Analytical chemistry needs for nuclear safeguards in nuclear fuel reprocessing

International Nuclear Information System (INIS)

Hakkila, E.A.

1977-01-01

A fuel reprocessing plant designed to process 1500 tons of light water reactor fuel per year will recover 15 tons of Pu during that time, or approximately 40 to 50 kg of Pu per day. Conventional nuclear safeguards accountability has relied on batch accounting at the head and tail ends of the reprocessing plant with semi-annual plant cleanout to determine in-process holdup. An alternative proposed safeguards system relies on dynamic material accounting whereby in-line NDA and conventional analytical techniques provide indications on a daily basis of SNM transfers into the system and information of Pu holdup within the system. Some of the analytical requirements and problems for dynamic materials accounting in a nuclear fuel reprocessing plant are described. Some suggestions for further development will be proposed

Nuclear fuel reprocessing and high level waste disposal: informational hearings. Volume V. Reprocessing. Part 2

Energy Technology Data Exchange (ETDEWEB)

None

1977-03-08

Testimony was presented by a four member panel on the commercial future of reprocessing. Testimony was given on the status of nuclear fuel reprocessing in the United States. The supplemental testimony and materials submitted for the record are included in this report. (LK)

Radioactive Semivolatiles in Nuclear Fuel Reprocessing

Energy Technology Data Exchange (ETDEWEB)

Jubin, R. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Strachan, D. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ilas, G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Spencer, B. B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Soelberg, N. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-09-01

In nuclear fuel reprocessing, various radioactive elements enter the gas phase from the unit operations found in the reprocessing facility. In previous reports, the pathways and required removal were discussed for four radionuclides known to be volatile, 14C, 3H, 129I, and 85Kr. Other, less volatile isotopes can also report to the off-gas streams in a reprocessing facility. These were reported to be isotopes of Cs, Cd, Ru, Sb, Tc, and Te. In this report, an effort is made to determine which, if any, of 24 semivolatile radionuclides could be released from a reprocessing plant and, if so, what would be the likely quantities released. As part of this study of semivolatile elements, the amount of each generated during fission is included as part of the assessment for the need to control their emission. Also included in this study is the assessment of the cooling time (time out of reactor) before the fuel is processed. This aspect is important for the short-lived isotopes shown in the list, especially for cooling times approaching 10 y. The approach taken in this study was to determine if semivolatile radionuclides need to be included in a list of gas-phase radionuclides that might need to be removed to meet Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. A list of possible elements was developed through a literature search and through knowledge and literature on the chemical processes in typical aqueous processing of nuclear fuels. A long list of possible radionuclides present in irradiated fuel was generated and then trimmed by considering isotope half-life and calculating the dose from each to a maximum exposed individual with the US EPA airborne radiological dispersion and risk assessment code CAP88 (Rosnick 1992) to yield a short list of elements that actually need to be considered for control because they require high decontamination factors to meet a reasonable fraction of the regulated release. Each of these elements is

Nuclear material inventory estimation in a nuclear fuel reprocessing facility

International Nuclear Information System (INIS)

Bennett, J.E.; Beyerlein, A.L.

1981-01-01

A new approach in the application of modern system identification and estimation techniques is proposed to help nuclear reprocessing facilities meet the nuclear accountability requirement proposed by the International Atomic Energy Agency. The proposed identification and estimation method considers the material inventory in a portion of the chemical separations area of a reprocessing facility. The method addresses the nonlinear aspects of the problem, the time delay through the separation facility, and the lack of measurement access. The method utilizes only input-output measured data and knowledge of the uncertainties associated with the process and measured data. 14 refs

On-line control of nuclear fuel reprocessing

International Nuclear Information System (INIS)

Parus, I.; Kierzek, J.; Zoltowski, T.

1977-01-01

The development trends in the field of chemical processes control and the present state of the development of continuous composition analysers has been described. On this background the peculiarities of on-line control methods for spent nuclear fuel reprocessing have been discussed. The measuring methods for direct and indirect determination of chemical composition and nuclear safety are reviewed in detail. The review comprises such methods as: measurement of α, γ and neutron radiation emitted both by nuclides present in technological solutions and using external sources of different radiation, X-ray fluorescence, measurements of physicochemical parameters connected with the composition (pH, density, electrical conductivity), polarography and spectrophotometry. At the end of this review some new trends in process control based on dynamic process models have been presented. (author)

Nuclear fuel re-processing plant

International Nuclear Information System (INIS)

Sasaki, Yuko; Honda, Takashi; Shoji, Saburo; Kobayashi, Shiro; Furuya, Yasumasa

1989-01-01

In a nuclear fuel re-processing plant, high Si series stainless steels not always have sufficient corrosion resistance in a solution containing only nitric acid at medium or high concentration. Further, a method of blowing NOx gases may possibly promote the corrosion of equipment constituent materials remarkably. In view of the above, the corrosion promoting effect of nuclear fission products is suppressed without depositing corrosive metal ions as metals in the nitric acid solution. That is, a reducing atmosphere is formed by generating NOx by electrolytic reduction thereby preventing increase in the surface potential of stainless steels. Further, an anode is disposed in the nitric acid solution containing oxidative metal ions to establish an electrical conduction and separate them by way of partition membranes and a constant potential or constant current is applied while maintaining an ionic state so as not to deposit metals. Thus, equipments of re-processing facility can be protected from corrosion with no particular treatment for wastes as radioactive materials. (K.M.)

Legal problems of nuclear fuel reprocessing

International Nuclear Information System (INIS)

Rossnagel, A.

