. Risk assessment also plays a role in setting priorities between sites during cleanup actions and in setting cleanup standards for certain contaminants at a site. The applicable technologies and waste disposal designs can be screened through risk assessment.

Not Available

1993-09-01

304

High Level Waste Remote Handling Equipment in the Melter Cave Support Handling System at the Hanford Waste Treatment Plant  

SciTech Connect

Cold war plutonium production led to extensive amounts of radioactive waste stored in tanks at the Department of Energy's (DOE) Hanford site. Bechtel National, Inc. is building the largest nuclear Waste Treatment Plant in the world located at the Department of Energy's Hanford site to immobilize the millions of gallons of radioactive waste. The site comprises five main facilities; Pretreatment, High Level Waste vitrification, Low Active Waste vitrification, an Analytical Lab and the Balance of Facilities. The pretreatment facilities will separate the high and low level waste. The high level waste will then proceed to the HLW facility for vitrification. Vitrification is a process of utilizing a melter to mix molten glass with radioactive waste to form a stable product for storage. The melter cave is designated as the High Level Waste Melter Cave Support Handling System (HSH). There are several key processes that occur in the HSH cell that are necessary for vitrification and include: feed preparation, mixing, pouring, cooling and all maintenance and repair of the process equipment. Due to the cell's high level radiation, remote handling equipment provided by PaR Systems, Inc. is required to install and remove all equipment in the HSH cell. The remote handling crane is composed of a bridge and trolley. The trolley supports a telescoping tube set that rigidly deploys a TR 4350 manipulator arm with seven degrees of freedom. A rotating, extending, and retracting slewing hoist is mounted to the bottom of the trolley and is centered about the telescoping tube set. Both the manipulator and slewer are unique to this cell. The slewer can reach into corners and the manipulator's cross pivoting wrist provides better operational dexterity and camera viewing angles at the end of the arm. Since the crane functions will be operated remotely, the entire cell and crane have been modeled with 3-D software. Model simulations have been used to confirm operational and maintenance functional and timing studies throughout the design process. Since no humans can go in or out of the cell, there are several recovery options that have been designed into the system including jack-down wheels for the bridge and trolley, recovery drums for the manipulator hoist, and a wire rope cable cutter for the slewer jib hoist. If the entire crane fails in cell, the large diameter cable reel that provides power, signal, and control to the crane can be used to retrieve the crane from the cell into the crane maintenance area. (authors)

Bardal, M.A. [PaR Systems, Inc., Shoreview, MN (United States); Darwen, N.J. [Bechtel National, Inc., Richland, WA (United States)

2008-07-01

305

Waste Isolation Pilot Plant design validation: Final report, Appendices  

SciTech Connect

This volume is comprised of the following appendices: DOE stipulated agreement with State of New Mexico (partial); geologic correlations; mathematical simulation of underground in situ behavior; C and SH shaft geologic logs and maps; waste shaft geologic logs and maps; exhaust shaft geologic log; test rooms geologic maps and sections; drift cross sections; facility level geologic core hole logs; geomechanical instrumentation data plots; and analytical data plots.

Not Available

1986-10-01

306

Power plant land availability constraints on waste heat utilization  

Microsoft Academic Search

An assessment of land available at nuclear power stations was performed in an effort to determine the limitations land availability would impose on the implementation of reject-heat-utilization systems. A waste-heat-utilization factor was defined for all operating and planned nuclear power stations for which a Preliminary Safety Analysis Report had been filed. This factor is the percentage of the station's reject

M. Olszewski; H. R. Bigelow

1978-01-01

307

Codigestion of manure and organic waste at centralized biogas plants  

Microsoft Academic Search

Abstract The present study focuses on process inhibitions in Danish centralized biogas plants. Collection of data from the plants and a number,of interviews sho wed that inhibitions occur frequently. High concentrations of ammonia, long chain fatty acids o r other inhibitory compounds, and foaming in prestorage tanks are well known,causes of inhibitio n. These problems,mainly occurs due to: 1) inadequate

H. b. Nielsen; I. Angelidaki

308

Application of a Plasma Mass Separator to Advanced LWR Spent Fuel Reprocessing  

SciTech Connect

The US Department of Energy (DOE) is investigating spent fuel reprocessing for the purposes of increasing the effective capacity of a deep geological repository, reducing the radiotoxicity of waste placed in the repository and conserving nuclear fuel resources. DOE is considering hydro-chemical processing of the spent fuel after cutting the fuel cladding and fuel dissolution in nitric acid. The front end process, known as UREX, is largely based on the PUREX process and extracts U, Tc as well as fission product gases. A number of additional processing steps have become known as UREX+. One of the steps includes a further chemical treatment of remove Cs and Sr to reduce repository heat load. Other steps include successive extraction of the actinides from residual fission products, including the lanthanides. The additional UREX+ processing renders the actinides suitable for burning as reactor fuel in an advanced reactor to convert actinides to shorter-lived fission products and to produce power. New methods for separating groups of elements by their atomic mass have been developed and can be exploited to enhance spent fuel reprocessing. These physical processes dry the waste streams so that they can be vaporized and singly ionized in plasma that is contained in longitudinal magnetic and perpendicular electric fields. Proper configuration of the fields causes the plasma to rapidly rotate and expel heavier mass ions at the center of the machine. Lower mass ions form closed orbits within the cylindrical plasma column and are transported to either end of the machine. This plasma mass separator was originally developed to reduce the mass of material that must be immobilized in borosilicate glass from DOE defense waste at former weapons production facilities. The plasma mass separator appears to be well-suited for processing the UREX raffinate and solids streams by exploiting the large atomic mass gap that exists between lanthanides (< {approx}180 amu) and actinides (> {approx}220 amu). In one processing step the raffinate and solids would be separated into a group of residual fission products including the lanthanides and another group containing predominately Pu and mixed higher actinides. The plasma mass separator could process the UREX raffinate and solids directly for spent fuel that has cooled for 50 years or more, but there may be some advantage to removing Cs and Sr by hydro-chemical means for relatively short ({approx}10 years) cooled fuel. This paper will explore the potential cost and environmental impact advantages of combining a hydro-chemical front end with a plasma mass separator back end in an advanced spent fuel reprocessing plant. (authors)

Freeman, Richard; Miller, Robert; Papay, Larry; Wagoner, John [Archimedes Technology Group, 5660 Eastgate Drive, San Diego, CA 92121 (United States); Ahlfeld, Charles; Czerwinski, Ken [Department of Chemistry, University of Nevada, Las Vegas, 4505 Maryland Parkway, Box 454003, Las Vegas, Nevada 89154-4003 (United States)

2006-07-01

309

Assessment of bacteria and virus emissions at a refuse-derived fuel plant and other waste-handling facilities  

Microsoft Academic Search

The results of work carried out by Midwest Research Institute for the Environmental Protection Agency to determine relative levels of bacteria are presented in order to compare these levels at the St. Louis Refuse Processing Plant with those at four other types of waste handling facilities (i.e., an incinerator, a waste transfer station, a wastewater treatment plant, and a landfill).

D. E. Fiscus; P. G. Gorman; M. P. Schrag; L. J. Shannon

1978-01-01

310

Determination of evapotranspiration from an alfalfa crop irrigated with saline waste water from an electrical power plant  

Microsoft Academic Search

Investigations were carried out in 1989 to determine the evapotranspiration (ET) of alfalfa when irrigated with saline waste water coming from the evaporation of fresh water in the cooling towers of Utah Power and Light Company Electrical Power Plant at Huntington in central Utah, U.S.A. The primary goal is to dispose of the waste water from the power plant by

Esmaiel Malek; Gail E. Bingham; Gregory D. McCurdy; R. John Hanks

1992-01-01

311

Environmental odours assessment from waste treatment plants: dynamic olfactometry in combination with sensorial analysers "electronic noses".  

PubMed

After an overview about the criteria of odour nuisance in different technical laws, about electronic noses analysers and about dynamic olfactometry, in the present paper the authors describe an application of dynamic olfactometry in combination with the determinations of electronic noses. The coordination of the two approaches permits optimisation of the advantages offered by both methods to the measurable and objective evaluation of the odour nuisance from waste treatment plants and chemical plants. PMID:16766175

Littarru, Paolo

2007-01-01

312

Environmental odours assessment from waste treatment plants: Dynamic olfactometry in combination with sensorial analysers 'electronic noses'  

SciTech Connect

After an overview about the criteria of odour nuisance in different technical laws, about electronic noses analysers and about dynamic olfactometry, in the present paper the authors describe an application of dynamic olfactometry in combination with the determinations of electronic noses. The coordination of the two approaches permits optimisation of the advantages offered by both methods to the measurable and objective evaluation of the odour nuisance from waste treatment plants and chemical plants.

Littarru, Paolo [Department of Chemical Engineering, Materials, Raw Materials and Metallurgy, c/o Chair of Applied Environmental Chemistry - University of Rome 'La Sapienza', Via Eudossiana 18, 00184 Rome (Italy) and Petroltecnica S.r.l. Via Rovereta 32 - Cerasolo Ausa di Coriano, Rimini (Italy)]. E-mail: p_lit@hotmail.com

2007-07-01

313

Waste-to-energy plant for paper industry sludges disposal: technical-economic study  

Microsoft Academic Search

In this work, a detailed technical-economic analysis of a fluidized bed based waste-to-energy system for disposal of paper manufacturing sludges has been carried out. Specific reference is made to a case study represented by the largest plant in Italy producing recycled paper, with a daily sludge output of about 52t.The adopted plant has been sized for a nominal capacity of

Antonio C. Caputo; Pacifico M. Pelagagge

2001-01-01

314

Seismic Response of a Deep Underground Geologic Repository for Nuclear Waste at the Waste Isolation Pilot Plant in New Mexico  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) is a deep underground nuclear waste repository certified by the U.S. Environmental Protection Agency ,(EPA) to store transuranic defense-related waste contaminated by small amounts of radioactive materials. Located at a depth of about 655 meters below the surface, the facility is sited in southeastern New Mexico, about 40 Department of Energy underground facilities, waste disposal. kilometers east of the city of Carlsbad, New Mexico. The U.S. (DOE) managed the design and construction of the surface and and remains responsible for operation and closure following The managing and operating contractor for the DOE at the WIPP, Westinghouse Electric Corporation, maintains two rechmiant seismic monitoring systems located at the surface and in the underground. This report discusses two earthquakes detected by the seismic monitoring system, one a duratior magnitude 5.0 (Md) event located approximately 60 km east-southeast of the facility, and another a body-wave magnitude 5.6 (rob) event that occurred approximately 260 kilometers to the south-southeast.

Sanchez, P.E.

1998-11-02

315

The Waste Isolation Pilot Plant - An International Center of Excellence for ''Training in and Demonstration of Waste Disposal Technologies''  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) site, which is managed and operated by the United States (U.S.) Department of Energy (USDOE) Carlsbad Field Office (CBFO) and located in the State of New Mexico, presently hosts an underground research laboratory (URL) and the world's first certified and operating deep geological repository for safe disposition of long-lived radioactive materials (LLRMs). Both the URL and the repository are situated approximately 650 meters (m) below the ground surface in a 250-million-year-old, 600-m-thick, undisturbed, bedded salt formation, and they have been in operation since 1982 and 1999, respectively. Founded on long-standing CBFO collaborations with international and national radioactive waste management organizations, since 2001, WIPP serves as the Center of Excellence in Rock Salt for the International Atomic Energy Agency's (IAEA's) International Network of Centers on ''Training in and Demonstration of Waste Disposal Technologies in Underground Research Facilities'' (the IAEA Network). The primary objective for the IAEA Network is to foster collaborative projects among IAEA Member States that: supplement national efforts and promote public confidence in waste disposal schemes; contribute to the resolution of key technical issues; and encourage the transfer and preservation of knowledge and technologies.

Matthews, Mark L.; Eriksson, Leif G.

2003-02-25

316

Energy and greenhouse gas balances for a solid waste incineration plant: a case study.  

PubMed

Energy and greenhouse gas balances for a waste incineration plant (Reno-Nord I/S, Aalborg, Denmark) as a function of time over a 45-year period beginning 1960 are presented. The quantity of energy recovered from the waste increased over time due to increasing waste production, increasing lower heating value of the waste and implementation of improved energy recovery technology at the incineration plant. Greenhouse gas (GHG) balances indicated progressively increasing GHG savings during the time period investigated as a result of the increasing energy production. The GHG balances show that the Reno-Nord incineration plant has changed from a net annual GHG emission of 30 kg CO(2)-eq person(-1) year(-1) to a net annual GHG saving of 770 kg CO(2)-eq person(-1) year(-1) which is equivalent to approximately 8% of the annual emission of GHG from an average Danish person (including emissions from industry and transport). The CO(2) emissions associated with combustion of the fossil carbon contained in the waste accounted for about two-thirds of the GHG turnover when no energy recovery is applied but its contribution reduces to between 10 and 15% when energy recovery is implemented. The reason being that energy recovery is associated with a large CO(2) saving (negative emission). PMID:21746759

Brinck, Kim; Poulsen, Tjalfe G; Skov, Henrik

2011-10-01

317

Unit operations used to treat process and/or waste streams at nuclear power plants. [R  

SciTech Connect

Estimates are given of the annual amounts of each generic type of LLW (i.e., Government and commerical (fuel cycle and non-fuel cycle)) that is generated at LWR plants. Many different chemical engineering unit operations used to treat process and/or waste streams at LWR plants include adsorption, evaporation, calcination, centrifugation, compaction, crystallization, drying, filtration, incineration, reverse osmosis, and solidification of waste residues. The treatment of these various streams and the secondary wet solid wastes thus generated is described. The various treatment options for concentrates or solid wet wastes, and for dry wastes are discussed. Among the dry waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting and shredding. Organic materials (liquids (e.g., oils or solvents) and/or solids), could be incinerated in most cases. The filter sludges, spent resins, and concentrated liquids (e.g., evaporator concentrates) are usually solidified in cement, or urea-formaldehyde or unsaturated polyester resins prior to burial. Incinerator ashes can also be incorporated in these binding agents. Asphalt has not yet been used. This paper presents a brief survey of operational experience at LWRs with various unit operations, including a short discussion of problems and some observations on recent trends.

Godbee, H.W.; Kibbey, A.H.

1980-01-01

318

Management activities for retrieved and newly generated transuranic waste, Savannah River Plant  

SciTech Connect

The purpose of this Environmental Assessment (EA) is to assess the potential environmental impacts of the retrieval and processing of retrieved and newly generated transuranic (TRU) radioactive waste at the Savannah River Plant (SRP), including the transportation of the processes TRU waste to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. A new TRU Waste Facility (TWF) will be constructed at SRP to retrieve and process the SRP TRU waste in interim storage to meet WIPP criteria. This EA has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, and the requirements of the Council of Environmental Quality Regulations for implementing NEPA (40 CFR Parts 1500--1508). The National Environmental Policy Act (NEPA) requires the assessment of environmental consequences of all major federal actions that may affect the quality of the human environment. This document describes the environmental impact of constructing and operating the TWF facility for processing and shipment of the TRU waste to WIPP and considers alternatives to the proposed action. 40 refs., 12 figs., 12 tabs.