1987-01-01

The contributions in this book are intended to exemplify the legal situation in connection with the reprocessing of spent nuclear fuel from the point of view of constitutional law, administrative law, and international law. Outline solutions are presented with regard to ensuring health, personal freedom, democratic rights and other rights, and are discussed. The author Rossnagel investigates whether the principle of essential matter can guarantee a parliamentary prerogative concerning this field of large-scale technology. The author Schmidt shows that there is no legal obligation of commitment to a reprocessing technology that would exclude research for or application of a less hazardous technology. The contribution by Baumann explains the problems presented by a technology not yet developed to maturity with regard to the outline approval of the technological concept, which is a prerequisite of any partial licence to be issued. The final contribution by Guendling investigates the duties under international law, as for instance transfrontier information, consultation, and legal protection, and how these duties can be better put into practice in order to comply the seriousness of the hazards involved in nuclear fuel reprocessing. (orig./HP) [de

Handbook on process and chemistry of nuclear fuel reprocessing. 3rd edition

International Nuclear Information System (INIS)

2015-03-01

The fundamental data on spent nuclear fuel reprocessing and related chemistry was collected and summarized as a new edition of 'Handbook on Process and Chemistry of Nuclear Fuel Reprocessing'. The purpose of this handbook is contribution to development of the fuel reprocessing and fuel cycle technology for uranium fuel and mixed oxide fuel utilization. Contents in this book was discussed and reviewed by specialists of science and technology on fuel reprocessing in Japan. (author)

Predicting the behaviour or neptunium during nuclear fuel reprocessing

International Nuclear Information System (INIS)

Drake, V.A.

1988-01-01

Behaviour of Np and its distribution over reprocessing flowsheet is studied due to the necessity of improvement of reprocessing methods of wastes formed during purex-process. Valency states of Np in solutions of reprocessing cycles, Np distribution in organic and acid phases, Np(5) oxidation by nitric acid at the stage of extraction, effect of U and Pu presence on Np behaviour, are considered. Calculation and experimental data are compared; the possibility of Np behaviour forecasting in the process of nuclear fuel reprocessing, provided initial data vay, is shown. 7 refs.; 4 figs.; 1 tab

Simulations of Atmospheric Krypton-85 to Assess the Detectability of Clandestine Nuclear Reprocessing

International Nuclear Information System (INIS)

Ross, O.; Ahlswede, J.; Annewandter, R.; Kalinowski, M.B.; Rast, S.; Schluenzen, K.H.

2010-01-01

The results of this study were achieved in the project 'Simulation of Atmospheric Noble Gas Concentrations to Assess Sampling Procedures for the Detection of Clandestine Nuclear Reprocessing' (IAEA GER 1643) in the joint programme of IAEA and Federal Government of Germany. In the first year of the project the detectability of additional krypton-85 sources was investigated using atmospheric transport modelling. Krypton-85 is released into the air during reprocessing of spent nuclear fuel rods. Therefore the krypton-85 signature can possibly be used for the detection of undeclared plutonium separation. First, the global krypton-85 background produced by known reprocessing facilities from 1971 until 2006 was simulated with the atmospheric general circulation model ECHAM5 using annual emission data. The model results were evaluated by extensive comparison with measurements performed by the German Federal Office for Radiation Protection. Of particular interest for an assessment of the detectability of unknown sources is the background variability. The variability of concentrations is very high over central Europe, where the large reprocessing plants La Hague and Sellafield are located, and it is very low on the Southern Hemisphere, where no nuclear reprocessing takes place. The analysis of concentration time series on various time scales allows partly a distinction between fluctuations caused by the variability of the sources from variations due to atmospheric dynamics. Furthermore the detection sensitivity to a set of arbitrarily specified source locations is analysed with a Lagrangian particle dispersion model. This, in combination with the location specific background variability, is giving first benchmarks on the capability of using krypton-85 for IAEA Safeguards based on the Additional Protocols foreseeing environmental sampling. (author)

Operation of Nuclear Fuel Based on Reprocessed Uranium for VVER-type Reactors in Competitive Nuclear Fuel Cycles

Energy Technology Data Exchange (ETDEWEB)

Troyanov, V.; Molchanov, V.; Tuzov, A. [TVEL Corporation, 49 Kashirskoe shosse, Moscow 115409 (Russian Federation); Semchenkov, Yu.; Lizorkin, M. [RRC ' Kurchatov Institute' (Russian Federation); Vasilchenko, I.; Lushin, V. [OKB ' Gidropress' (Russian Federation)

2009-06-15

Current nuclear fuel cycle of Russian nuclear power involves reprocessed low-enriched uranium in nuclear fuel production for some NPP units with VVER-type LWR. This paper discusses design and performance characteristics of commercial nuclear fuel based on natural and reprocessed uranium. It presents the review of results of commercial operation of nuclear fuel based on reprocessed uranium on Russian NPPs-unit No.2 of Kola NPP and unit No.2 of Kalinin NPP. The results of calculation and experimental validation of safe fuel operation including necessary isotope composition conformed to regulation requirements and results of pilot fuel operation are also considered. Meeting the customer requirements the possibility of high burn-up achieving was demonstrated. In addition the paper compares the characteristics of nuclear fuel cycles with maximum length based on reprocessed and natural uranium considering relevant 5% enrichment limitation and necessity of {sup 236}U compensation. The expedience of uranium-235 enrichment increasing over 5% is discussed with the aim to implement longer fuel cycles. (authors)

The main chemical safety problems in main process of nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Song Fengli; Zhao Shangui; Liu Xinhua; Zhang Chunlong; Lu Dan; Liu Yuntao; Yang Xiaowei; Wang Shijun

2014-01-01

There are many chemical reactions in the aqueous process of nuclear fuel reprocessing. The reaction conditions and the products are different so that the chemical safety problems are different. In the paper the chemical reactions in the aqueous process of nuclear fuel reprocessing are described and the main chemical safety problems are analyzed. The reference is offered to the design and accident analysis of the nuclear fuel reprocessing plant. (authors)

The proceedings of China-Japan workshop on nuclear waste management and reprocessing

International Nuclear Information System (INIS)

2000-01-01

China-Japan workshop on Nuclear Waste Management and Reprocessing held by sponsors, Nuclear Chemical Engineering Association, Chinese nuclear Society and Division of nuclear Fuel Cycle and Environment, Atomic Energy Society of Japan and by co-sponsor, Nuclear and Radiochemistry Association, Chinese Nuclear Society, on April 5-7, 2000, in Beijing, China. The proceedings is published. It collected 34 articles. The contents include nuclear fuel reprocessing, radioactive waste processing and radioactive waste disposal, partitioning and transmutation, radionuclide migration, sorption and diffusion and actinide chemistry

To reprocess to recycle. The nuclear safety

International Nuclear Information System (INIS)

1999-01-01

After a summary of fundamental notions of radioactivity and nuclear safety, the first part of this work is devoted to the organisation in France to provide the nuclear facilities safety. The second part related to the fuel cycle describes the big steps of this cycle and particularly the stakes and objectives of the reprocessing -recycling as well as the valorization of reusable matters such plutonium and uranium. The risks identification, means to control them, in conception, realisation and operation are described in the third, fourth and fifth parts. In this last part the managements of accidental situations is treated. The sixth and last part is devoted to the environment protection, treats the control of waste release of reprocessing -recycling facilities, of these waste management that is to say every disposition made by Cogema to limit the impact of its installations on environment. In this last part are also described the safety of nuclear and radioactive matters transport, and the definitive breakdown of installations. (N.C.)

Storage and Reprocessing of Spent Nuclear Fuel

Energy Technology Data Exchange (ETDEWEB)

Karpius, Peter Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-02

Addressing the problem of waste, especially high-level waste (HLW), is a requirement of the nuclear fuel cycle that cannot be ignored. We explore the two options employed currently, long-term storage and reprocessing.

Ventilating system for reprocessing of nuclear fuel rods

International Nuclear Information System (INIS)

Szulinski, M.J.

1981-01-01

In a nuclear facility such as a reprocessing plant for nuclear fuel rods, the central air cleaner discharging ventilating gas to the atmosphere must meet preselected standards not only as to the momentary concentration of radioactive components, but also as to total quantity per year. In order to comply more satisfactorily with such standards, reprocessing steps are conducted by remote control in a plurality of separate compartments. The air flow for each compartment is regulated so that the air inventory for each compartment has a slow turnover rate of more than a day but less than a year, which slow rate is conveniently designated as quasihermetic sealing. The air inventory in each such compartment is recirculated through a specialized processing unit adapted to cool and/or filter and/or otherwise process the gas. Stale air is withdrawn from such recirculating inventory and fresh air is injected (eg., By the less than perfect sealing of a compartment) into such recirculating inventory so that the air turnover rate is more than a day but less than a year. The amount of air directed through the manifold and duct system from the reprocessing units to the central air cleaner is less than in reprocessing plants of conventional design

Cost and availability of gadolinium for nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Klepper, O.H.

1985-06-01

Gadolinium is currently planned for use as a soluble neutron poison in nuclear fuel reprocessing plants to prevent criticality of solutions of spent fuel. Gadolinium is relatively rare and expensive. The present study was undertaken therefore to estimate whether this material is likely to be available in quantities sufficient for fuel reprocessing and at reasonable prices. It was found that gadolinium, one of 16 rare earth elements, appears in the marketplace as a by-product and that its present supply is a function of the production rate of other more prevalent rare earths. The potential demand for gadolinium in a fuel reprocessing facility serving a future fast reactor industry amounts to only a small fraction of the supply. At the present rate of consumption, domestic supplies of rare earths containing gadolinium are adequate to meet national needs (including fuel reprocessing) for over 100 years. With access to foreign sources, US demands can be met well beyond the 21st century. It is concluded therefore that the supply of gadolinium will quite likely be more than adequate for reprocessing spent fuel for the early generation of fast reactors. The current price of 99.99% pure gadolinium oxide lies in the range $50/lb to $65/lb (1984 dollars). By the year 2020, in time for reprocessing spent fuel from an early generation of large fast reactors, the corresponding values are expected to lie in the $60/lb to $75/lb (1984 dollars) price range. This increase is modest and its economic impact on nuclear fuel reprocessing would be minor. The economic potential for recovering gadolinium from the wastes of nuclear fuel reprocessing plants (which use gadolinium neutron poison) was also investigated. The cost of recycled gadolinium was estimated at over twelve times the cost of fresh gadolinium, and thus recycle using current recovery technology is not economical. 15 refs., 4 figs., 11 tabs

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

International Nuclear Information System (INIS)

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

1980-12-01

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

Determination of zirconium 93 and molybdenum 93 in reprocessing nuclear waste

International Nuclear Information System (INIS)

Puech, P.

1998-01-01

The aim of this work is to find new determination methods of zirconium 93 and molybdenum 93 (two long-lived radioelements) contained in reprocessing nuclear waste. 93 Zr has a very long period: 1.5 * 10 6 years. The measurement of this isotope is more performing by the ICP-MS method than by the classical radiochemical measurement methods. 93 Mo disintegrates with a radioactive period of 4000 years and can be detected by radiochemical measurement in particular by X spectrometry. But these radioelements cannot be directly measured on the reprocessing nuclear waste; they require a preliminary chemical separation (removing the radioelements able to interfere and those responsible of the radioactivity of the nuclear waste). The separation is implemented with very potentially selective techniques, using Mo and Zr specific extracting molecules: solvent extraction, emulsified liquid membrane extraction and liquid chromatography extraction (on a resin impregnated by solvent). Studies carried out in CEA/Cadarache, on a synthetic solution simulating a reprocessing nuclear waste, have allowed to show the selective properties of the L'-benzoinoxime for extracting Mo and of TBP for extracting Zr for the three studied techniques. The optimal extraction and separation conditions have been reached with a methodology including experiment plans. At last, the methods have been tested on real reprocessing nuclear waste at Cogema/La Hague. 93 Zr and 93 Mo have been measured in a dissolution solution and in a fission product solution. The obtained values are 2 * 10 6 Bq/l and 10 7 Bq/l for 93 Zr and 500 Bq/l for 93 Mo in a dissolution solution. These methods have allowed to determine too the isotopic compositions for Mo and Zr elements contained in reprocessing nuclear waste. The results are in accordance with those obtained with the Cesar code. (O.M.)

Nuclear energy without waste reprocessing in West Germany?

International Nuclear Information System (INIS)

Ebert, K.

1989-01-01

The decision to discontinue construction of the Wackersdorf waste reprocessing plant has been an item of public interest for only a short period; even supporters of nuclear power seemed to have been just relieved that this controversial project was off the agenda, and done with. So only little was to be heard from experts about the facts, background, and consequences of this decision. The author of the article in hand is head of the Hot Chemistry Institute of the Karlsruhe Nuclear Research Centre and therefore has been a leading scientist in the development of reprocessing technology. He presents from his point of view the facts and reasons leading to the decision, and explains the possible consequences for the F.R.G. (orig./RB) [de

Status of ANSI standards on decommissioning of nuclear reprocessing facilities

International Nuclear Information System (INIS)

Graham, H.B.