Not Available

1988-08-01

319

Correlation of various oxygen demanding parameters in advanced waste-water treatment plants  

SciTech Connect

This study was designed to examine the various oxygen demand parameters and their relationship in a waste-water stream on a unit operation basis as it moves through a variety of state-of-the-art waste-water treatment facilities. Regression techniques were utilized to evaluate if analytical tools can be developed which provide plant operators with fast accurate monitoring techniques for evaluating and interpreting plant performance. Results of this study indicated that the failure to consistently obtain statistical correlations among operational control parameters, including BOD{sub 5}, in similar waste-water treatment facilities may be due to the varying types of compounds present in the raw sewage, and the increase in amount of variability of the non-biodegradable organics as treatment proceeds. The use of surrogate parameters to predict BOD{sub 5} was not warranted.

Rhodes, K.A.

1988-01-01

320

Direct utilization of human liquid wastes by plants in a closed ecosystem  

NASA Astrophysics Data System (ADS)

Model experiments in phytotrons have shown that urea is able to cover 70% of the demand in nitrogen of the conveyer cultivated wheat. At the same time wheat plants can directly utilize human liquid wastes. In this article by human liquid wastes the authors mean human urine only. In a long-term experiment on ``man-higher plants'' system with two crewmen, plants covered 63 m^2, with wheat planted to - 39.6 m^2. For 103 days, complete human urine (total amount - 210.7 l) was supplied into the nutrient solution for wheat. In a month and a half NaCl supply into the nutrient solution stabilized at 0.9-1.65 g/l. This salination had no marked effect on wheat production. The experiment revealed the realistic feasibility to directly involve liquid wastes into the biological turnover of the life support system. The closure of the system, in terms of water, increased by 15.7% and the supply of nutrients for wheat plants into the system was decreased. Closedness of biological turnover of matter in a man-made ``man - higher plants'' ecological system might involve, among other processes, direct utilization of human liquid wastes by plants. The amount of urine comprises 15-20% of the total amount of water cycling within the system including water as part of food, household, hygiene and potable water necessary for man. What is more, it they contains most nitrogen-bearing compounds emitted by man, almost all of the NaCl and some other substances involved in the biological turnover. Human liquid wastes can be utilized either by preliminary physical-chemical treatment (evaporating or freezing out the water, finally oxidizing the organic matter, isolating the mineral components required for plants, etc.) and further involvement of the obtained products or by direct application into the nutrient solution for plants. The challenge of direct utilization is that plants have no need of Na^+ and Cl^-, and also the organic forms of nitrogen emitted by man cannot fully meet the demand of plants for this element. Besides, hygienic and/or psychological reasons make it desirable to avoid direct use of liquid wastes in the nutrient solutions that would have direct contact with edible part of plants (tubers, roots, bulbs). Feasibility of direct utilization of liquid wastes by plants in a closed ``man - higher plants'' ecosystem has been experimentally studied on wheat - grain culture as a model plant with the edible part in the form of seeds spatially dissociated with the nutrient medium. The wheat covered 60-65% of the area under higher plants. The studies have been carried out in ``Bios-3'' experimental facility described in detail elsewhere.

Lisovsky, G. M.; Gitelson, J. I.; Shilenko, M. P.; Gribovskaya, I. V.; Trubachev, I. N.

1997-01-01

321

Automated Sampling and Sample Pneumatic Transport of High Level Tank Wastes at the Hanford Waste Treatment Plant  

SciTech Connect

This paper describes the development work, and design and engineering tasks performed, to provide a fully automated sampling system for the Waste Treatment Plant (WTP) project at the Hanford Site in southeastern Washington State, USA. WTP is being built to enable the emptying and immobilization of highly active waste resulting from processing of irradiated nuclear fuel since the 1940's. The Hanford Tank Wastes are separated into Highly Level Waste (HLW), and Low Active Waste (LAW) fractions, which are separately immobilized by vitrification into borosilicate glass. Liquid samples must be taken of the waste and Glass Forming Chemicals (GFCs) before vitrification, and analyzed to insure the glass products will comply with specifications established in the WTP contract. This paper describes the non-radioactive testing of the sampling of the HLW and LAW melter feed simulants that was performed ahead of final equipment design. These trials were essential to demonstrate the effectiveness and repeatability of the integrated sampling system to collect representative samples, free of cross-contamination. Based on existing tried and proven equipment, the system design is tailored to meet the WTP project's specific needs. The design provides sampling capabilities from 47 separate sampling points and includes a pneumatic transport system to move the samples from the 3 separate facilities to the centralized analytical laboratory. The physical and rheological compositions of the waste simulants provided additional challenges in terms of the sample delivery, homogenization, and sample capture equipment design requirements. The activity levels of the actual waste forms, specified as 486 E9 Bq/liter (Cs-137), 1.92 E9 Bq/liter (Co-60), and 9.67 E9 Bq/liter (Eu-154), influenced the degree of automation provided, and justified the minimization of manual intervention needed to obtain and deliver samples from the process facilities to the analytical laboratories. Maintaining high integrity primary and secondary confinement, including during the cross-site transportation of the samples, is a key requirement that is achieved and assured at all times. (authors)

Phillips, C.; Richardson, J. E. [BNG America, 2345 Stevens Drive, Richland, WA, 99354 (United States)

2006-07-01

322

Optimal design of hybrid separation systems for in-plant waste reduction  

SciTech Connect

A general procedure for using hybrid separation systems to prevent pollution is presented. The design procedure integrates segregation, interception, and recycle. A systematic method developed to identify the optimal design combination is illustrated through a case study. The case study presented is the removal of cresol from aqueous wastes in a tricresyl phosphate plant. 21 refs., 4 figs.

Hamad, A.A.; Crabtree, E.W.; El-Halwagi, M.M. [Auburn Univ., AL (United States); Garrison, G.W. [Matrix Process Integration, Leesburg, VA (United States)

1996-12-31

323

PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION  

Microsoft Academic Search

Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D&D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The

JOHNSTON GA

2008-01-01

324

Basic data report for borehole DOE1. Waste Isolation Pilot Plant (WIPP) Project, Southeastern New Mexico  

Microsoft Academic Search

Borehole DOE-1 is one of several exploratory boreholes drilled at the Waste Isolation Pilot Plant (WIPP) site for the purpose of gathering stratigraphic, hydrologic and structural data. DOE-1 is located in Zone III about 1.25 miles to the southeast of the exploratory shaft location. This project was undertaken for several reasons: to investigate the presence of an anticlinal structure in

Freeland

1982-01-01

325

The influence of humic acids derived from earthworm-processed organic wastes on plant growth  

Microsoft Academic Search

Some effects of humic acids, formed during the breakdown of organic wastes by earthworms (vermicomposting), on plant growth were evaluated. In the first experiment, humic acids were extracted from pig manure vermicompost using the classic alkali\\/acid fractionation procedure and mixed with a soilless container medium (Metro-Mix 360), to provide a range of 0, 50, 100, 150, 200, 250, 500, 1000,

R. M. Atiyeh; S. Lee; C. A. Edwards; N. Q. Arancon; J. D. Metzger

2002-01-01

326

Conceivable new recycling of nuclear waste by nuclear power companies in their plants  

E-print Network

We outline the basic principles and the needed experiments for a conceivable new recycling of nuclear waste by the power plants themselves to avoid its transportation and storage to a (yet unknown) dumping area. Details are provided in an adjoining paper and in patents pending.

Ruggero Maria Santilli

1997-04-09

327

RADIOACTIVE WASTE DISPOSAL PROJECTS. IDAHO CHEMICAL PROCESSING PLANT TECHNICAL PROGRESS REPORT FOR JULY-SEPTEMBER 1959  

Microsoft Academic Search

The progress of extensive laboratory and pilot plant investigations on ; the fluidized bed process for the con version of radioactive liquid wastes to ; solids is reported. These studies are directed toward obtaining information on ; the dynamics of fluidized bed operation, the removal of volatile fission products ; and solids particles from gases, the development of equipment and

C. M. Slansky; F. M. Warzel; J. I. ed. Stevens

1960-01-01

328

Utilization of low value waste heat for an aqua-ammonia refrigeration pilot plant  

SciTech Connect

Design data for absorption refrigeration pilot plants utilizing low quality waste heat from commercial manufacturing operations is described. This facility is being developed as an energy source for commercial freezing and cold storage. Successful completion of this project will have a major impact on energy saving in food refrigeration.

Pigott, G.M.; Bucove, G.

1983-12-01

329

Application of Bayesian Network Learning Methods to Waste Water Treatment Plants  

Microsoft Academic Search

Bayesian Networks have been proposed as an alternative to rule-based systems in domains with uncertainty. Applications in monitoring and control can benefit from this form of knowledge representation. Following the work of Chong and Walley, we explore the possibilities of Bayesian Networks in the Waste Water Treatment Plants (WWTP) monitoring and control domain. We show the advantages of modelling knowledge

Ramón Sangüesa; Phillip Burrell

2000-01-01

330

Biodegradation studies of aniline and nitrobenzene in aniline plant waste water by gas chromatography  

SciTech Connect

A gas chromatographic (GC) method has been developed for studying the biodegradation of aniline and/or nitrobenzene in aniline plant waste water. The effects of various parameters have been reported and critically discussed. The results are precise and afford simultaneous determination of aniline and nitrobenzene.

Patil, S.S.; Shinde, V.M.

1988-10-01

331

Hydraulic testing of Salado Formation evaporites at the Waste Isolation Pilot Plant site: Second interpretive report  

SciTech Connect

Pressure-pulse, constant-pressure flow, and pressure-buildup tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Transmissivities have been interpreted from six sequences of tests conducted on five stratigraphic intervals within 15 m of the WIPP underground excavations.

Beauheim, R.L. [Sandia National Labs., Albuquerque, NM (United States); Roberts, R.M.; Dale, T.F.; Fort, M.D.; Stensrud, W.A. [INTERA, Inc., Austin, TX (United States)

1993-12-01

332

Thermodynamics -2 An industrial plant produces a waste stream of hot compressed air  

E-print Network

Thermodynamics - 2 An industrial plant produces a waste stream of hot compressed air: Pressure P from this stream as it is discharged to the atmosphere (T = 300 K, P = 100 kPa). a) (50 pts.) What is maximum work that can be produced if the air is discharged to the atmosphere at atmospheric pressure

Virginia Tech

333

Operational readiness\\/risk assessment at the waste isolation pilot plant  

Microsoft Academic Search

The Waste Isolation Pilot Plant (WIPP) is currently preparing to enter its operational phase. In preparation, a risk-based management (RBM) program is being developed to ensure maximum safety and reliability of all aspects of facility operation. Training of workers, preparation of procedures, and development of emergency action plans are examples of activities currently being performed. The RBM program will verify

1988-01-01

334

Effect of alternative conceptual models in a preliminary performance assessment for the waste isolation pilot plant  

Microsoft Academic Search

The most appropriate conceptual model for performance assessment (PA) at the waste isolation pilot plant (WIPP) is believed to include gas generation resulting from corrosion and microbial action in the repository, and a dual-porosity (matrix and fracture porosity) representation for the solute transport in the Culebra dolomite member of the Rustler formation. Under these assumptions, complementary cumulative distribution functions (CCDFs)

J. C. Helton; D. R. Anderson; B. L. Baker; J. E. Bean; J. W. Berglund; W. Beyeler; J. W. Garner; H. J. Iuzzolino; M. G. Marietta; R. P. Rechard; P. J. Roache; D. K. Rudeen; J. D. Schreiber; P. N. Swift; M. S. Tierney; P. Vaughn

1995-01-01

335

Milestones for disposal of radioactive waste at the Waste Isolation Pilot Plant (WIPP) in the United States  

SciTech Connect

Since its identification as a potential deep geologic repository in about 1973, the regulatory assessment process for the Waste Isolation Pilot Plant (WIPP) in New Mexico has developed over the past 25 years. National policy issues, negotiated agreements, and court settlements over the first half of the project had a strong influence on the amount and type of scientific data collected. Assessments and studies before the mid 1980s were undertaken primarily (1) to satisfy needs for environmental impact statements, (2) to develop general understanding of selected natural phenomena associated with nuclear waste disposal, or (3) to satisfy negotiated agreements with the State of New Mexico. In the last third of the project, federal compliance policy and actual regulations were sketched out, but continued to evolve until 1996. During this eight-year period, four preliminary performance assessments, one compliance performance assessment, and one verification performance assessment were performed.

Rechard, R.P.

1998-04-01

336

Vermicomposting of distillation waste of citronella plant (Cymbopogon winterianus Jowitt.) employing Eudrilus eugeniae.  

PubMed

Laboratory experiment on vermicomposting of distillation waste of java citronella (Cymbopogon winterianus Jowitt.) was carried out employing Eudrilus eugeniae, in two seasonal trials, covering summer and winter periods. Two vermicomposting treatments were conducted in earthen pots, one with citronella plant waste only (CW) and the other, a mixture of citronella waste and cowdung in the proportion 5:1 (CW+CD). Vermicomposting of citronella waste resulted reduction in C/N ratio (83.5-87.7%), enhancement of ash content and a number of macro and micronutrients. The FT-IR spectroscopy of the vermicompost revealed the reduction in aliphatic and aromatic compound as well as increase in amide group after the 105 days stabilization process. The vermicompost output was significantly enhanced in CW+CD treatment than CW treatment. Even, nutrient content of the vermicompost was also higher in CW+CD treatment than CW alone indicating the positive role of cowdung in improvement of quantity and quality. PMID:21550233

Deka, H; Deka, S; Baruah, C K; Das, J; Hoque, S; Sarma, N S

2011-07-01

337

Final compliance criteria (40 CFR part 194) for the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP), which is under development by the Department of Energy (DOE), is a potential geologic disposal system for defense transuranic (TRU) radioactive waste. Pursuant to the 1992 WIPP Land Withdrawal Act, the U.S. Environmental Protection Agency (EPA) is required to perform several activities including, but not limited to, issuing criteria for determining whether the WIPP complies with the radioactive waste disposal standards in 40 CFR part 191. EPA finalized these compliance criteria (40 CFR part 194), intended to implement the 40 CFR part 191 disposal standards specifically at the WIPP, in February 1996. The paper presents the Agency`s approach to WIPP`s compliance demonstration. This program is unique because the EPA`s approach Laken at the WIPP may set precedent for future approaches Liken at other radioactive disposal facilities. This document addresses many of the nuclear waste issues that are of considerable concern to the public.

Marcinowski, F.; Kruger, M.; Forinash, E. [Environmental Protection Agency, Washington, DC (United States)

1996-06-01

338

Warm water aquaculture using waste heat and water from zero discharge power plants in the Great Basin  

SciTech Connect

Two series of experiments were completed to determine (a) toxicity of waste water from power plants on warm water fish and (b) multiple use of waste heat and water for aquatic animal and plant production. All three types of waste water from a typical coal-fired power plant are acceptable for growing catfish and tilapia following aeration. This growth was compared with fish raised in spring water. Closed, recirculating polyculture systems using evaporation pond water operated efficiently for plant (duckweed) and animal (fish and freshwater prawns) production. Duckweed is an excellent supplement for fish feed. Tilapia and freshwater prawns grew rapidly in the tanks containing duckweed only. 10 references, 13 tables.

Heckmann, R.A.; Winget, R.N.; Infanger, R.C.; Mickelsen, R.W.; Hendersen, J.M.