1975-01-01

A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

Reprocessing free nuclear fuel production via fusion fission hybrids

Energy Technology Data Exchange (ETDEWEB)

Kotschenreuther, Mike, E-mail: mtk@mail.utexas.edu [Intitute for Fusion Studies, University of Texas at Austin (United States); Valanju, Prashant; Mahajan, Swadesh [Intitute for Fusion Studies, University of Texas at Austin (United States)

2012-05-15

Fusion fission hybrids, driven by a copious source of fusion neutrons can open qualitatively 'new' cycles for transmuting nuclear fertile material into fissile fuel. A totally reprocessing-free (ReFree) Th{sup 232}-U{sup 233} conversion fuel cycle is presented. Virgin fertile fuel rods are exposed to neutrons in the hybrid, and burned in a traditional light water reactor, without ever violating the integrity of the fuel rods. Throughout this cycle (during breeding in the hybrid, transport, as well as burning of the fissile fuel in a water reactor) the fissile fuel remains a part of a bulky, countable, ThO{sub 2} matrix in cladding, protected by the radiation field of all fission products. This highly proliferation-resistant mode of fuel production, as distinct from a reprocessing dominated path via fast breeder reactors (FBR), can bring great acceptability to the enterprise of nuclear fuel production, and insure that scarcity of naturally available U{sup 235} fuel does not throttle expansion of nuclear energy. It also provides a reprocessing free path to energy security for many countries. Ideas and innovations responsible for the creation of a high intensity neutron source are also presented.

Reprocessing free nuclear fuel production via fusion fission hybrids

International Nuclear Information System (INIS)

Kotschenreuther, Mike; Valanju, Prashant; Mahajan, Swadesh

2012-01-01

Fusion fission hybrids, driven by a copious source of fusion neutrons can open qualitatively “new” cycles for transmuting nuclear fertile material into fissile fuel. A totally reprocessing-free (ReFree) Th 232 –U 233 conversion fuel cycle is presented. Virgin fertile fuel rods are exposed to neutrons in the hybrid, and burned in a traditional light water reactor, without ever violating the integrity of the fuel rods. Throughout this cycle (during breeding in the hybrid, transport, as well as burning of the fissile fuel in a water reactor) the fissile fuel remains a part of a bulky, countable, ThO 2 matrix in cladding, protected by the radiation field of all fission products. This highly proliferation-resistant mode of fuel production, as distinct from a reprocessing dominated path via fast breeder reactors (FBR), can bring great acceptability to the enterprise of nuclear fuel production, and insure that scarcity of naturally available U 235 fuel does not throttle expansion of nuclear energy. It also provides a reprocessing free path to energy security for many countries. Ideas and innovations responsible for the creation of a high intensity neutron source are also presented.

Administrative and managerial controls for the operation of nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Anon.

1979-01-01

Guidelines are provided for the administrative and managerial controls necessary for the safe and efficient operation of nuclear fuel reprocessing plants. Topics covered include: administrative organization; review and audit; facility administrative policies and procedures; and tests and inspections. Recognizing that administrative practices vary among organizations operating nuclear fuel reprocessing plants, the standard incorporates flexibility that provides for compliance by any organization

Reprocessing of spent nuclear fuel

International Nuclear Information System (INIS)

Gal, I.

1964-12-01

This volume contains the following reports: Experimental facility for testing and development of pulsed columns and auxiliary devices; Chemical-technology study of the modified 'Purex' process; Chemical and radiometric control analyses; Chromatographic separation of rare earth elements on paper treated by di-n butylphosphate; Preliminary study of some organic nitrogen extracts significant in fuel reprocessing

Process information systems in nuclear reprocessing

International Nuclear Information System (INIS)

Jaeschke, A.; Keller, H.; Orth, H.

1987-01-01

On a production management level, a process information system in a nuclear reprocessing plant (NRP) has to fulfill conventional operating functions and functions for nuclear material surveillance (safeguards). Based on today's state of the art of on-line process control technology, the progress in hardware and software technology allows to introduce more process-specific intelligence into process information systems. Exemplified by an expert-system-aided laboratory management system as component of a NRP process information system, the paper demonstrates that these technologies can be applied already. (DG) [de

Method of reprocessing spent nuclear fuels

International Nuclear Information System (INIS)

Kamiyama, Hiroaki; Inoue, Tadashi; Miyashiro, Hajime.

1987-01-01

Purpose: To facilitate the storage management for the wastes resulting from reprocessing by chemically separating transuranium elements such as actionoid elements together with uranium and plutonium. Method: Spent fuels from a nuclear reactor are separated into two groups, that is, a mixture of uranium, plutonium and transuranium elements and cesium, strontium and other nuclear fission products. Virgin uranium is mixed to adjust the mixture of uranium, plutonium and transuranium elements in the first group, which is used as the fuels for the nuclear reactor. After separating to recover useful metals such as cesium and strontium are separated from short half-decay nuclear fission products of the second group, other nuclear fission products are stored and managed. This enables to shorten the storage period and safety storage and management for the wastes. (Takahashi, M.)

Nuclear engineering questions: power, reprocessing, waste, decontamination, fusion

International Nuclear Information System (INIS)

Walton, R.D. Jr.

1979-01-01

This volume contains papers presented at the chemical engineering symposium on nuclear questions. Specific questions addressed by the speakers included: nuclear power - why and how; commercial reprocessing - permanent death or resurrection; long-term management of commercial high-level wastes; long-term management of defense high-level waste; decontamination and decommissioning of nuclear facilities, engineering aspects of laser fusion I; and engineering aspects of laser fusion II. Individual papers have been input to the Energy Data Base previously

Nuclear safety in fuel-reprocessing plants

International Nuclear Information System (INIS)

Hennies, H.H.; Koerting, K.