1984-01-31

339

Wool-waste as organic nutrient source for container-grown plants  

SciTech Connect

A container experiment was conducted to test the hypothesis that uncomposted wool wastes could be used as nutrient source and growth medium constituent for container-grown plants. The treatments were: (1) rate of wool-waste application (0 or unamended control, 20, 40, 80, and 120 g of wool per 8-in. pot), (2) growth medium constituents [(2.1) wool plus perlite, (2.2) wool plus peat, and (2.3) wool plus peat plus perlite], and (3) plant species (basil and Swiss chard). A single addition of 20, 40, 80, or 120 g of wool-waste to Swiss chard (Beta vulgaris L.) and basil (Ocimum basilicum L.) in pots with growth medium provided four harvests of Swiss chard and five harvests of basil. Total basil yield from the five harvests was 1.6-5 times greater than the total yield from the unamended control, while total Swiss chard yield from the four harvests was 2-5 times greater relative to the respective unamended control. The addition of wool-waste to the growth medium increased Swiss chard and basil tissue N, and NO{sub 3}-N and NH{sub 4}-N in growth medium relative to the unamended control. Scanning electron microscopy (SEM) and energy dispersive X-ray (EDX) microanalysis of wool fibers sampled at the end of the experiments indicated various levels of decomposition, with some fibers retaining their original surface structure. Furthermore, most of the wool fibers' surfaces contained significant concentrations of S and much less N, P, or K. SEM/EDX revealed that some plant roots grow directly on wool-waste fibers suggesting either (1) root directional growth towards sites with greater nutrient concentration and/or (2) a possible role for roots or root exudates in wool decomposition. Results from this study suggest that uncomposted wool wastes can be used as soil amendment, growth medium constituent, and nutrient source for container-grown plants.

Zheljazkov, Valtcho D. [Mississippi State University, North Mississippi Research and Extension Center, Verona, MS 38879 (United States)], E-mail: vj40@pss.msstate.edu; Stratton, Glenn W. [Department of Plant and Animal Sciences and Department of Environmental Sciences, Nova Scotia Agricultural College, Truro, NS, B2N 5E3 (Canada); Pincock, James [Department of Chemistry, Dalhousie University, Halifax, NS, B3H 4J3 (Canada); Butler, Stephanie [Department of Plant and Animal Sciences and Department of Environmental Sciences, Nova Scotia Agricultural College, Truro, NS, B2N 5E3 (Canada); Jeliazkova, Ekaterina A. [Mississippi State University, Department of Plant and Soil Sciences, Mississippi State, MS 39762 (United States); Nedkov, Nedko K. [Research Institute for Roses and Aromatic Crops, 49 Osvobojdenie Blv., Kazanluk (Bulgaria); Gerard, Patrick D. [Department of Applied Economics and Statistics, Clemson University, Clemson, SC 29634 (United States)

2009-07-15

340

Knowledge-based and model-based hybrid methodology for comprehensive waste minimization in electroplating plants  

NASA Astrophysics Data System (ADS)

The electroplating industry of over 10,000 planting plants nationwide is one of the major waste generators in the industry. Large quantities of wastewater, spent solvents, spent process solutions, and sludge are the major wastes generated daily in plants, which costs the industry tremendously for waste treatment and disposal and hinders the further development of the industry. It becomes, therefore, an urgent need for the industry to identify technically most effective and economically most attractive methodologies and technologies to minimize the waste, while the production competitiveness can be still maintained. This dissertation aims at developing a novel WM methodology using artificial intelligence, fuzzy logic, and fundamental knowledge in chemical engineering, and an intelligent decision support tool. The WM methodology consists of two parts: the heuristic knowledge-based qualitative WM decision analysis and support methodology and fundamental knowledge-based quantitative process analysis methodology for waste reduction. In the former, a large number of WM strategies are represented as fuzzy rules. This becomes the main part of the knowledge base in the decision support tool, WMEP-Advisor. In the latter, various first-principles-based process dynamic models are developed. These models can characterize all three major types of operations in an electroplating plant, i.e., cleaning, rinsing, and plating. This development allows us to perform a thorough process analysis on bath efficiency, chemical consumption, wastewater generation, sludge generation, etc. Additional models are developed for quantifying drag-out and evaporation that are critical for waste reduction. The models are validated through numerous industrial experiments in a typical plating line of an industrial partner. The unique contribution of this research is that it is the first time for the electroplating industry to (i) use systematically available WM strategies, (ii) know quantitatively and accurately what is going on in each tank, and (iii) identify all WM opportunities through process improvement. This work has formed a solid foundation for the further development of powerful WM technologies for comprehensive WM in the following decade.

Luo, Keqin

1999-11-01

341

Validating CFD Models of Multiphase Mixing in the Waste Treatment Plant at the Hanford Site  

SciTech Connect

The Columbia River in Washington State is threatened by the radioactive legacy of the cold war. Two hundred thousand cubic meters (fifty-three million US gallons) of radioactive waste is stored in 177 underground tanks (60% of the Nation's radioactive waste). A vast complex of waste treatment facilities is being built to convert this waste into stable glass (vitrification). The waste in these underground tanks is a combination of sludge, slurry, and liquid. The waste will be transported to a pre-treatment facility where it will be processed before vitrification. It is necessary to keep the solids in suspension during processing. The mixing devices selected for this task are known as pulse-jet mixers (PJMs). PJMs cyclically empty and refill with the contents of the vessel to keep it mixed. The transient operation of the PJMs has been proven successful in a number of applications, but needs additional evaluation to be proven effective for the slurries and requirements at the Waste Treatment Plant (WTP). Computational fluid dynamic (CFD) models of mixing vessels have been developed to demonstrate the ability of the PJMs to meet mixing criteria. Experimental studies have been performed to validate these models. These tests show good agreement with the transient multiphase CFD models developed for this engineering challenge. (authors)

Rosendall, Brigette; Barringer, Chris; Wen, Feng; Knight, Kelly J. [Bechtel National, Inc. (United States)

2006-07-01

342

Characterisation of radioactive waste products associated with plant decommissioning.  

PubMed

The inventory of radioactivity that must be considered in the decommissioning of a typical 1000 MWe Spanish pressurised water reactor (PWR) was investigated as part of a generic plant decommissioning study. Analyses based on DORT models (in both R-Z and R-theta geometries) were used with representative plant operating history and core power distribution data in defining the expected neutron environment in regions near the reactor core. The activation analyses were performed by multiplying the DORT scalar fluxes by energy-dependent reaction cross sections (based on ENDF/B-VI data) to generate reaction rates on a per atom basis. The results from the ORIGEN2 computer code were also used for determining the activities associated with certain nuclides where multi-group cross section data were not available. In addition to the bulk material activation of equipment and structures near the reactor, the activated corrosion-product (or 'crud') deposits on system and equipment surfaces were considered. The projected activities associated with these sources were primarily based on plant data and experience from operating PWR plants. PMID:16381771

Sejvar, J; Fero, A H; Gil, C; Hagler, R J; Santiago, J L; Holgado, A; Swenson, R

2005-01-01

343

Power recovery from waste heat in modern turboexpander plants  

Microsoft Academic Search

The object of this study is to determine the feasibility and cost of installing a power recovery system in an existing gas processing plant. The power generated by the system is to be used to drive a residue gas compressor, a refrigeration compressor and the heat medium circulating pump, each having its own expander driver. For this purpose the heat

S. Mafi; C. Drake

1981-01-01

344

A short history of waste management at the Hanford Site  

NASA Astrophysics Data System (ADS)

The world’s first full-scale nuclear reactors and chemical reprocessing plants built at the Hanford Site in the desert of southeastern Washington State produced two-thirds of the plutonium generated in the United States for nuclear weapons. Operating these facilities also created large volumes of radioactive and chemical waste, some of which was released into the environment exposing people who lived downwind and downstream. Hanford now contains the largest accumulation of nuclear waste in the Western Hemisphere. Hanford’s last reactor shut down in 1987 followed by closure of the last reprocessing plant in 1990. Today, Hanford’s only mission is cleanup. Most onsite radioactive waste and nuclear material lingers inside underground tanks or storage facilities. About half of the chemical waste remains in tanks while the rest persists in the soil, groundwater, and burial grounds. Six million dollars each day, or nearly two billion dollars each year, are spent on waste management and cleanup activities. There is significant uncertainty in how long cleanup will take, how much it will cost, and what risks will remain for future generations. This paper summarizes portions of the waste management history of the Hanford Site published in the book “Hanford: A Conversation about Nuclear Waste and Cleanup.” ( Gephart, 2003).

Gephart, Roy E.

345

Disease suppression on greenhouse tomatoes using plant waste compost.  

PubMed

This study investigated the disease suppression abilities of a compost amendment that was added to the conventional growing medium, yellow cedar sawdust, used in most British Columbia vegetable greenhouses. The compost amendment was produced in a controlled, in-vessel process primarily from greenhouse crop waste materials. The pathogen and cultivar under study were Fusarium oxysporum f. sp. radicis-lycopersici (FORL) on Dombito (FORL-susceptible) beefsteak greenhouse tomatoes. Significant reduction of Fusarium crown and root rot was also realized in tomato seedlings by applying compost amendment from several different batches, as a seed cover or plug substitute. In a greenhouse trial, disease suppression using a mixture of 2:1 sawdust to amendment by volume was shown to be most effective. As a result, the tomato yield over a nine-month growing season was improved by 74% where the medium was deliberately infested with FORL. PMID:15913017

Cheuk, William; Lo, Kwang Victor; Copeman, Robert; Joliffe, Peter; Fraser, Bud S

2005-01-01

346

Transfer of elements relevant to radioactive waste from soil to five boreal plant species.  

PubMed

In long-term safety assessment models for radioactive waste disposal, uptake of radionuclides by plants is an important process with possible adverse effects in ecosystems. Cobalt-60, (59,63)Ni, (93)Mo, and (210)Pb are examples of long-living radionuclides present in nuclear waste. The soil-to-plant transfer of stable cobalt, nickel, molybdenum and lead and their distribution across plant parts were investigated in blueberry (Vaccinium myrtillus), May lily (Maianthemum bifolium), narrow buckler fern (Dryopteris carthusiana), rowan (Sorbus aucuparia) and Norway spruce (Picea abies) at two boreal forest sites in Eastern Finland. The concentrations of all of the studied elements were higher in roots than in above-ground plant parts showing that different concentration ratios (CR values) are needed for modelling the transfer to roots and stems/leaves. Some significant differences in CR values were found in comparisons of different plant species and of the same species grown at different sites. However, large within-species variation suggests that it is not justified to use different CR values for modelling soil-to-plant transfer of these elements in the different boreal forest plant species. PMID:21190719

Roivainen, Päivi; Makkonen, Sari; Holopainen, Toini; Juutilainen, Jukka

2011-04-01

347

Native Plant Uptake Model for Radioactive Waste Disposal Areas at the Nevada Test Site  

SciTech Connect

This report defines and defends the basic framework, methodology, and associated input parameters for modeling plant uptake of radionuclides for use in Performance Assessment (PA) activities of Radioactive Waste Management Sites (RWMS) at the Nevada Test Site (NTS). PAs are used to help determine whether waste disposal configurations meet applicable regulatory standards for the protection of human health, the environment, or both. Plants adapted to the arid climate of the NTS are able to rapidly capture infiltrating moisture. In addition to capturing soil moisture, plant roots absorb nutrients, minerals, and heavy metals, transporting them within the plant to the above-ground biomass. In this fashion, plant uptake affects the movement of radionuclides. The plant uptake model presented reflects rooting characteristics important to plant uptake, biomass turnover rates, and the ability of plants to uptake radionuclides from the soil. Parameters are provided for modeling plant uptake and estimating surface contaminant flux due to plant uptake under both current and potential future climate conditions with increased effective soil moisture. The term ''effective moisture'' is used throughout this report to indicate the soil moisture that is available to plants and is intended to be inclusive of all the variables that control soil moisture at a site (e.g., precipitation, temperature, soil texture, and soil chemistry). Effective moisture is a concept used to simplify a number of complex, interrelated soil processes for which there are too little data to model actual plant available moisture. The PA simulates both the flux of radionuclides across the land surface and the potential dose to humans from that flux. Surface flux is modeled here as the amount of soil contamination that is transferred from the soil by roots and incorporated into aboveground biomass. Movement of contaminants to the surface is the only transport mechanism evaluated with the model presented here. Parameters necessary for estimating surface contaminant flux due to native plants expected to inhabit the NTS RWMSS are developed in this report. The model is specific to the plant communities found at the NTS and is designed for both short-term (<1,000 years) and long-term (>1,000 years) modeling efforts. While the model has been crafted for general applicability to any NTS PA, the key radionuclides considered are limited to the transuranic (TRU) wastes disposed of at the NTS.

BROWN,THERESA J.; WIRTH,SHARON

1999-09-01

348

Socioeconomic study for the proposed waste isolation pilot plant  

SciTech Connect

This document presents the historical and existing socioeconomic conditions in the vicinity of the proposed plant, projected changes in those conditions with and without the plant, and an outline of the various techniques used to make these projections. The analysis predicts impacts on the general economy in the area near the plant and on employment, personal income, population, social structure, the private economic sector, housing, land use, community services and facilities, and local government finances. Among the most important results are the following predictions: The economy of the area will derive $165 million directly and indirectly during the first 7.5 years of the project. After that, it will derive about $21 million directly and indirectly during each year of full operation. About 2100 jobs will be created directly and indirectly at the peak of the construction and about 950 jobs during the full operation. A net in-migration will occur: about 2250 people at the peak of the construction and about 1000 people during operation. A housing shortage may begin in Carlsbad in 1981 or 1982 and last for about 2 years.

Not Available

1980-10-01

349

Environmental impact statement for initiation of transuranic waste disposal at the waste isolation pilot plant  

SciTech Connect

WIPP`s long-standing mission is to demonstrate the safe disposal of TRU waste from US defense activities. In 1980, to comply with NEPA, US DOE completed its first environmental impact statement (EIS) which compared impacts of alternatives for TRU waste disposal. Based on this 1980 analysis, DOE decided to construct WIPP in 1981. In a 1990 decision based on examination of alternatives in a 1990 Supplemental EIS, DOE decided to continue WIPP development by proceeding with a testing program to examine WIPP`s suitability as a TRU waste repository. Now, as DOE`s Carlsbad Area Office (CAO) attempts to complete its regulatory obligations to begin WIPP disposal operations, CAO is developing WIPP`s second supplemental EIS (SEIS-II). To complete the SEIS-II, CAO will have to meet a number of challenges. This paper explores both the past and present EISs prepared to evaluate the suitability of WIPP. The challenges in completing an objective comparison of alternatives, while also finalizing other critical-path compliance documents, controlling costs, and keeping stakeholders involved during the decision-making process are addressed.

Johnson, H.E. [U.S. Dept. of Energy, Carlsbad, NM (United States) Carlsbad Area Office; Whatley, M.E. [Westinghouse Electric Corp., Carlsbad, NM (United States). Waste Isolation Div.

1996-08-01

350

Study of waste-heat recovery and utilization at the Farmington Municipal Power Plant. Final report, December 1, 1980June 30, 1981  

Microsoft Academic Search

An examination was made of the technical and economc feasibility of utilizing waste heat from the Farmington Municipal Power Plant. First, the production cycles of the natural-gas-fired plant were assessed to determine the quantity and quality of recoverable waste heat created by the plant during its operation. Possibilities for utilizing waste heat from the exhaust gases and the cooling water

G. G. Leigh; W. R. Edgel; K. T. Jr. Feldman; E. J. Moss

1982-01-01

351

40 CFR Appendix A to Part 194 - Certification of the Waste Isolation Pilot Plant's Compliance With the 40 CFR Part 191 Disposal...  

...Certification of the Waste Isolation Pilot Plant's Compliance With the 40 CFR Part 191...RE-CERTIFICATION OF THE WASTE ISOLATION PILOT PLANT'S COMPLIANCE WITH THE 40 CFR PART 191...Certification of the Waste Isolation Pilot Plant's Compliance With the 40 CFR Part...