1976-01-01

The danger potential of nuclear power and fuel reprocessing plants in normal operation is compared. It becomes obvious that there are no basic differences. The analysis of possible accidents - blow-up of an evaporator for highly active wastes, zircaloy burning, cooling failure in self-heating process solutions, burning of a charged solvent, criticality accidents - shows that they are kept under control by the plant layout. (HP) [de

An overview on dry reprocessing of irradiated nuclear fuels

International Nuclear Information System (INIS)

Ouyang Yinggen

2002-01-01

Although spent nuclear fuels have been reprocessed successfully for many years by the well-know Purex process based on solvent extraction, other reprocessing method which do not depend upon the use of organic solvents and aqueous media appear to have important potential advantage. There are two main non-aqueous methods for the reprocessing of spent fuel: fluoride-volatility process and pyro-electrochemical process. The presence of a poser in the process is that PuF 6 is obviously thermodynamically stable only in the presence of a large excess of fluorine. Pyro-electrochemical process is suited to processing metallic, oxide and carbide fuels. First, the fuel is dissolved in fresh salts, then, electrodes are introduced into the bath, U and Pu are deposited on the cathode, third, separation and refinement U and Pu are deposited on the cathode. There is a couple of contradictions in the process that are not in harmonious proportion in the fields on the nuclear fuel is dissolved the ability in the molten salt and corrosiveness of the molten salt for equipment used in the process

Economic feasibility study of regional centers for nuclear fuel reprocessing in the developing countries

International Nuclear Information System (INIS)

Bakeshloo, A.A.

1977-01-01

The fuel cycle costs for the following three different economic alternatives were studied: (1) Reprocessing in an industrialized country (such as the U.S.); (2) Reprocessing in the individual developing country; (3) Reprocessing in a regional center. The nuclear fuel cycle cost for the ''Throw-away'' fuel cycle was evaluated. Among the six regions which were considered in this study, region one (South America including Mexico) was selected for the economic analysis of the nuclear fuel cycle for the above three alternatives. For evaluation of the cases where the fuel is reprocessed in a regional center or in an individual developing country, a unit reprocessing cost equation was developed. An economic evaluation was developed to estimate the least expensive method for transporting radioactive nuclear material by either leased or purchased shipping casks. The necessary equations were also developed for estimating plutonium transportation and the safeguard costs. On the basis of nuclear material and services requirements and unit costs for each component, the levelized nuclear fuel cycle costs for each alternative were estimated. Finally, by a comparison of cost, among these three alternatives plus the ''Throw-away'' case,it was found that it is not at all economical to build individual reprocessing plants inside the developing countries in region one. However, it also was found that the economic advantage of a regional center with respect to the first alternative is less than a 4% difference between their total fuel cycle costs. It is concluded that there is no great economic advantage in any developing countries to seek to process their fuel in one of the advanced countries. Construction of regional reprocessing centers is an economically viable concept

Remotex and servomanipulator needs in nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Garin, J.

1981-01-01

Work on the conceptual design of a pilot-scale plant for reprocessing breeder reactor fuels is being performed at Oak Ridge National Laboratory. The plant design will meet all current federal regulations for repocessing plants and will serve as prototype for future production plants. A unique future of the concept is the incorporation of totally remote operation and maintenance of the process equipment within a large barn-like hot cell. This approach, caled Remotex, utilizes servomanipulators coupled with television viewing to extend man's capabilities into the hostile cell environment. The Remotex concept provides significant improvements for fuel reprocessing plants and other nuclear facilities in the areas of safeguarding nuclear materials, reducing radiation exposure, improving plant availability, recovering from unplanned events, and plant decommissioning

Reprocessing decision

International Nuclear Information System (INIS)

Heising, C.D.

1978-01-01

The United States must decide whether to permit, delay, or prohibit the reprocessing and recycling of nuclear spent fuel. To permit reprocessing would allow recycle as early as 1985; to delay the decision for a later administration to deal with means spent fuel would mount up at nuclear reactor sites; to prohibit would eliminate recycling and mandate permanent storage. Bayesian decision analysis was used to examine reprocessing costs associated with risks and economic benefits. Three distinct categories of risk that are important in the nuclear fuel cycle are discussed. These are: health, environment, and safety risks; nuclear theft and sabotage; and nuclear weapons proliferation risks. Results are discussed from comparing nine routes to weapons-usuable mterial available to nonweapons states that desire a nuclear capability. These are: production reactor and military reporcessor; research reacotr and military reprocessor; power plant plus military reprocessor or commercial reprocessor; enrichment (centrifuge, gaseous diffusion, electromagnetic separation, or aerodynamic jet cascade); and accelerator. It was found that the commercial power reactor-commercial reprocessor route is comparatively unattractive to a nonweapons state. In summary, allowing nuclear fuel reprocessing to go forward in the United States can be expected to increase the costs to society by a maximum $360 million a year. This is approximately one-seventh of the expected benefit (reduced electricity bills) to be dderived by society from closing the fuel cycle. It appears that the permitting reprocessing now is logically preferable to delaying or prohibiting the technology, the author concludes

The economics of reprocessing versus direct disposal of spent nuclear fuel

International Nuclear Information System (INIS)

Bunn, M.; Holdren, J.P.; Fetter, S.; Zwaan, B. van der

2007-01-01

The economics of reprocessing versus direct disposal of spent nuclear fuel are assessed. The break-even uranium price at which reprocessing spent nuclear fuel from existing light water reactors (LWRs) and recycling the resulting plutonium and uranium in LWRs would become economic is estimated for a wide range of reprocessing prices and other fuel cycle costs and parameters. The contribution of each fuel cycle option to the cost of electricity is also estimated. A similar analysis is performed for the breakeven uranium price at which deploying fast neutron reactors (FRs) would become competitive compared with a once-through fuel cycle in LWRs, for a range of differences in capital cost between LWRs and FRs. Available information about reprocessing prices and various other fuel cycle costs and input parameters are reviewed, as well as the quantities of uranium likely to be recoverable worldwide at a range of different possible future prices. It is concluded that the once-through fuel cycle is likely to remain significantly cheaper than reprocessing and recycling in either LWRs or FRs for at least the next 50 years. Finally, there is a discussion of how scarce and expensive repository space would have to become before separation and transmutation would be economically attractive. (author)

On permission of reprocessing project change at the Reprocessing Works of the Japan Nuclear Fuel Ltd. (Reply)

International Nuclear Information System (INIS)

1997-01-01

The Nuclear Safety Commission replied as follows to the Prime Minister on July 14, 1997 on permission of reprocessing project change at the Reprocessing Works of the Japan Nuclear Fuel Ltd. inquired on Dec. 26, 1996. Contents of the inquiry consisted of change of refinery facility and its related instruments, integration of low level wasted liquid treating instrument and change of low level solid waste treating instrument, integration of high level wasted liquid storing building and high level wasted liquid glassification building, installation of used fuel transporting container maintenance instrument and its relating instruments, and so forth. As a result of careful discussion at the Commission for these items, they were admitted to be valid on her technical ability and her safety. (G.K.)

Analyzing the reprocessing decision: plutonium recycle and nuclear proliferation. Final report

International Nuclear Information System (INIS)

Heising, C.D.; Connolly, T.J.

1978-11-01

The United States decision to defer indefinitely the reprocessing of spent nuclear fuel is examined in this thesis. Bayesian decision analysis is applied to develop a rational framework for the assessment of alternatives. Benefits and costs for each alternative are evaluated and compared in dollar terms to determine the optimal decision. A fuel cycle simulation model is constructed to assess the economic value of reprocessing light water reactor (LWR) spent fuel and recycling plutonium. In addition, a dynamic fuel substitution model is used to estimate the economic effects of the reprocessing decision's influence on the introduction date of the liquid metal fast breeder reactor (LMFBR). The analysis of benefits and costs is extended to include the social costs due to technological risks, such as accident risk, nuclear theft and/or sabotage, and international nuclear proliferation. These social costs are expressed in dollar terms for comparison with the conventional economic values. Results of the analysis indicate that the domestic social costs are less than the economic benefits by more than three orders of magnitude, and that the permit option dominates those of delay or prohibit. An examination of proliferation risk indicates a factor of approximately 7 between cost-benefits. Thus, on the basis of this analysis, it appears that to permit reprocessing is optimal over delaying or prohibiting the technology

Why reprocess

International Nuclear Information System (INIS)

Hagen, M.

1977-01-01

The problem of whether to reprocess spent nuclear fuel elements has been studied already in the early days of the commercial utilization of nuclear power and has been answered positively. This also, and in particular, applies to the United States. Under the new American nuclear policy reprocessing is rejected only for reasons of non-proliferation. Although these are valid reasons, the effectiveness of a ban on reprocessing, as fas as the non-profileration of nuclear weapons is concerned, is not accepted worldwide because the necessary knowledge either already exists in many countries or can be obtained. Only if there had been a realistic chance to prevent the proliferation of nuclear weapons, also the other industrialized countries would have seconded the policy of the United States. A country like the Federal Republic of Germany, with a substantial long-term nuclear power program based initially on light water reactors, subsequently on advanced reactor systems, cannot do without a complete nuclear fuel cycle. This reasoning is outlined in the light of economic and radioecological aspects. Extensive experience on a technical scale is available in the reprocessing sector. The technical problems associated with this activity have been solved in principle and have largely been demonstrated to function in practice. (orig.) [de

Design study on advanced nuclear fuel recycling system by pyrometallurgical reprocessing technology

Energy Technology Data Exchange (ETDEWEB)

Kasai, Yoshimitsu; Kakehi, Isao; Moro, Satoshi; Tobe, Kenji; Kawamura, Fumio; Higashi, Tatsuhiro; Yonezawa, Shigeaki [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center; Yoshiuji, Takahiro

1998-12-01

The Japan Nuclear Fuel Cycle Development Institute is conducting research and development on the nuclear fuel recycling system, which will improve the economy, safety, and environmental impact of the nuclear fuel recycling system in the age of the FBR. The System Engineering Division in the O-arai Engineering Center has conducted a design study on an advanced nuclear fuel recycling system for FBRs by using pyrometallurgical reprocessing technology. The system is an economical and compact module-type system, and can be used for reprocessing oxide fuel and also new types of fuel (metal fuel and nitride fuel). This report describes the concept of this system and results of the design study. (author)

Design study on advanced nuclear fuel recycling system by pyrometallurgical reprocessing technology

International Nuclear Information System (INIS)

Kasai, Yoshimitsu; Kakehi, Isao; Moro, Satoshi; Tobe, Kenji; Kawamura, Fumio; Higashi, Tatsuhiro; Yonezawa, Shigeaki; Yoshiuji, Takahiro

1998-01-01

The Japan Nuclear Fuel Cycle Development Institute is conducting research and development on the nuclear fuel recycling system, which will improve the economy, safety, and environmental impact of the nuclear fuel recycling system in the age of the FBR. The System Engineering Division in the O-arai Engineering Center has conducted a design study on an advanced nuclear fuel recycling system for FBRs by using pyrometallurgical reprocessing technology. The system is an economical and compact module-type system, and can be used for reprocessing oxide fuel and also new types of fuel (metal fuel and nitride fuel). This report describes the concept of this system and results of the design study. (author)

Design aspects of water usage in the Windscale nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Wharton, J.; Bullock, M.J.

1982-01-01

The safeguard requirements of a nuclear fuel reprocessing plant place unique constraints on a designer which, in turn, affect the scope for the exercise of water economy. These constraints are examined within the context of the British Nuclear Fuels Limited reprocessing plants at Windscale and indicate the scope for water conservation. The plants and their design principles are described with particular reference to water services and usage. Progressive design development is discussed to illustrate the increasing importance of water economy. (author)

Methodology for estimating reprocessing costs for nuclear fuels

International Nuclear Information System (INIS)

Carter, W.L.; Rainey, R.H.

1980-02-01

A technological and economic evaluation of reprocessing requirements for alternate fuel cycles requires a common assessment method and a common basis to which various cycles can be related. A methodology is described for the assessment of alternate fuel cycles utilizing a side-by-side comparison of functional flow diagrams of major areas of the reprocessing plant with corresponding diagrams of the well-developed Purex process as installed in the Barnwell Nuclear Fuel Plant (BNFP). The BNFP treats 1500 metric tons of uranium per year (MTU/yr). Complexity and capacity factors are determined for adjusting the estimated facility and equipment costs of BNFP to determine the corresponding costs for the alternate fuel cycle. Costs of capacities other than the reference 1500 MT of heavy metal per year are estimated by the use of scaling factors. Unit costs of reprocessed fuel are calculated using a discounted cash flow analysis for three economic bases to show the effect of low-risk, typical, and high-risk financing methods

Nuclear fuel reprocessing expansion strategies

International Nuclear Information System (INIS)

Gallagher, J.M.