2014-07-01

352

Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 1  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) is a research and development facility for the demonstration of the permanent isolation of transuranic radioactive wastes in a geologic formation. The facility was constructed in southeastern New Mexico in a manner intended to meet criteria established by the scientific and regulatory community for the safe, long-term disposal of transuranic wastes. The US Department of Energy (DOE) is preparing an application to demonstrate compliance with the requirements outlined in Title 40, Part 191 of the Code of Federal Regulations (CFR) for the permanent disposal of transuranic wastes. As mandated by the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act of 1992, the US Environmental Protection Agency (EPA) must evaluate this compliance application and provide a determination regarding compliance with the requirements within one year of receiving a complete application. Because the WIPP is a very complex program, the DOE has planned to submit the application as a draft in two parts. This strategy will allow for the DOE and the EPA to begin technical discussions on critical WIPP issues before the one-year compliance determination period begins. This report is the first of these two draft submittals.

NONE

1995-03-31

353

Feasibility study for a demonstration plant for liquefaction and coprocessing of waste plastics and tires  

SciTech Connect

The results of a feasibility study for a demonstration plant for the liquefaction of waste polymers and the coprocessing of waste polymers with coal are presented. The study was carried out by a committee of participants from five universities, the US DOE Federal Energy Technology Center, and Burns and Roe Corporation. The study included an assessment of current recycling practices, a review of pertinent research, and a survey of feedstock availability. A conceptual design for a demonstration plant was developed and a preliminary economic analysis for various feedstock mixes was carried out. The base case for feedstock scenarios was chosen to be 200 tons per day of waste plastic and 200 tons per day of waste tires. For this base case, the return on investment (ROI) was found to range from 8% to 16% as tipping fees for waste plastic and tires increased over a range comparable to that existing in the US. A number of additional feedstock scenarios that were both more and less profitable were also considered and are briefly discussed.

Huffman, G.P.; Shah, N.; Shelley, M.; El-Halwagi, M.; Schindler, H.; Eastman, M.

1998-07-01

354

Feasibility study for a demonstration plant for liquefaction and coprocessing of waste plastics and tires  

SciTech Connect

The results of a feasibility study for a demonstration plant for the liquefaction of waste polymers and the coprocessing of waste polymers with coal are presented. The study was carried out by a committee of participants from five universities, the US DOE Federal Energy Technology Center, and Burns & Roe Corporation. The study included an assessment of current recycling practices, a review of pertinent research, and a survey of feedstock availability. A conceptual design for a demonstration plant was developed and a preliminary economic analysis for various feedstock mixes was carried out. The base case for feedstock scenarios was chosen to be 200 tons per day of waste plastic and 100 tons per day of waste tires. For this base case, the return on investment (ROI) was found to range from 8% to 16% as tipping fees for waste plastic and tires increased over a range comparable to that existing in the US. A number of additional feedstock scenarios that were both more and less profitable were also considered and are briefly discussed.

Huffman, G.P.; Shah, N. [Univ. of Kentucky, Lexington, KY (United States); Shelley, M. [Auburn Univ., AL (United States)] [and others

1998-04-01

355

Manufactured gas plant sites: Characterization of wastes and IGT`s innovative remediation alternatives  

SciTech Connect

Manufactured gas plants (MGP)--often referred to as town gas plants--have existed in many parts of the world, including the United States, during the nineteenth and twentieth centuries. Consequently, many of these plants disposed of process wastes and less valuable by-products onsite, contaminated with coal-tar wastes, light oils, naphthalene, etc. Polynuclear aromatic hydrocarbons (PAHs) are components of coal-tar wastes and other wastes that remain at many of these town gas sites. PAH- containing soils, as a result, represent the largest waste type at most MGP sites. Also, certain PAHs are recognized today as being potential animal and/or human carcinogens and, as such, represent an environmental hazard. The Institute of Gas Technology (IGT) has developed and/or evaluated several techniques/processes to improve the biodegradation of PAHs present at MGP sites. As a result of extensive studies, IGT has successfully developed and demonstrated an integrated Chemical/Biological Treatment (CBT) process that is capable of enhancing the rate as well as the extent of PAH degradation. This process combines two complementary as well as powerful remedial techniques: (1) chemical pretreatment using Fenton`s reagent and (2) a biological system using native aerobic microorganisms. This paper presents the general characteristics of MGP sites and wastes and the innovative IGT processes at various stages of development and demonstration. This paper also discusses the IGT/GRI treatability protocol that can be used to determine the potential of bioremediation for any MGP site soil within a 2 to 3-month period.

Srivastava, V.J.

1993-12-31

356

Development of waste minimization and decontamination technologies at the Idaho Chemical Processing Plant  

SciTech Connect

Emphasis on the minimization of decontamination secondary waste has increased because of restrictions on the use of hazardous chemicals and Idaho Chemical Processing Plant (ICPP) waste handling issues. The Lockheed Idaho Technologies Co. (LITCO) Decontamination Development Subunit has worked to evaluate and introduce new performed testing, evaluations, development and on-site demonstrations for a number of novel decontamination techniques that have not yet previously been used at the ICPP. This report will include information on decontamination techniques that have recently been evaluated by the Decontamination Development Subunit.

Ferguson, R.L.; Archibald, K.E.; Demmer, R.L. [and others

1995-11-01

357

PLANNING AND ASSESSMENT MEASURES TO UPDATING RESOURCES RECYCLING EQUIPMENTS IN COLLABORATION WITH SEWAGE TREATMENT PLANTS AND WASTE INCINERATION PLANTS  

NASA Astrophysics Data System (ADS)

This study aims to assess two biomass utilization policies: the integration of food waste treatment in a sewerage treatment plant with an anaerobic digestion tank, and the pruned branch usage as heat source for drying sludge. We focused on two points in our analysis that the impact of the increase of dewatered sludge on sludge treatment processes after digestion and the improvement of the efficiency of waste power generation plants. A developed model was applied to the case study in Kobe city and evaluated the impact until 2030 by four indicators: energy consumption, greenhouse gas (GHG) emission, phosphorus-recovery, and cost. The results showed that case 3-C, which introducing the combined sludge and food waste digestion system, pyrolysis gasification with gas engine and wood-chip boiler, could supply additional 452 TJ/y of energy, recovery 93 t-P/y of phosphorus, and reduce 38 kt-CO2eq./y of GHG while shrinking the cost by 88 million yen/y compared to business as usual types-update case.

Nakakubo, Toyohiko; Tokai, Akihiro; Ohno, Koichi

358

Diversion scenarios in an aqueous reprocessing facility.  

E-print Network

??The International Atomic Energy Agency requires nuclear facilities around the world to abide by heavily enforced safeguards to prevent proliferation. Nuclear fuel reprocessing facilities are… (more)

Calderón, Lindsay Lorraine

2009-01-01

359

Persistence of engineered nanoparticles in a municipal solid-waste incineration plant  

NASA Astrophysics Data System (ADS)

More than 100 million tonnes of municipal solid waste are incinerated worldwide every year. However, little is known about the fate of nanomaterials during incineration, even though the presence of engineered nanoparticles in waste is expected to grow. Here, we show that cerium oxide nanoparticles introduced into a full-scale waste incineration plant bind loosely to solid residues from the combustion process and can be efficiently removed from flue gas using current filter technology. The nanoparticles were introduced either directly onto the waste before incineration or into the gas stream exiting the furnace of an incinerator that processes 200,000 tonnes of waste per year. Nanoparticles that attached to the surface of the solid residues did not become a fixed part of the residues and did not demonstrate any physical or chemical changes. Our observations show that although it is possible to incinerate waste without releasing nanoparticles into the atmosphere, the residues to which they bind eventually end up in landfills or recovered raw materials, confirming that there is a clear environmental need to develop degradable nanoparticles.

Walser, Tobias; Limbach, Ludwig K.; Brogioli, Robert; Erismann, Esther; Flamigni, Luca; Hattendorf, Bodo; Juchli, Markus; Krumeich, Frank; Ludwig, Christian; Prikopsky, Karol; Rossier, Michael; Saner, Dominik; Sigg, Alfred; Hellweg, Stefanie; Günther, Detlef; Stark, Wendelin J.

2012-08-01

360

Modification and expansion of X-7725A Waste Accountability Facility for storage of polychlorinated biphenyl wastes at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio  

SciTech Connect

The US Department of Energy (DOE) must manage wastes containing polychlorinated biphenyls (PCBs) in accordance with Toxic Substances Control Act (TSCA) requirements and as prescribed in a Federal Facilities Compliance Agreement (FFCA) between DOE and the U.S. Environmental Protection Agency (EPA). PCB-containing wastes are currently stored in the PORTS process buildings where they are generated. DOE proposes to modify and expand the Waste Accountability facility (X-7725A) at the Portsmouth Gaseous Diffusion Plant (PORTS), Piketon, Ohio, to provide a central storage location for these wastes. The proposed action is needed to eliminate the fire and safety hazards presented by the wastes. In this EA, DOE considers four alternatives: (1) no action, which requires storing wastes in limited storage areas in existing facilities; (2) modifying and expanding the X-7725A waste accountability facility; (3) constructing a new PCB waste storage building; and (4) shipping PCB wastes to the K-25 TSCA incinerator. If no action is taken, PCB-contaminated would continue to be stored in Bldgs X-326, X-330, and X-333. As TSCA cleanup activities continue, the quantity of stored waste would increase, which would subsequently cause congestion in the three process buildings and increase fire and safety hazards. The preferred alternative is to modify and expand Bldg. X-7725A to store wastes generated by TSCA compliance activities. Construction, which could begin as early as April 1996, would last approximately five to seven months, with a total peak work force of 70.

NONE

1995-11-01

361

Waste Isolation Pilot Plant TruDock crane system analysis  

SciTech Connect

The WIPP TruDock crane system located in the Waste Handling Building was identified in the WIPP Safety Analysis Report (SAR), November 1995, as a potential accident concern due to failures which could result in a dropped load. The objective of this analysis is to evaluate the frequency of failure of the TruDock crane system resulting in a dropped load and subsequent loss of primary containment, i.e. drum failure. The frequency of dropped loads was estimated to be 9.81E-03/year or approximately one every 102 years (or, for the 25% contingency, 7.36E-03/year or approximately one every 136 years). The dominant accident contributor was the failure of the cable/hook assemblies, based on failure data obtained from NUREG-0612, as analyzed by PLG, Inc. The WIPP crane system undergoes a rigorous test and maintenance program, crane operation is discontinued following any abnormality, and the crane operator and load spotter are required to be trained in safe crane operation, therefore it is felt that the WIPP crane performance will exceed the data presented in NUREG-0612 and the estimated failure frequency is felt to be conservative.

Morris, B.C. [Westinghouse Electric Corp., Pittsburgh, PA (United States); Carter, M. [Westinghouse Electric Corp., Carlsbad, NM (United States). Waste Isolation Div.

1996-10-01

362

Metal accumulation strategies in plants spontaneously inhabiting Zn-Pb waste deposits.  

PubMed

Metal (Zn, Pb, Cd, Cu, Ni, Cr) accumulation in shoots of 38 plant species spontaneously colonizing three Zn-Pb waste deposits in southern Poland was studied in order to find out if the age of the waste (30-130 years) or its type (slag or flotation residues) influence metal content in plants and to identify species potentially suitable for biomonitoring and phytoremediation. The total metal concentrations in the waste upper layers ranged from 7300 to 171,790 mg kg(-1) for Zn, from 1390 to 22,265 mg kg(-1) for Pb, and from 66 to 1,464 mg kg(-1) for Cd, whereas CaCl2-extracted fractions accounted for 0.034-0.11 %, 0.005-0.03 %, and 0.28-0.62 % of total Zn, Pb and Cd concentrations, respectively. The concentrations of Cu, Ni, and Cr in substrates and in plants were low and ranged within the background values. Metal accumulation in plant shoots was poorly correlated with both total and CaCl2-extracted forms of metals in the substrate and was highly variable among species and also specimens of the same species. The highest mean concentrations of Zn, Pb and Cd were found in Anthyllis vulneraria L. (901.5 mg kg(-1)), Echium vulgare L. (116.92 mg kg(-1)), and Hieracium piloselloides Vill. (26.86 mg kg(-1)), respectively. Besides Reseda lutea L., no species appeared to be a good indicator of polymetallic environment pollution based on chemical analysis of shoots; however, metal accumulation in the whole plant communities of a particular contaminated area might be an accurate tool for assessment of metal transfer to vegetation irrespective of the type or age of the waste. All the species studied developed a metal exclusion strategy, thus exhibiting potential for phytostabilization of metalliferous wastelands. PMID:24793328

Wójcik, Ma?gorzata; Sugier, Piotr; Siebielec, Grzegorz

2014-07-15

363

Biofiltration treatment of odors from municipal solid waste treatment plants.  

PubMed

An in situ compost biofilter was established for the treatment of odors from biostabilization processing of municipal solid waste. The concentrations of total volatile organic compounds (VOCs) in odors and their components were measured. Biofilter media was characterized in terms of total carbon (TC), total nitrogen (TN), total phosphorus (TP), organic matter (OM), pH value and determination of bacterial colony structure. Gas chromatography-mass spectrometry (GC-MS) analysis showed that the main components of the produced gas were benzene, toluene, ethylbenzene and xylene (BTEX) along with other alkanes, alkenes, terpenes, and sulphur compounds. The compost biofilter had remarkable removal ability for alkylated benzenes (>80%), but poor removal for terpenes ( approximately 30%). Total VOC concentrations in odors during the biostabilization process period ranged from 0.7 to 87 ppmv, and the VOC removal efficiency of the biofilter varied from 20% to 95%. After about 140 days operation, TN, TC, TP and OM in compost were kept almost stable, but the dissolved N, NH(4)-N and NO(3)-N experienced an increase of 44.5%, 56.2% and 76.3%, respectively. Dissolved P decreased by 27.3%. The pH value experienced an increase in the early period and finally varied from 7.38 to 8.08. Results of bacterial colony in packing material indicated that bacteria and mold colony counts increased, but yeasts and actinomyces decreased along with biofilter operation, which were respectively, 3.7, 3.4, 0.04 and 0.07 times of their initial values. PMID:19282165

Liu, Qiang; Li, Mi; Chen, Rong; Li, Zhengyue; Qian, Guangren; An, Taicheng; Fu, Jiamo; Sheng, Guoying

2009-07-01

364

Enhanced biodegradation of polyaromatic hydrocarbons in manufactured gas plant wastes  

SciTech Connect

Scientists at the Institute of Gas Technology (IGT) have focused on enhancing destruction of polyaromatic hydrocarbons (PAHs) present as pollutants in manufactured gas plant (MGP) soils. The factor that bears the most restrictive influence on successful biological PAH degradation is low pollutant transfer from soil into an aqueous environment where biotreatment processes can take place. Physical and chemical enhancements were used in conjunction with biological processes. Physical enhancements overcame the mass transfer problem and made possible the biological destruction of aromatic hydrocarbons. One- to three-ring aromatic hydrocarbons were readily biodegraded in liquid, soil slurry, and -- to a lesser degree -- composted soil systems. Four- to six-ring PAHs remained persistent but were effectively destroyed when chemical co-treatments were used. Combined biological/chemical/physical processes are currently being tested to achieve the most extensive PAH degradation possible for MGP soils. 8 refs., 9 figs., 2 tabs.