1975-01-01

A description is given of an effort to apply the techniques of operations research and energy system modeling to the problem of determination of cost-effective strategies for capacity expansion of the domestic nuclear fuel reprocessing industry for the 1975 to 2000 time period. The research also determines cost disadvantages associated with alternative strategies that may be attractive for political, social, or ecological reasons. The sensitivity of results to changes in cost assumptions was investigated at some length. Reactor fuel types covered by the analysis include the Light Water Reactor (LWR), High-Temperature Gas-Cooled Reactor (HTGR), and the Fast Breeder Reactor (FBR)

Management of reprocessed uranium. Current status and future prospects

International Nuclear Information System (INIS)

2007-02-01

There is worldwide interest in developing advanced and innovative technologies for nuclear fuel cycles, minimizing waste and environmental impacts. As of the beginning of 2003, about 171000 tonnes heavy metal spent nuclear fuel is in storage, while smaller amounts have been reprocessed. In several countries, including France, India, Japan and the Russian Federation, spent fuel has been viewed as a national energy resource. Some countries hold reprocessed uranium as the result of their commercial reprocessing service contracts for reprocessing the spent fuel of others. Reprocessed uranium has a potential value for recycling either directly or after appropriate treatment. This report analyses the existing options, approaches and developments in the management of reprocessed uranium. It includes the technical issues involved in managing reprocessed uranium which are RepU arisings, storage, chemical conversion, re-enrichment, fuel fabrication, transport, reactor irradiation, subsequent reprocessing and disposal options, as well as assessment of holistic environmental impacts. The objective of this document is to overview the information on the current status and future trends in the management of RepU and to identify major issues to be considered for future projects

Survey of economics of spent nuclear fuel reprocessing

International Nuclear Information System (INIS)

Valvoda, Z.

1976-01-01

Literature data are surveyed on the economic problems of reprocessing spent fuel from light-water reactors in the period 1970 to 1975 and on the capacity of some reprocessing plants, such as NFS, Windscale, Marcoule, etc. The sharp increase in capital and production costs is analyzed and the future trend is estimated. The question is discussed of the use of plutonium and the cost thereof. The economic advantageousness previously considered to be the primary factor is no longer decisive due to new circumstances. The main objective today is to safeguard uninterrupted operation of nuclear power plants and the separation of radioactive wastes from the fuel cycle and the safe disposal thereof. (Oy)

Nuclear fuel reprocessing: A time for decision

International Nuclear Information System (INIS)

O'Donnell, A.J.; Sandbery, R.O.

1983-01-01

Availability of adequate supplies of energy at an affordable cost is essential to continued growth of the world's economics. The tie between economic growth and electricity usage is particularly strong and the pervasive wordwide trend toward increasing electrification shows no signs of abating. Very few viable alternatives are available for supplying the projected increase in baseload electric generating capacity in the next several decades, and most industrialized nations have chosen nuclear power to play a major role. Sustained growth of nuclear power can only be achieved, however, by reprocessing spent fuel to recover and utilize the residual uranium and plutonium energy values

NO/sub x/ emissions from Hanford nuclear fuels reprocessing plants

International Nuclear Information System (INIS)

Pajunen, A.L.; Dirkes, R.L.

1978-01-01

Operation of the existing Hanford nuclear fuel reprocessing facilities will increase the release of nitrogen oxides (NO/sub x/) to the atmosphere over present emission rates. Stack emissions from two reprocessing facilities, one waste storage facility and two coal burning power plants will contain increased concentrations of NO/sub x/. The opacity of the reprocessing facilities' emissions is predicted to periodically exceed the State and local opacity limit of twenty percent. Past measurements failed to detect differences in the ambient air NO/sub x/ concentration with and without reprocessing plant operations. Since the facilities are not presently operating, increases in the non-occupational ambient air NO/sub x/ concentration were predicted from theoretical diffusion models. Based on the calculations, the annual average ambient air NO/sub x/ concentration will increase from the present level of less than 0.004 ppM to less than 0.006 ppM at the Hanford site boundaries. The national standard for the annual mean ambient air NO 2 concentration is 0.05 ppM. Therefore, the non-occupational ambient air NO/sub x/ concentration will not be increased to significant levels by reprocessing operations in the Hanford 200 Areas

THE ECONOMICS OF REPROCESSING vs. DIRECT DISPOSAL OF SPENT NUCLEAR FUEL

International Nuclear Information System (INIS)

Bunn, Matthew; Fetter, Steve; Holdren, John P.; Zwaan, Bob van der

2003-01-01

This report assesses the economics of reprocessing versus direct disposal of spent nuclear fuel. The breakeven uranium price at which reprocessing spent nuclear fuel from existing light-water reactors (LWRs) and recycling the resulting plutonium and uranium in LWRs would become economic is assessed, using central estimates of the costs of different elements of the nuclear fuel cycle (and other fuel cycle input parameters), for a wide range of range of potential reprocessing prices. Sensitivity analysis is performed, showing that the conclusions reached are robust across a wide range of input parameters. The contribution of direct disposal or reprocessing and recycling to electricity cost is also assessed. The choice of particular central estimates and ranges for the input parameters of the fuel cycle model is justified through a review of the relevant literature. The impact of different fuel cycle approaches on the volume needed for geologic repositories is briefly discussed, as are the issues surrounding the possibility of performing separations and transmutation on spent nuclear fuel to reduce the need for additional repositories. A similar analysis is then performed of the breakeven uranium price at which deploying fast neutron breeder reactors would become competitive compared with a once-through fuel cycle in LWRs, for a range of possible differences in capital cost between LWRs and fast neutron reactors. Sensitivity analysis is again provided, as are an analysis of the contribution to electricity cost, and a justification of the choices of central estimates and ranges for the input parameters. The equations used in the economic model are derived and explained in an appendix. Another appendix assesses the quantities of uranium likely to be recoverable worldwide in the future at a range of different possible future prices

Importance of nuclear fuel reprocessing

International Nuclear Information System (INIS)

Allday, C.