Gauger, W.K.; Srivastava, V.J. (Institute of Gas Technology, Chicago, IL (United States)); Hayes, T.D.; Linz, D.G. (Gas Research Inst., Chicago, IL (United States))

1990-01-01

365

Power recovery from waste heat in modern turboexpander plants  

SciTech Connect

The object of this study is to determine the feasibility and cost of installing a power recovery system in an existing gas processing plant. The power generated by the system is to be used to drive a residue gas compressor, a refrigeration compressor and the heat medium circulating pump, each having its own expander driver. For this purpose the heat from the exhaust of a number of gas turbines is to be combined to provide a total 75 MM Btu/hr. heat energy. Because of safety reasons, Freon 12 has been chosen for the working fluid. The condensing media is water at a design temperature of 80 degrees F. The process conditions for the cycle and the duties of the major equipments are described.

Mafi, S.; Drake, C.

1981-01-01

366

Demonstration of the TRUEX process for the treatment of actual high activity tank waste at the INEEL using centrifugal contactors  

SciTech Connect

The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering and Environmental Laboratory (INEEL), formerly reprocessed spent nuclear fuel to recover fissionable uranium. The radioactive raffinates from the solvent extraction uranium recovery processes were converted to granular solids (calcine) in a high temperature fluidized bed. A secondary liquid waste stream was generated during the course of reprocessing, primarily from equipment decontamination between campaigns and solvent wash activities. This acidic tank waste cannot be directly calcined due to the high sodium content and has historically been blended with reprocessing raffinates or non-radioactive aluminum nitrate prior to calcination. Fuel reprocessing activities are no longer being performed at the ICPP, thereby eliminating the option of waste blending to deplete the waste inventory. Currently, approximately 5.7 million liters of high-activity waste are temporarily stored at the ICPP in large underground stainless-steel tanks. The United States Environmental Protection Agency and the Idaho Department of Health and Welfare filed a Notice of Noncompliance in 1992 contending some of the underground waste storage tanks do not meet secondary containment. As part of a 1995 agreement between the State of Idaho, the Department of Energy, and the Department of Navy, the waste must be removed from the tanks by 2012. Treatment of the tank waste inventories by partitioning the radionuclides and immobilizing the resulting high-activity and low-activity waste streams is currently under evaluation. A recent peer review identified the most promising radionuclide separation technologies for evaluation. The Transuranic Extraction-(TRUEX) process was identified as a primary candidate for separation of the actinides from ICPP tank waste.

Law, J.D.; Brewer, K.N.; Todd, T.A.; Olson, L.G.

1997-10-01

367

Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect

The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report.

Bradley, E.W. [Science Applications International Corp., Oak Ridge, TN (United States); Wu, C.F.; Goff, T.E. [Westinghouse Electric Corp., Carlsbad, NM (United States). Waste Isolation Div.

1993-12-31

368

Environmental management assessment of the Waste Isolation Pilot Plant (WIPP), Carlsbad, New Mexico  

SciTech Connect

This document contains the results of the Environmental Management Assessment of the Waste Isolation Pilot Plant (WIPP). This Assessment was conducted by EH-24 from July 19 through July 30, 1993 to advise the Secretary of Energy of the adequacy of management systems established at WIPP to ensure the protection of the environment and compliance with Federal, state, and DOE environmental requirements. The mission of WIPP is to demonstrate the safe disposal of transuranic (TRU) waste. During this assessment, activities and records were reviewed and interviews were conducted with personnel from the management and operating contractors. This assessment revealed that WIPP`s environmental safety and health programs are satisfactory, and that all levels of the Waste Isolation Division (WID) management and staff consistently exhibit a high level of commitment to achieve environmental excellence.

Not Available

1993-07-01

369

Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 2, Chapter C, Appendix C1--Chapter C, Appendix C3 (beginning), Revision 3  

SciTech Connect

This volume contains appendices for the following: Rocky Flats Plant and Idaho National Engineering Laboratory waste process information; TRUPACT-II content codes (TRUCON); TRUPACT-II chemical list; chemical compatibility analysis for Rocky Flats Plant waste forms; chemical compatibility analysis for waste forms across all sites; TRU mixed waste characterization database; hazardous constituents of Rocky Flats Transuranic waste; summary of waste components in TRU waste sampling program at INEL; TRU waste sampling program; and waste analysis data.

Not Available

1993-03-01

370

Concept for dismantling the Hllw treatment facility on the Former Wak Reprocessing Site  

SciTech Connect

The German pilot reprocessing plant WAK was operated until 1990 and processed about 200 tons of nuclear fuels from test and power reactors. In late 1991, the Federal Republic of Germany, the State of Baden-Wuerttemberg, and the utilities decided to shut down the WAK and to dismantle it completely to the green field. In the years 2000/2001, remote-controlled dismantling of the process cells in the reprocessing building was completed. Part of the building has already been subjected to release measurement and released from the obligations under the German Atomic Energy Act. However, a major prerequisite for the complete dismantling of the WAK is the management of the 60 m{sup 3} high-level liquid waste (HLLW) with an activity of 8.0 E 17 Bq resulting from reprocessing. For this purpose, the Karlsruhe vitrification plant (VEK) was constructed and is now under commissioning /1/. Hot operation is foreseen for the years 2007/2008. Following vitrification operation, dismantling of the four HLLW tanks in the storage building will be a particularly challenging task in terms of radiology. The HLLW tanks are located in thick-walled concrete cells that require remote- controlled horizontal access. For this purpose, a new access building, the southern extension, was built. It serves to bring in and operate the remote handling tools and allows for the contamination-safe removal and measurement of the MAW drums. In contrast to the crane in the process building, the manipulator carrier system used here is an 8 Mg excavator. All tools, including the wall cutter, chisel, cutting disk, scissors, and the electric master-slave manipulator (EMSM), can be docked to this excavator. The VEK installations shall be dismantled parallel to the HLLW storage tanks. Due to the dose rates expected after operation, two dismantling areas have to be distinguished in the VEK: The core area with the HLLW transfer cell, melter cell, and exhaust gas cell requires remote dismantling. All remaining cells and rooms may presumably be dismantled manually. (authors)

Birringer, K.J.; Fleisch, J.; Graffunder, I.; Pfeifer, W. [Wiederaufarbeitungsanlage Karlsruhe, Ruckbau- und Entsorgungs- GmbH, Eggenstein-Leopoldshafen (Germany)

2007-07-01

371

Synthesis of biomass and utilization of plants wastes in a physical model of biological life-support system.  

PubMed

The paper considers problems of biosynthesis of higher plants' biomass and "biological incineration" of plant wastes in a working physical model of biological LSS. The plant wastes are "biologically incinerated" in a special heterotrophic block involving Californian worms, mushrooms and straw. The block processes plant wastes (straw, haulms) to produce soil-like substrate (SLS) on which plants (wheat, radish) are grown. Gas exchange in such a system consists of respiratory gas exchange of SLS and photosynthesis and respiration of plants. Specifics of gas exchange dynamics of high plants--SLS complex has been considered. Relationship between such a gas exchange and PAR irradiance and age of plants has been established. Nitrogen and iron were found to the first to limit plants' growth on SLS when process conditions are deranged. The SLS microflora has been found to have different kinds of ammonifying and denitrifying bacteria which is indicative of intensive transformation of nitrogen-containing compounds. The number of physiological groups of microorganisms in SLS was, on the whole, steady. As a result, organic substances--products of exchange of plants and microorganisms were not accumulated in the medium, but mineralized and assimilated by the biocenosis. Experiments showed that the developed model of a man-made ecosystem realized complete utilization of plant wastes and involved them into the intrasystem turnover. PMID:14649254

Tikhomirov, A A; Ushakova, S A; Manukovsky, N S; Lisovsky, G M; Kudenko, Yu A; Kovalev, V S; Gribovskaya, I V; Tirrannen, L S; Zolotukhin, I G; Gros, J B; Lasseur, Ch

2003-01-01

372

Synthesis of biomass and utilization of plants wastes in a physical model of biological life-support system  

NASA Astrophysics Data System (ADS)

The paper considers problems of biosynthesis of higher plants' biomass and "biological incineration" of plant wastes in a working physical model of biological LSS. The plant wastes are "biologically incinerated" in a special heterotrophic block involving Californian worms, mushrooms and straw. The block processes plant wastes (straw, haulms) to produce soil-like substrate (SLS) on which plants (wheat, radish) are grown. Gas exchange in such a system consists of respiratory gas exchange of SLS and photosynthesis and respiration of plants. Specifics of gas exchange dynamics of high plants — SLS complex has been considered. Relationship between such a gas exchange and PAR irradiance and age of plants has been established. Nitrogen and iron were found to the first to limit plants' growth on SLS when process conditions are deranged. The SLS microflora has been found to have different kinds of ammonifying and denitrifying bacteria which is indicative of intensive transformation of nitrogen-containing compounds. The number of physiological groups of microorganisms in SLS was, on the whole, steady. As a result, organic substances — products of exchange of plants and microorganisms were not accumulated in the medium, but mineralized and assimilated by the biocenosis. Experiments showed that the developed model of a man-made ecosystem realized complete utilization of plant wastes and involved them into the intrasystem turnover.

Tikhomirov, A. A.; Ushakova, S. A.; Manukovsky, N. S.; Lisovsky, G. M.; Kudenko, Yu. A.; Kovalev, V. S.; Gribovskaya, I. V.; Tirranen, L. S.; Zolotukhin, I. G.; Gros, J. B.; Lasseur, Ch.

2003-08-01

373

Method of recovering boric acid from waste water concentrates of nuclear plants  

SciTech Connect

A waste water concentrate containing boric acid together with chemical residues and radionuclides, especially from a nuclear power plant, is treated to recovering boric acid which can be recycled to the plant. According to the invention, the practically neutral solution is acidified with an acid selected from the group which consists of sulfuric acid, hydrochloric acid, nitric acid and acetic acid to precipitate the boric acid which is separated from the concentrate and subjected to at least one recrystallization step. The boric acid thus obtained is of comparatively high purity.

Schroeder, H.J.; Ambros, R.; Brenner, N.; Paffrath, G.

1984-03-06

374

Expert judgement on inadvertent human intrusion into the Waste Isolation Pilot Plant  

Microsoft Academic Search

Four expert-judgment teams have developed analyses delineating possible future societies in the next 10,000 years in the vicinity of the Waste Isolation Pilot Plant (WIPP). Expert-judgment analysis was used to address the question of future societies because neither experimentation, observation, nor modeling can resolve such uncertainties. Each of the four, four-member teams, comprised of individuals with expertise in the physical,

S. C. Hora; D. von Winterfeldt; K. M. Trauth

1991-01-01

375

Technical letter report: Submerged bed scrubber sediment resuspension testing for the Hanford Waste Vitrification Plant  

Microsoft Academic Search

During-vitrification operations in the Hanford Waste Vitrification Plant (HWVP), some feed components will be vented from the melter to the melter offgas cleaning equipment. The current HWVP reference process for melter off.-gas treatment includes a submerged bed scrubber (SBS) to provide the first stage of off-gas scrubbing and quenching. During most melter\\/off-gas test runs at Pacific Northwest Laboratory (PNL) with

A. J. Schmidt; M. G. Herrington

1996-01-01

376

Metal Tolerant Mycorrhizal Plants: A Review from the Perspective on Industrial Waste in Temperate Region  

Microsoft Academic Search

\\u000a The chapter summarizes research carried out on the role of mycorrhizal fungi in phytoremediation of heavy-metal-rich wastes\\u000a in temperate regions. Symbiotic fungi are an important component of soil microbiota, especially under harsh conditions. Properly\\u000a developed mutual symbiosis enhances the survival of plants in polluted areas by improving nutrient acquisition and water relations.\\u000a In addition, mycorrhizal fungi were found to play

Katarzyna Turnau; Przemys?aw Ryszka; Grzegorz Wojtczak

377

Data used in preliminary performance assessment of the Waste Isolation Pilot Plant (1990)  

SciTech Connect

This report documents the data available as of August 1990 and used by the Performance Assessment Division of Sandia National Laboratories in its December 1990 preliminary performance assessment of the Waste Isolation Pilot Plant (WIPP). Parameter values are presented in table form for the geologic subsystem, engineered barriers, borehole flow properties, climate variability, and intrusion characteristics. Sources for the data and a brief discussion of each parameter are provided. 101 refs., 72 figs., 21 tabs.

Rechard, R.P (Sandia National Labs., Albuquerque, NM (USA)); Luzzolino, H. (Geo-Centers, Inc., Albuquerque, NM (USA)); Sandha, J.S. (Science Applications International Corp., Albuquerque, NM (USA))

1990-12-01

378

Transport of waste heat from a nuclear power plant into coastal water  

Microsoft Academic Search

A numerical and experimental modeling is presented for studying the transport of waste heat from a nuclear power plant into coastal water by using a full-field physical model with scale distortion, a local physical model with normal scale and a depth-averaged k?? turbulence model with a modified second-order upwind scheme. Field investigations are also used to provide the calibration and

Ping Zeng; Huiquan Chen; Baichuan Ao; Ping Ji; Xiaojian Wang; Zhiliang Ou

2002-01-01

379

Purification of crude glycerol derived from waste used-oil methyl ester plant  

Microsoft Academic Search

The purification of crude glycerol from a biodiesel plant using waste used-oil as a raw material was carried out on a laboratory\\u000a scale by using the combined chemical and physical treatments based upon repeated cycles of acidification to the desired pH\\u000a within the range of 1–6 using 1.19 M H2SO4, allowing phase separation and harvesting of the glycerol-rich middle phase

Sangkorn Kongjao; Somsak Damronglerd; Mali Hunsom

2010-01-01

380

Improvements in dioxin abatement strategies at a municipal waste management plant in Barcelona  

Microsoft Academic Search

This study presents the results of a dioxin abatement programme undertaken in the municipal waste incineration plant of Montcada i Reixac (Barcelona, Spain) after the replacement of an obsolete air cleaning device by a new flue gas treatment system. A number of sampling campaigns were conducted with the aim of characterising stack gas emission levels of polychlorinated dibenzo-p-dioxins (PCDDs)\\/polychlorinated dibenzofurans

Esteban Abad; Josep Caixach; Josep Rivera

2003-01-01

381

Rooting depths of plants on low-level waste disposal sites  

Microsoft Academic Search

In 1981-1982 an extensive bibliographic study was done to reference rooting depths of native plants in the United States. The data base presently contains 1034 different rooting citations with approximately 12,000 data elements. For this report, data were analyzed for rooting depths related to species found on low-level waste (LLW) sites at Los Alamos National Laboratory. Average rooting depth and

T. S. Foxx; G. D. Tierney; J. M. Williams

1984-01-01

382

Recombination of hydrogen and oxygen in the technical gaseous waste of nuclear power plants  

Microsoft Academic Search

The recombination of hydrogen and oxygen in technical gaseous waste of nuclear power plants in enlarged scale experiment has\\u000a been studied on the basis of our previous work.1 The catalyst and its best operating conditions for recombination of hydrogen and oxygen determined in a small scale experiment\\u000a were demonstrated and tested. The results show that the data obtained in an

A. D. He; M. L. Ye; Z. H. Tang; S. J. Lu; Y. Z. Gu; X. G. Fan; L. Zhao; J. B. Gao

1998-01-01

383

Metal uptake by native plants and revegetation potential of mining sulfide-rich waste-dumps.  

PubMed

Waste dumps resulting from metal exploitation create serious environmental damage, providing soil and water degradation over long distances. Phytostabilization can be used to remediate these mining sites. The present study aims to evaluate the behavior of selected plant species (Erica arborea, Ulex europaeus, Agrostis delicatula, and Cytisus multiflorus) that grow spontaneously in three sulfide-rich waste-dumps (Lapa Grande, Cerdeirinha, and Penedono, Portugal). These sites represent different geological, climatic and floristic settings. The results indicate distinctive levels and types of metal contamination: Penedono presents highest sulfate and metal contents, especially As, with low levels of Fe. In contrast, at Lapa Grande and Cerdeirinha Fe, Mn, and Zn are the dominant metals. In accordance, each waste dump develops a typical plant community, providing a specific vegetation inventory. At Penedono, Agrostis delicatula accumulates As, Pb, Cu, Mn, and Zn, showing higher bioaccumulation factors (BF) for Mn (32.1) and As (24.4). At Cerdeirinha, Ulex europaeus has the highest BF for Pb (984), while at Lapa Grande, Erica arborea presents high BF for Mn (9.8) and Pb (8.1). Regarding TF, low values were obtained for most of the metals, especially As (TF < 1). Therefore, the results obtained from representative plant species suggest appropriate behavior for phytostabilization measures. PMID:24933904

Gomes, Patrícia; Valente, Teresa; Pamplona, Jorge; Braga, Maria Amália Sequeira; Pissarra, José; Gil, José António Grande; de la Torre, Maria Luisa

2014-01-01

384

Leaching characteristics of paraffin waste forms generated from Korean nuclear power plants.  

PubMed

Leaching tests of paraffin waste forms including boric acid, cobalt, strontium and cesium were performed to investigate the leaching characteristics of paraffin waste forms which had been generated in Korean nuclear power plants. The leaching tests were conducted according to ANSI/ANS-16.1 test procedure and the cumulative fractions leached (CFLs) of boric acid, cobalt, strontium and cesium were obtained. The compressive strength before and after the leaching test was measured for various waste forms with different mixing ratios of boric acid to paraffin. It was observed that boric acid and other nuclides immobilized within paraffin waste forms were congruently released and the leaching rates were influenced by reacted layer depth as the dissolution reaction progressed. A shrinking core model based on the diffusion-controlled dissolution kinetics was developed in order to simulate the test results. The CFLs and the leaching rates were well expressed by the shrinking core model and the cross-sectional view of specimen after the test demonstrated the applicability of this model with the shrinking dissolution front to the leaching analysis of paraffin waste forms. PMID:11300532

Kim, J Y; Kim, C L; Chung, C H

2001-01-01

385

Ceramic process and plant design for high-level nuclear waste immobilization  

SciTech Connect

In the last 3 years, significant advances in ceramic technology for high-level nuclear waste solidification have been made. Product quality in terms of leach-resistance, compositional uniformity, structural integrity, and thermal stability promises to be superior to borosilicate glass. This paper addresses the process effectiveness and preliminary designs for glass and ceramic immobilization plants. The reference two-step ceramic process utilizes fluid-bed calcination (FBC) and hot isostatic press (HIP) consolidation. Full-scale demonstration of these well-developed processing steps has been established at DOE and/or commercial facilities for processing radioactive materials. Based on Savannah River-type waste, our model predicts that the capital and operating cost for the solidification of high-level nuclear waste is about the same for the ceramic and glass options. However, when repository costs are included, the ceramic option potentially offers significantly better economics due to its high waste loading and volume reduction. Volume reduction impacts several figures of merit in addition to cost such as system logistics, storage, transportation, and risk. The study concludes that the ceramic product/process has many potential advantages, and rapid deployment of the technology could be realized due to full-scale demonstrations of FBC and HIP technology in radioactive environments. Based on our finding and those of others, the ceramic innovation not only offers a viable backup to the glass reference process but promises to be a viable future option for new high-level nuclear waste management opportunities.

Grantham, L.F.; McKisson, R.L.; De Wames, R.E.; Guon, J.; Flintoff, J.F.; McKenzie, D.E.

1983-01-01

386

Refinery Waste Heat Ammonia Absorption Refrigeration Plant (WHAARP) Recovers LPG's and Gasoline, Saves Energy, and Reduces Air Pollution  

E-print Network

A first-of-its-kind Waste Heat Ammonia Absorption Refrigeration Plant (WHAARP™) was installed by Planetec Utility Services Co., Inc. in partnership with Energy Concepts Co. at Ultramar Diamond Shamrock's 30,000 barrel per day refinery in Denver...

Brant, B.; Brueske, S.; Erickson, D.; Papar, R.

387

FULL-SCALE FIELD EVALUATION OF WASTE DISPOSAL FROM COAL-FIRED ELECTRIC GENERATING PLANTS. VOLUME 5. APPENDIX F  

EPA Science Inventory

The six-volume report summarizes results of a 3-year study of current coal ash and flue gas desulfurization (FGD) waste disposal practices at coal-fired electric generating plants. The study involved characterization of wastes, environmental data gathering, evaluation of environm...

388

Heat recovery from waste water by energy-saving heat pump systems in connection with water treatment plants  

Microsoft Academic Search

The advantages of waste water recovery as an energy source were investigated. It was found that heat pump systems reach the highest performance coefficients and their primary energy ratios are competitive with conventional heating systems. It is concluded that the utilization of waste water treatment plants by large heat pump systems provides a considerable annual energy saving of light oil.

U. Wiedmann; R. Flohrschuetz

1980-01-01

389

ASSESSMENT OF BACTERIA AND VIRUS EMISSIONS AT A REFUSE DERIVED FUEL PLANT AND OTHER WASTE HANDLING FACILITIES  

EPA Science Inventory

The report is an executive summary of results of a program to compare relative levels of selected airborne bacteria and viruses within and around various waste handling facilities. Facilities included were an incinerator, a waste transfer station, a wastewater treatment plant, a ...

390

Lanthanides extraction processes in molten fluoride media: Application to nuclear spent fuel reprocessing  

Microsoft Academic Search

This paper describes four techniques of extraction of lanthanide (Ln) elements from molten salts in the general frame of reprocessing nuclear wastes; one of them is chemical: the precipitation of Ln ions in insoluble compounds (oxides or oxyfluorides); the others use electrochemical methodology in molten fluorides for extraction and measurement of the progress of the processes: first electrodeposition of pure

P. Taxil; L. Massot; C. Nourry; M. Gibilaro; P. Chamelot; L. Cassayre

2009-01-01

391

Evaluation of New Corrosion-Resistant Superheater Tubing in High-Efficiency Waste-to-Energy Plants  

Microsoft Academic Search

Field corrosion tests were conducted on eight single tube materials and two welded overlay materials in three typical Japanese waste incineration plants in an effort to develop new corrosion-resistant superheater tubes capable of functioning efficiently under temperature and pressure conditions of 500 C and 100 kgf\\/cm²-g in high-efficiency waste-to-energy (WTE) plants. Austenitic alloys containing higher concentrations of chromium, nickel, and

Y. Kawahara; H. Tsuboi; K. Yukawa; M. Nakamura

1998-01-01

392

Waste Treatment Plant Support Program: Summaries of Reports Produced During Fiscal Years 1999-2010  

SciTech Connect

The Waste Treatment Plant (WTP) being built on the U.S. Department of Energy (DOE) Hanford Site will be the largest chemical processing plant in the United States. Bechtel National Inc. (BNI) is the designer and constructor for the WTP. The Pacific Northwest National Laboratory (PNNL) has provided significant research and testing support to the WTP. This report provides a summary of reports developed initially under PNNL’s “1831” use agreement and later PNNL’s “1830” prime contract with DOE in support of the WTP. In March 2001, PNNL under its “1831” use agreement entered into a contract with BNI to support their research and testing activities. However, PNNL support to the WTP predates BNI involvement. Prior to March 2001, PNNL supported British Nuclear Fuels Ltd. in its role as overall designer and constructor. In February 2007, execution of PNNL’s support to the WTP was moved under its “1830” prime contract with DOE. Documents numbered “PNWD-XXXX” were issued under PNNL’s “1831” use agreement. Documents numbered “PNNL-XXXX” were issued under PNNL’s “1830” prime contract with DOE. The documents are sorted by fiscal year and categorized as follows: ? Characterization ? HLW (High Level Waste) ? Material Characterization ? Pretreatment ? Simulant Development ? Vitrification ? Waste Form Qualification. This report is intended to provide a compendium of reports issued by PNWD/PNNL in support of the Waste Treatment Plant. Copies of all reports can be obtained by clicking on http://www.pnl.gov/rpp-wtp/ and downloading the .pdf file(s) to your computer.

Beeman, Gordon H.

2010-08-12

393

Evolution of enzymatic activities and carbon fractions throughout composting of plant waste.  

PubMed

Many alternatives for the proper disposal of horticultural plant wastes have been studied, and composting is one of the most attractive due to its insignificant environmental impact and low cost. The quality of compost for agronomical use is related to the degree of organic matter maturation and stabilization. Traditional parameters as well as temperature, ratio C/N, cationic exchange capacity, extractable carbon, or evolution of humificated substances have been successfully used to assess compost maturity and stability. However, microorganisms frequently isolated during composting release a wide range of hydrolytic enzymes, whose activity could apparently give interesting information on the rate of decomposition of organic matter and, therefore, on the product stability. The aim of this work was to study the evolution of some important enzymatic activities during composting of agricultural wastes and their comparison with other chemical parameters commonly employed as quality and maturity indexes, to establish a relationship between the degradation intensity of specific organic carbon fractions throughout the process. In this work, the chemical and biochemical parameters of plant wastes were studied along a composting process of 189 days to evaluate their importance as tools for compost characterization. Results showed an intense enzymatic activity during the first 2-3 weeks of composting (bio-oxidative phase), because of the availability of easily decomposable organic compounds. From a biological point of view, a less intense phase was observed between second and third month of composting (mesophilic or cooling phase). Finally, chemical humification parameters were more closely associated with the period between 119 and 189 days (maturation phase). Significant correlations between the enzymatic activities as well as between enzyme activities and other more traditional parameters were also highlighted, indicating that both kind of indexes can be a reliable tool to determine the degree of stability and maturation of horticultural plant wastes based-compost. PMID:24412984

Jurado, M M; Suárez-Estrella, F; Vargas-García, M C; López, M J; López-González, J A; Moreno, J

2014-01-15

394

Lessons Learned from Characterization, Performance Assessment, and EPA Regulatory Review of the 1996 Actinide Source Term for the Waste Isolation Pilot Plant  

Microsoft Academic Search

The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy (DOE) facility for the permanent disposal of transuranic waste from defense activities. In 1996, the DOE submitted the Title 40 CFR Part 191 Compliance Certification Application for the Waste Isolation Pilot Plant (CCA) to the US Environmental Protection Agency (EPA). The CCA included a probabilistic performance assessment (PA)

K. W. Larson; R. C. Moore; E. J. Nowak; H. W. Papenguth; H. Jow

1999-01-01

395

Optimising energy recovery and use of chemicals, resources and materials in modern waste-to-energy plants.  

PubMed

Due to ongoing developments in the EU waste policy, Waste-to-Energy (WtE) plants are to be optimized beyond current acceptance levels. In this paper, a non-exhaustive overview of advanced technical improvements is presented and illustrated with facts and figures from state-of-the-art combustion plants for municipal solid waste (MSW). Some of the data included originate from regular WtE plant operation - before and after optimisation - as well as from defined plant-scale research. Aspects of energy efficiency and (re-)use of chemicals, resources and materials are discussed and support, in light of best available techniques (BAT), the idea that WtE plant performance still can be improved significantly, without direct need for expensive techniques, tools or re-design. In first instance, diagnostic skills and a thorough understanding of processes and operations allow for reclaiming the silent optimisation potential. PMID:23810322

De Greef, J; Villani, K; Goethals, J; Van Belle, H; Van Caneghem, J; Vandecasteele, C

2013-11-01

396

Plutonium Finishing Plant Treatment and Storage Unit Dangerous Waste Training Plan  

SciTech Connect

The training program for personnel performing waste management duties pertaining to the Plutonium Finishing Plant (PFP) Treatment and Storage Unit is governed by the general requirements established in the Plutonium Finishing Plant Dangerous Waste Training Plan (PFP DWTP). The PFP Treatment and Storage Unit DWTP presented below incorporates all of the components of the PFP DWTP by reference. The discussion presented in this document identifies aspects of the training program specific to the PFP Treatment and Storage Unit. The training program includes specifications for personnel instruction through both classroom and on-the-job training. Training is developed specific to waste management duties. Hanford Facility personnel directly involved with the PFP Treatment and Storage Unit will receive training to container management practices, spill response, and emergency response. These will include, for example, training in the cementation process and training pertaining to applicable elements of WAC 173-303-330(1)(d). Applicable elements from WAC 173-303-330(1)(d) for the PFP Treatment and Storage Unit include: procedures for inspecting, repairing, and replacing facility emergency and monitoring equipment; communications and alarm systems; response to fires or explosions; and shutdown of operations.

ENTROP, G.E.

2000-06-27

397

Waste-assimilation study of Koshkonong Creek below sewage-treatment plant at Sun Prairie, Wisconsin  

USGS Publications Warehouse

A waste-load-assimilation study of a reach of Koshkonong Creek below the Sun Prairie, Wisconsin, sewage-treatment-plant outfall indicated that a high level of treatment would be required to meet Wisconsin water-quality standards. To maintain a minimum dissolved-oxygen concentration of 5 mg/liter during the critical summer low-flow period, 5-day carbonaceous biochemical-oxygen demand in waste discharges should not exceed 5 mg/liter and ammonium nitrogen should not exceed 1.5 mg/liter. Advanced treatment with denitrification is required because stream-reaeration coefficients are not high enough to offset deoxygenation caused by an abundance of attached biological slimes. The slimes apparently consumed dissolved oxygen at a rate of about 110 mg/liter per day at the time of the stream survey. During the critical summer low-flow period, natural stream discharge is very small compared to waste-water discharge , so benefits of dilution are insignificant. An evaluation of two proposed alternative waste-water discharge sites indicated that the present discharge site is hydraulically superior to these sites. Stream-reaeration coefficients used in the study were based on measurements using the radioactive-tracer method. (Woodard-USGS)

Grant, R. Stephen

1976-01-01

398

Citizens guide to the Waste Isolation Pilot Plant Compliance Certification Application to the EPA  

SciTech Connect

The US Department of Energy (DOE) has submitted an application to the US Environmental Protection Agency (EPA) for a certificate showing that the Waste Isolation Pilot Plant (WIPP) complies with strict environmental regulations designed to safeguard humans and the environment for at least 10,000 years. Congress gave the EPA authority to regulate the WIPP site for disposal of transuranic waste under the 1992 WIPP Land Withdrawal Act. The EPA has one year to review the Compliance Certification Application (CCA) before determining whether the DOE has successfully documented the WIPP`s compliance with federal environmental standards. The application presents the conclusions of more than 20 years of scientific and engineering work specifically dedicated to disposal of transuranic waste at the WIPP. The application thoroughly documents how the natural characteristics of the WIPP site, along with engineered features, comply with the regulations. In the application, the DOE responds fully to the federal standards and to the EPA`s certification criteria. This Citizens` Guide provides an overview of the CCA and its role in moving toward final disposal of transuranic waste.

NONE

1996-11-01

399

Status of Waste Isolation Pilot Plant compliance with 40 CFR 191B, December 1992  

SciTech Connect

Before disposing of transuranic radioactive waste at the Waste Isolation Pilot Plant (WIPP), the US Department of Energy (DOE) must evaluate compliance with long-term regulations of the US Environmental Protection Agency (EPA). Sandia National Laboratories (SNL) is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for final compliance evaluations. This paper describes the 1992 preliminary comparison with Subpart B of the Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191), which regulates long-term releases of radioactive waste. Results of the 1992 PA are preliminary, and cannot be used to determine compliance or noncompliance with EPA regulations because portions of the modeling system and data base are incomplete. Results are consistent, however, with those of previous iterations of PA, and the SNL WIPP PA Department has high confidence that compliance with 40 CFR 191B can be demonstrated. Comparison of predicted radiation doses from the disposal system also gives high confidence that the disposal system is safe for long-term isolation.

Marietta, M.G.; Anderson, D.R.

1993-10-01

400

Recent Improvements In Interface Management For Hanfords Waste Treatment And Immobilization Plant - 13263  

SciTech Connect

The U.S. Department of Energy (DOE), Office of River Protection (ORP) is responsible for management and completion of the River Protection Project (RPP) mission, which comprises both the Hanford Site tank farms operations and the Waste Treatment and Immobilization Plant (WTP). The RPP mission is to store, retrieve and treat Hanford's tank waste; store and dispose of treated wastes; and close the tank farm waste management areas and treatment facilities by 2047. The WTP is currently being designed and constructed by Bechtel National Inc. (BNI) for DOE-ORP. BNI relies on a number oftechnical services from other Hanford contractors for WTP's construction and commissioning. These same services will be required of the future WTP operations contractor. The WTP interface management process has recently been improved through changes in organization and technical issue management documented in an Interface Management Plan. Ten of the thirteen active WTP Interface Control Documents (ICDs) have been revised in 2012 using the improved process with the remaining three in progress. The value of the process improvements is reflected by the ability to issue these documents on schedule.

Arm, Stuart T. [Washington River Protection Solutions, Richland, WA (United States); Pell, Michael J. [Bechtel National, Inc., Richland, WA (United States); Van Meighem, Jeffery S. [Washington River Protection Solutions, Richland, WA (United States); Duncan, Garth M. [Bechtel National, Inc., Richland, WA (United States); Harrington, Christopher C. [Department of Energy, Office of River Protection, Richland, Washington (United States)

2012-11-20

401

Materials selection for process equipment in the Hanford waste vitrification plant  

SciTech Connect

The Hanford Waste Vitrification Plant (HWVP) is being designed to vitrify defense liquid high-level wastes and transuranic wastes stored at Hanford. The HWVP Functional Design Criteria (FDC) requires that materials used for fabrication of remote process equipment and piping in the facility be compatible with the expected waste stream compositions and process conditions. To satisfy FDC requirements, corrosion-resistant materials have been evaluated under simulated HWVP-specific conditions and recommendations have been made for HWVP applications. The materials recommendations provide to the project architect/engineer the best available corrosion rate information for the materials under the expected HWVP process conditions. Existing data and sound engineering judgement must be used and a solid technical basis must be developed to define an approach to selecting suitable construction materials for the HWVP. This report contains the strategy, approach, criteria, and technical basis developed for selecting materials of construction. Based on materials testing specific to HWVP and on related outside testing, this report recommends for constructing specific process equipment and identifies future testing needs to complete verification of the performance of the selected materials. 30 refs., 7 figs., 11 tabs.

Elmore, M R; Jensen, G A

1991-07-01

402

Performance assessment in support of the 1996 compliance certification application for the Waste Isolation Pilot Plant.  

PubMed

The conceptual and computational structure of a performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) is described. Important parts of this structure are (1) maintenance of a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, with stochastic uncertainty arising from the many possible disruptions that could occur over the 10,000-year regulatory period that applies to the WIPP, and subjective uncertainty arising from the imprecision with which many of the quantities required in the analysis are known, (2) use of Latin hypercube sampling to incorporate the effects of subjective uncertainty, (3) use of Monte Carlo (i.e., random) sampling to incorporate the effects of stochastic uncertainty, and (4) efficient use of the necessarily limited number of mechanistic calculations that can be performed to support the analysis. The WIPP is under development by the U.S. Department of Energy (DOE) for the geologic (i.e., deep underground) disposal of transuranic (TRU) waste, with the indicated PA supporting a Compliance Certification Application (CCA) by the DOE to the U.S. Environmental Protection Agency (EPA) in October 1996 for the necessary certifications for the WIPP to begin operation. The EPA certified the WIPP for the disposal of TRU waste in May 1998, with the result that the WIPP will be the first operational facility in the United States for the geologic disposal of radioactive waste. PMID:10765441

Helton, J C; Anderson, D R; Jow, H N; Marietta, M G; Basabilvazo, G

1999-10-01

403

Feasibility study for the processing of Hanford Site cesium and strontium isotopic sources in the Hanford Waste Vitrification Plant  

SciTech Connect

The final environmental impact statement for the disposal of defense-related wastes at the Hanford Site (Final Environmental Impact Statement: Disposal of Hanford Defense High-Level, Transuranic and Tank Wastes [HDW-EIS] [DOE 1987]) states that the preferred alternative for disposal of cesium and strontium wastes at the Hanford Site will be to package and ship these wastes to the commercial high-level waste repository. The Record of Decision for this EIS states that before shipment to a geologic repository, these wastes will be packaged in accordance with repository waste acceptance criteria. However, the high cost per canister for repository disposal and uncertainty about the acceptability of overpacked capsules by the repository suggest that additional alternative means of disposal be considered. Vitrification of the cesium and strontium salts in the Hanford Waste Vitrification Plant (HWVP) has been identified as a possible alternative to overpacking. Subsequently, Westinghouse Hanford Company`s (Westinghouse Hanford) Projects Technical Support Office undertook a feasibility study to determine if any significant technical issues preclude the vitrification of the cesium and strontium salts. Based on the information presented in this report, it is considered technically feasible to blend the cesium chloride and strontium fluoride salts with neutralized current acid waste (NCAW) and/or complexant concentrate (CC) waste feedstreams, or to blend the salts with fresh frit and process the waste through the HWVP.

Anantatmula, R.P.; Watrous, R.A.; Nelson, J.L. [Westinghouse Hanford Co., Richland, WA (United States); Perez, J.M.; Peters, R.D.; Peterson, M.E. [Pacific Northwest Lab., Richland, WA (United States)

1991-09-01

404

The Universal Canister Strategy in Spent Fuel Reprocessing: UC-C a Real Industrial Improvement  

SciTech Connect

In commercial nuclear activities, spent fuel back end management is a key issue for nuclear countries as spent fuel represent most of national civil nuclear waste legacy. Ensuring public safety and protection of the environment, now and in the future has been and still remains a major commitment, it is still the subject of thorough development efforts and active public debates. Considerable benefits can be obtained from the Universal Canister strategy as implemented in France in spent fuel treatment and waste conditioning based on reprocessing. COGEMA developed sophisticated waste conditioning processes to simplify High Level and Long Lived Intermediate Level Waste storage and final disposal. Main benefits are: waste stabilization by immobilization and encapsulation; ultimate waste toxicity reduction; drastic ultimate waste volume reduction; and ultimate waste packages standardization.

Thomasson, J.; Barithel, S.; Cocaud, A.; Derycke, P.; Pierre, P.

2003-02-25

405

Swedish nuclear waste efforts  

SciTech Connect

After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981.

Rydberg, J.

1981-09-01

406

Influence of fuel cost on the operation of a gas turbine-waste heat boiler cogeneration plant  

Microsoft Academic Search

The influence of fuel cost on the operation is investigated for a gas turbine-waste heat boiler cogeneration plant by an optimal operational planning method. A planning method is first presented by which the operational policy of each piece of constituent equipment is determined so as to minimize the operational cost. Then, a case study is performed for a cogeneration plant

K. Ito; R. Yokoyama; S. Akagi; Y. Matsumoto

1990-01-01

407

Waste Isolation Pilot Plant site environmental report for calendar year 1990  

SciTech Connect

The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) monitors a comprehensive set of parameters in order to detect any potential environmental impacts and establish baselines for future quantitative environmental impact evaluations. Surface water and groundwater, soil, and biotics are measured for background radiation. Nonradiological environmental monitoring activities include meteorological, air quality, soil properties, and the status of the local biological community. Ecological studies focus on the immediate area surrounding the site with emphasis on the salt storage pile, whereas baseline radiological surveillance covers a broader geographic area including nearby ranches, villages, and cities. Since the WIPP is still in a preoperational state, no waste has been received; therefore, certain elements required by Order DOE 5400.1 are not presented in this report. 15 figs. 19 tabs.

Not Available

1990-01-01

408

Human Factors engineering criteria and design for the Hanford Waste Vitrification Plant preliminary safety analysis report  

SciTech Connect

This report provides a rationale and systematic methodology for bringing Human Factors into the safety design and operations of the Hanford Waste Vitrification Plant (HWVP). Human Factors focuses on how people perform work with tools and machine systems in designed settings. When the design of machine systems and settings take into account the capabilities and limitations of the individuals who use them, human performance can be enhanced while protecting against susceptibility to human error. The inclusion of Human Factors in the safety design of the HWVP is an essential ingredient to safe operation of the facility. The HWVP is a new construction, nonreactor nuclear facility designed to process radioactive wastes held in underground storage tanks into glass logs for permanent disposal. Its design and mission offer new opposites for implementing Human Factors while requiring some means for ensuring that the Human Factors assessments are sound, comprehensive, and appropriately directed.

Wise, J.A.; Schur, A.; Stitzel, J.C.L.

1993-09-01

409

A formal expert judgment procedure for performance assessments of the Waste Isolation Pilot Plant  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) is an experimental facility located in southeastern New Mexico. It has been designed to determine the feasibility of the geologic disposal of defense-generated transuranic waste in a deep bedded-salt formation. The WIPP was also designed for disposal and will operate in that capacity if approved. The WIPP Performance Assessment Department at Sandia National Laboratories has been conducting analyses to assess the long-term performance of the WIPP. These analyses sometimes require the use of expert judgment. This Department has convened several expert-judgment panels and from that experience has developed an internal quality-assurance procedure to guide the formal elicitation of expert judgment. This protocol is based on the principles found in the decision-analysis literature.

Trauth, K.M. [Sandia National Labs., Albuquerque, NM (United States); Guzowski, R.V. [Science Applications International Corp., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States). Business Administration & Economics Div.

1994-09-01

410

Odour emissions from a waste treatment plant using an inverse dispersion technique  

NASA Astrophysics Data System (ADS)

The determination of the in situ emission rate of pollution sources can often not be done directly. In the absence of emission measurements, the emission rate of the source can be assessed by an inverse dispersion technique using ambient concentration measurements and meteorological parameters as input. The dispersion model used is the Austrian regulatory Gaussian model. The method is applied to a thermal waste recycling plant. Seven chemical species (butyl acetate, benzene, ethyl acetate, toluene, m/p-xylene, o-xylene and ?-pinene), are identified as odorants and measured over a period of 1½ years in the prevailing wind direction leeward of the plant. The overall odour emission rate is calculated by adding the odour emission rate of all single species, using the individual odour threshold concentration. The estimated odour emission rates range between 206 and 8950 OU s -1, caused by the wide variety of the odour thresholds of the seven species. The higher value is in the upper range of odour emission rates of modern thermal treatment plants for waste.

Schauberger, Günther; Piringer, Martin; Knauder, Werner; Petz, Erwin

2011-03-01

411

Estimation of waste water treatment plant methane emissions: methodology and results from a short campaign  

NASA Astrophysics Data System (ADS)

This paper describes different methods to estimate methane emissions at different scales. These methods are applied to a waste water treatment plant (WWTP) located in Valence, France. We show that Fourier Transform Infrared (FTIR) measurements as well as Cavity Ring Down Spectroscopy (CRDS) can be used to measure emissions from the process to the regional scale. To estimate the total emissions, we investigate a tracer release method (using C2H2) and the Radon tracer method (using 222Rn). For process-scale emissions, both tracer release and chamber techniques were used. We show that the tracer release method is suitable to quantify facility- and some process-scale emissions, while the Radon tracer method encompasses not only the treatment station but also a large area around. Thus the Radon tracer method is more representative of the regional emissions around the city. Uncertainties for each method are described. Applying the methods to CH4 emissions, we find that the main source of emissions of the plant was not identified with certainty during this short campaign, although the primary source of emissions is likely to be from solid sludge. Overall, the waste water treatment plant represents a small part (3%) of the methane emissions of the city of Valence and its surroundings,which is in agreement with the national inventories.

Yver-Kwok, C. E.; Müller, D.; Caldow, C.; Lebegue, B.; Mønster, J. G.; Rella, C. W.; Scheutz, C.; Schmidt, M.; Ramonet, M.; Warneke, T.; Broquet, G.; Ciais, P.

2013-10-01

412

Vetiver grass, Vetiveria zizanioides: a choice plant for phytoremediation of heavy metals and organic wastes.  

PubMed

Glasshouse and field studies showed that Vetiver grass can produce high biomass (>100t/ tha(-1) year(-1)) and highly tolerate extreme climatic variation such as prolonged drought, flood, submergence and temperatures (-15 degrees - 55 degrees C), soils high in acidity and alkalinity (pH 3.3-9.5), high levels of Al (85% saturation percentage), Mn (578 mg kg(-1)), soil salinity (ECse 47.5 dS m(-1)), sodicity (ESP 48%), anda wide range of heavy metals (As, Cd, Cr, Cu, Hg, Ni, Pb, Se, and Zn). Vetiver can accumulate heavy metals, particularly lead (shoot 0.4% and root 1%) and zinc (shoot and root 1%). The majority of heavy metals are accumulated in roots thus suitable for phytostabilization, and for phytoextraction with addition of chelating agents. Vetiver can also absorb and promote biodegradation of organic wastes (2,4,6-trinitroluene, phenol, ethidium bromide, benzo[a]pyrene, atrazine). Although Vetiver is not as effective as some other species in heavy metal accumulation, very few plants in the literature have a wide range of tolerance to extremely adverse conditions of climate and growing medium (soil, sand, and railings) combined into one plant as vetiver. All these special characteristics make vetiver a choice plant for phytoremediation of heavy metals and organic wastes. PMID:19810597

Danh, Luu Thai; Truong, Paul; Mammucari, Raffaella; Tran, Tam; Foster, Neil

2009-01-01

413

21 CFR 211.115 - Reprocessing.  

...DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) DRUGS: GENERAL CURRENT GOOD MANUFACTURING PRACTICE FOR FINISHED PHARMACEUTICALS Production and Process Controls § 211.115 Reprocessing. (a) Written procedures shall be...

2014-04-01

414

Diversion scenarios in an aqueous reprocessing facility  

E-print Network

The International Atomic Energy Agency requires nuclear facilities around the world to abide by heavily enforced safeguards to prevent proliferation. Nuclear fuel reprocessing facilities are designed to be proliferation-resistant ...

Calderón, Lindsay Lorraine

2009-01-01

415

Waste heat disposal from U. S. geothermal power plants--an update  

SciTech Connect

Dissipation of the heat rejected from geothermal power plants is a major concern because the inherently low efficiencies result in heat rejection rates that are three to four times greater per kW of installed capacity than is typical of fossil- or nuclear-fueled stations. The most cost-effective methods of waste heat dissipation involve the evaporation of water, yet most of the important hydrothermal resources of the U.S. are located in areas where cooling tower makeup water for power plants is in short supply. Flashed-steam power cycles can use condensate derived from the geofluid for tower makeup unless reinjection is necessary, as is already required at some sites. Condensate is not available from binary cycles because the geofluid is reinjected. Geothermal station makeup water requirements have been estimated at 50 -- 100 m/sup 3//yr per kW of electrical capacity. Some of the methods currently being studied in the U.S. for reducing waste heat dissipation system costs and water consumption are: allowing plant power output to vary with ambient conditions; use of ammonia to transport waste heat from the turbine condenser to air-cooled coils; development of plastic-membrane type wet/dry tower; marketing of steam turbines that can tolerate a wider range o back pressures; use of circulating water storage to delay heat dissipation until more favourable ambient conditions exist; development of tubes with enhanced heat transfer surfaces to reduce condenser capital costs; and use of evaporative condensers to reduce costs in binary cycles. Many of these projects involve large-scale tests that are now installed and producing some preliminary data. Definitive results from some of the tests may not be available until mid-1982 or later.

Robertson, R.C.

1983-01-01

416

Peat-assisted phytoremediation of waste foundry sands: plant growth, metal accumulation and fertility aspects.  

PubMed

We investigated the potential of peat additions to improve plant growth and fertility and to reduce plant metal uptake in waste foundry sands (WFS) landfills. The WFS contains 78211 mg kg(-1) and 371 mg kg(-1) concentrations of Cr and Ni, respectively, and varied metal concentrations. The experiment investigated the growth of Brassica juncea plants on fertilized WFS mixed with peat at concentrations of 0, 2.5, 5, and 10% (w/w). The highest peat treatment allowed substantial plant growth and increased Ni mass in shoots, which was positively correlated to shoot biomass increments. On a concentration basis, peat additions did not increase shoot Ni values, thus suggesting that plants grown on peat-treated WFS may not increase risks to human and ecological receptors. Chromium was below detection levels in shoots for all peat treatments. Peat-treated substrates also promoted increased CEC values and higher water holding capacity, therefore improving the WFS agronomical properties. These results indicate that peat can be used as an amendment to assist in the phytoremediation of WFS landfill areas. However, there was evidence for increased mobilization of Cr and Ni in the substrate solution which can pose a threat to local groundwater. PMID:22567709

Moreno, Fábio N; Sígolo, Joel B; Figueira, Antonio V

2012-03-01

417

Field scale remediation of mine wastes at an abandoned gold mine, Australia II: Effects on plant growth and groundwater  

Microsoft Academic Search

This second paper reports the results of plant growth, plant mortality, plant leaf tissue metal and salt concentrations and\\u000a leachate quality monitoring from lysimeters in four large field trial treatments established on sulfidic waste rock\\/soil that\\u000a was used for haul road construction at a closed gold mine in Australia. The TerraB™, lime and clay treatments allowed good\\u000a tree growth of

Greg Maddocks; Chuxia Lin; David McConchie

2009-01-01

418

Waste  

SciTech Connect

A process for converting wastes in molten salts into usable fuels is described. The molten salt acts as a reaction medium and potential acidic pollutants are retained in the melt. The waste is converted to a fuel gas by reacting it with insufficient air for complete conversion to CO/sub 2/ and H/sub 2/O. The product gas is cleared of particles using a baghouse or venturi scrubber and it is then burned in a boiler to produce steam. The results for waste streams containing a high-sulfur oil refinery waste, rubber, wood, leather scraps, and waste x-ray film are presented in this article.

Gay, R.L.; Barclay, K.M.; Grantham, L.F.; Yosim, S.J.

1981-09-01

419

Biogeochemical Investigations to Evaluate the Performance of the Waste Isolation Pilot Plant (WIPP) (Invited)  

NASA Astrophysics Data System (ADS)

The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy facility located in southeastern New Mexico, approximately 655 m (2150 ft.) below ground surface in a bedded salt, Permian evaporite formation. This mined geologic repository has been receiving transuranic (TRU) waste from defense-related and environmental-management activities since March 1999. TRU waste contains alpha-emitting transuranic nuclides with half-lives greater than twenty years at concentrations greater than 100 nCi/gram. These actinide-contaminated wastes were generated from nuclear-weapons production and related processing activities. They include various organics, adsorbed liquids, sludges, cellulosics, plastics, rubber, and a variety of metals and cemented materials. An extensive set of investigations were performed to establish the basis for TRU waste disposal at WIPP and to support initial certification from the U.S. Environmental Protection Agency. A significant element of the conceptual geochemical model for WIPP is the microbiologically-driven reactions leading to biodegradation of organic constituents in TRU wastes, as well as interactions with actinides present in the waste. This presentation will discuss the biogeochemical investigations that were performed to evaluate microbiological activity at WIPP, including studies of gas generation due to biodegradation of cellulose, plastic, and rubber materials and actinide-microbe interactions leading to changes in actinide chemical speciation. Highlights of this work are discussed here. Cellulose biodegradation in salt-brine systems results in the generation of carbon dioxide and hydrogen, and aqueous fermentation products (low molecular weight organic acids). Hypersaline brine can limit the range of microbial metabolic pathways, due to the energetic stresses of maintaining osmotic balance compatible with metabolic processes. Methanogenesis yields the lowest free energy per mole of carbon and as such is often not detected in microorganisms that thrive in salt-brine environments (halophilic bacteria). However, laboratory tests performed over a period of 10 years demonstrated the production of methane gas from cellulose metabolism. Studies of actinide-microbe interactions revealed the bioaccumulation of uranium in phosphate-rich intracellular granules. These studies advanced the understanding of the metabolism of bacteria in salt-brine systems and the influence of halophilic microbiological activity on WIPP geochemistry.

Gillow, J. B.

2009-12-01

420

RADIOACTIVE WASTE MANAGEMENT IN THE CHERNOBYL EXCLUSION ZONE - 25 YEARS SINCE THE CHERNOBYL NUCLEAR POWER PLANT ACCIDENT  

SciTech Connect

Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities of the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste related problems in Ukraine and the Chernobyl Exclusion Zone, and in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program. The brief overview of the radioactive waste issues in the ChEZ presented in this article demonstrates that management of radioactive waste resulting from a beyond-designbasis accident at a nuclear power plant becomes the most challenging and the costliest effort during the mitigation and remediation activities. The costs of these activities are so high that the provision of radioactive waste final disposal facilities compliant with existing radiation safety requirements becomes an intolerable burden for the current generation of a single country, Ukraine. The nuclear accident at the Fukushima-1 NPP strongly indicates that accidents at nuclear sites may occur in any, even in a most technologically advanced country, and the Chernobyl experience shows that the scope of the radioactive waste management activities associated with the mitigation of such accidents may exceed the capabilities of a single country. Development of a special international program for broad international cooperation in accident related radioactive waste management activities is required to handle these issues. It would also be reasonable to consider establishment of a dedicated international fund for mitigation of accidents at nuclear sites, specifically, for handling radioactive waste problems in the ChEZ. The experience of handling Chernobyl radioactive waste management issues, including large volumes of radioactive soils and complex structures of fuel containing materials can be fairly useful for the entire world's nuclear community and can help make nuclear energy safer.

Farfan, E.; Jannik, T.

2011-10-01

421

Performance Assessment in Support of the 1996 Compliance Certification Application for the Waste Isolation Pilot Plant  

SciTech Connect

The conceptual and computational structure of a performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) is described. Important parts of thk structure are @ maintenance of a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertain, with stochastic uncefinty arising from the many possible disruptions that could occur over the 10,000 Y regulatory period fiat applies to the WIPP and subjective uncertainty arising from `the imprecision with which many of the quantities rquired in tie `hdysis are known, (ii) use of Latin hypercttbe sampling to incorporate the effects of subjective uncefirtty, (iii) use of Monte Carlo (i.e., random) sampling to incorporate the effects of stochastic uncetinty, and OV) efficient use of tie necessarily limited number of mechanistic calculations that can be performed to SUPPOII the analysis. The WIPP is under development by the U.S. Department of Ener~ (DOE) for the geologic (i.e., deep underground) disposal of transuranic (TRU) waste, with the indicated PA supporting a ~Compliance Certification Application (CCA) by the DOE to the U.S. Environmental Protection Agency (EPA) in October 1996 for tie necessary certifications for the WIPP to begin operation. If certified, the WIPP will be the first operational faciliv in tie United States for the geologic disposal of ra&oactive waste.

Anderson, D.R.; Basabilvazo, G.; Helton, J.C.; Jow, H.-N.; Marietta, M.G.

1998-10-14

422

Environmental Assessment for Hazardous Waste Staging Facility, Pantex Plant, Amarillo, Texas  

SciTech Connect

This Environmental Assessment (EA) has been prepared pursuant to the implementing regulations to the National Environmental Policy Act (NEPA), which require federal agencies to assess the environmental impacts of a proposed action to determine whether that action requires the preparation of an Environmental Impact Statement (EIS) or if a Finding of No Significant Impact (FONSI) can be issued. The Pantex Plant does not possess permanent containerized waste staging facilities with integral secondary containment or freeze protection. Additional deficiencies associated with some existing staging facilities include: no protection from precipitation running across the staging pads; lack of protection against weathering; and facility foundations not capable of containing leaks, spills or accumulated precipitation. These shortcomings have raised concerns with respect to requirements under Section 3001 of the Resource Conservation and Recovery Act (RCRA). Deficiencies for these waste staging areas were also cited by a government audit team (Tiger Team) as Action Items. The provision for the staging of hazardous, mixed, and low level waste is part of the no-action altemative in the Programmatic Environmental Impact Statement for the integrated ER/WM program. Construction of this proposed project will not prejudice whether or not this integration will occur, or how.

Not Available

1993-06-01

423

Concepts for operational period panel seal design at the Waste Isolation Pilot Plant  

SciTech Connect

Concepts for underground panel or drift seals at the Waste Isolation Pilot Plant are developed to satisfy sealing requirements of the operational period. The concepts are divided into two groups. In the ``NOW`` group, design concepts are considered in which a sleeve structure is installed in the panel access immediately after excavation and before waste is emplaced. In the ``LATER`` group, no special measures are taken during excavation or before waste emplacement; the seal is installed at a later date, perhaps up to 35 years after the drift is excavated. Three concepts are presented in both the NOW and LATER groups. A rigid sleeve, a yielding sleeve, and steel rings with inflatable tubes are proposed as NOW concepts. One steel ring concept and two concrete monoliths are proposed for seals emplaced in older drifts. Advantages and disadvantages are listed for each concept. Based on the available information, it appears most feasible to recommend a LATER concept using a concrete monolith as a preferred seal for the operational period. Each concept includes the potential of remedial grout and/or construction of a chamber that could be used for monitoring leakage from a closed panel during the operational period. Supporting in situ demonstrations of elements of the concepts are recommended.

Hansen, F.D. [Sandia National Labs., Albuquerque, NM (United States); Lin, M.S. [Parsons, Brinckerhoff, Quade and Douglas, Inc., San Francisco, CA (United States); Van Sambeek, L.L. [RE/SPEC, Inc., Rapid City, SD (United States)

1993-07-01

424

Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 2, Technical basis  

SciTech Connect

Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume, Volume 2, contains the technical basis for the 1992 PA. Specifically, it describes the conceptual basis for consequence modeling and the PA methodology, including the selection of scenarios for analysis, the determination of scenario probabilities, and the estimation of scenario consequences using a Monte Carlo technique and a linked system of computational models. Additional information about the 1992 PA is provided in other volumes. Volume I contains an overview of WIPP PA and results of a preliminary comparison with the long-term requirements of the EPA`s Environmental Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses related to the preliminary comparison with 40 CFR 191B. Volume 5 contains uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance. Finally, guidance derived from the entire 1992 PA is presented in Volume 6.

Not Available

1992-12-01

425

Potential for long-term isolation by the Waste Isolation Pilot Plant disposal system  

SciTech Connect

The US Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) must comply with EPA regulation 40 CFR Part 191, Subpart B, which sets environmental standards for radioactive waste disposal. The regulation, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (hereafter referred to as the Standard), was vacated in 1987 by a Federal Court of Appeals and is underground revision. By agreement with the Sate of New Mexico, the WIPP project is evaluating compliance with the Standard as promulgated, in 1985 until a new regulation is available. This report summarizes the early-1990 status of Sandia National Laboratories' (SNL) understanding of the Project's ability to achieve compliance. The report reviews the qualitative and quantitative requirements for compliance, and identifies unknowns complicating performance assessment. It discusses in relatively nontechnical terms the approaches to resolving those unknowns, and concludes that SNL has reasonable confidence that compliance is achievable with the Standard as first promulgated. 46 refs., 7 figs.

Bertram-Howery, S.G. (Sandia National Labs., Albuquerque, NM (USA)); Swift, P.N. (Tech. Reps., Inc., Albuquerque, NM (USA))

1990-06-01

426

First-order study of property/composition relationships for Hanford Waste Vitrification Plant glasses  

SciTech Connect

A first-order composition variability study (CVS-I) was conducted for the Hanford Waste Vitrification Plant (HWVP) program to preliminarily characterize the effects on key glass properties of variations i selected glass (waste and frit) components. The components selected were Si0{sub 2},B{sub 2}O{sub 3},A1{sub 2}O{sub 3}, Fe{sub 2}O{sub 3}, ZrO{sub 2}, Na{sub 2}O,Li{sub 2}O,CaO,MgO, and Others (all remaining waste components). A glass composition region was selected for study based on the expected range of glass compositions and the results of a previous series of scoping and solubility studies. Then, a 23-glass statistically-designed mixture experiment was conducted and data obtained for viscosity, electrical conductivity, glass transition temperature, thermal expansion, crystallinity, and durability [Materials Characterization Center (MCC-1) 28-day leach test and the 7-day Product Consistency Test (PCT)]. These data were modeled using first-order functions of composition, and the models were used to investigate the effects of the components on glass and melt properties. The CVS-I data and models will also be used to support the second-order composition variability study (CVS-II).

Piepel, G.F.; Hrma, P.R.; Bates, S.O.; Schweiger, M.J.; Smith, D.E.

1993-01-01

427

First-order study of property/composition relationships for Hanford Waste Vitrification Plant glasses  

SciTech Connect

A first-order composition variability study (CVS-I) was conducted for the Hanford Waste Vitrification Plant (HWVP) program to preliminarily characterize the effects on key glass properties of variations i selected glass (waste and frit) components. The components selected were Si0[sub 2],B[sub 2]O[sub 3],A1[sub 2]O[sub 3], Fe[sub 2]O[sub 3], ZrO[sub 2], Na[sub 2]O,Li[sub 2]O,CaO,MgO, and Others (all remaining waste components). A glass composition region was selected for study based on the expected range of glass compositions and the results of a previous series of scoping and solubility studies. Then, a 23-glass statistically-designed mixture experiment was conducted and data obtained for viscosity, electrical conductivity, glass transition temperature, thermal expansion, crystallinity, and durability [Materials Characterization Center (MCC-1) 28-day leach test and the 7-day Product Consistency Test (PCT)]. These data were modeled using first-order functions of composition, and the models were used to investigate the effects of the components on glass and melt properties. The CVS-I data and models will also be used to support the second-order composition variability study (CVS-II).

Piepel, G.F.; Hrma, P.R.; Bates, S.O.; Schweiger, M.J.; Smith, D.E.

1993-01-01

428

Conceptual structure of performance assessments conducted for the Waste Isolation Pilot Plant  

SciTech Connect

The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is being developed by the US Department of Energy as a disposal facility for transuranic waste. In support of this project, Sandia National Laboratories is conducting an ongoing performance assessment (PA) for the WIPP. The ordered triple representation for risk prop