1977-01-01

The following topics are discussed: world energy requirements; energy conservation and the economics of recycle environmental considerations and the timescale of reprocessing; and problems associated with reprocessing. The conclusion is reached that reprocessing is essential to the conservation of the world's energy resources and is an environmentally, and probably an economically, more acceptable option to the ''throw away'' alternative

Improving the reliability of nuclear reprocessing by application of computers and mathematical modelling

International Nuclear Information System (INIS)

Gabowitsch, E.; Trauboth, H.

1982-01-01

After a brief survey of the present and expected future state of nuclear energy utilization, which should demonstrate the significance of nuclear reprocessing, safety and reliability aspects of nuclear reprocessing plants (NRP) are considered. Then, the principal possibilities of modern computer technology including computer systems architecture and application-oriented software for improving the reliability and availability are outlined. In this context, two information systems being developed at the Nuclear Research Center Karlsruhe (KfK) are briefly described. For design evaluation of certain areas of a large NRP mathematical methods and computer-aided tools developed, used or being designed by KfK are discussed. In conclusion, future research to be pursued in information processing and applied mathematics in support of reliable operation of NRP's is proposed. (Auth.)

Ministerial ordinance on the establishment of a reserve fund for spent nuclear fuel reprocessing

International Nuclear Information System (INIS)

1984-01-01

The ministerial ordinance provides for a reserve fund for spent nuclear fuel reprocessing, according to the Electricity Enterprises Act. The Government designates an electricity enterprise that must deposit a reserve fund for spent nuclear fuel reprocessing. The electricity enterprise concerned must deposit a certain sum of money as a reserve fund which is the payment left over from spent fuel reprocessing at the end of a fiscal year minus the same at the end of the preceding year less a certain sum, when the former exceeds the latter. Then, concerning the remainder of the reserve fund in the preceding year, a certain sum must be subtracted from this reserve fund. (Mori, K.)

Spent fuel reprocessing options

International Nuclear Information System (INIS)

2008-08-01

The objective of this publication is to provide an update on the latest developments in nuclear reprocessing technologies in the light of new developments on the global nuclear scene. The background information on spent fuel reprocessing is provided in Section One. Substantial global growth of nuclear electricity generation is expected to occur during this century, in response to environmental issues and to assure the sustainability of the electrical energy supply in both industrial and less-developed countries. This growth carries with it an increasing responsibility to ensure that nuclear fuel cycle technologies are used only for peaceful purposes. In Section Two, an overview of the options for spent fuel reprocessing and their level of development are provided. A number of options exist for the treatment of spent fuel. Some, including those that avoid separation of a pure plutonium stream, are at an advanced level of technological maturity. These could be deployed in the next generation of industrial-scale reprocessing plants, while others (such as dry methods) are at a pilot scale, laboratory scale or conceptual stage of development. In Section Three, research and development in support of advanced reprocessing options is described. Next-generation spent fuel reprocessing plants are likely to be based on aqueous extraction processes that can be designed to a country specific set of spent fuel partitioning criteria for recycling of fissile materials to advanced light water reactors or fast spectrum reactors. The physical design of these plants must incorporate effective means for materials accountancy, safeguards and physical protection. Section four deals with issues and challenges related to spent fuel reprocessing. The spent fuel reprocessing options assessment of economics, proliferation resistance, and environmental impact are discussed. The importance of public acceptance for a reprocessing strategy is discussed. A review of modelling tools to support the

Decommissioning of nuclear facilities: COGEMA expertise devoted to UP1 reprocessing plant dismantling programme

International Nuclear Information System (INIS)

Gay, A.

2001-01-01

Over the last past decades, the French nuclear industry has acquired a great experience and know-how in the field of dismantling. Today this experience amounts to more than 200,000 hours. The fundamental aims within dismantling strategy are the same as for all nuclear facilities: minimising doses received by workers, minimising waste volume and adapting waste management to radioactivity levels, minimising costs. French experience is based on technologies which are currently used in nuclear maintenance facilities. Dismantling is a dynamic process especially in the field of decontamination (chemical and mechanical), cleaning, robotics and remote control operations. The strategy for the dismantling of former UP1 reprocessing plant is based on the feedback of experience gained through the dismantling of other facilities such as the AT1 workshop at La Hague. This workshop, a pilot plant for reprocessing of fast-breeder reactor fuels (Rapsodie and Phenix) has to be dismantled to IAEA level 3 (unrestricted site use), excluding civil works structures. Currently conducted by trained shifts, this dismantling project should end in 1999. The experience already acquired proves that chemical rinsings with the use of specific reagents is sufficient to decontaminate the hot cells and that the use of remote operations or robotics is not as important as previously envisaged. The UP1 reprocessing plant of Marcoule operated from 1958 to 1997. End of the operation was pronounced on the 31st of December 1997. 20,000 tons of spent fuels were reprocessed at UP1. The cleaning and dismantling operations at the Marcoule site depend upon the CEA, EDF and COGEMA. The Defence and Industry Ministries asked for a specific structure to be set up. An economic interest group called CODEM was created in May 1996. CODEM decides, finances and supervises dismantling operations, while respecting the constraints of nuclear safety, environmental protection and cost-effectiveness. The cleaning operations of

Nuclear energy without reprocessing: a future made possible by energy conservation

International Nuclear Information System (INIS)

Feiveson, Harold

1987-01-01

The achievements of energy conservation and the promise of future progress have rendered economically unattractive for many decades the separation of plutonium from spent reactor fuel (reprocessing) and its recycle into breeder or light water reactors. Despite this, reprocessing and recycle are already underway in Europe and Japan. If unchecked, these activities, by the end of the century, will lead to an annual flow in routine commerce of tens of thousands of kilograms of separated plutonium, a circumstance which would pose a grave threat to international security. However, continued stagnation of nuclear power programs in much of the world, due significantly to greatly reduced growth rates in electricity demand, will underscore the economic folly of reprocessing and recycle and may eventually encourage their abandonment. (author)

Cost probability analysis of reprocessing spent nuclear fuel in the US

International Nuclear Information System (INIS)

Recktenwald, G.D.; Deinert, M.R.

2012-01-01

The methods by which nuclear power's radioactive signature could be reduced typically require the reprocessing of spent nuclear fuel. However, economic assessments of the costs that are associated with doing this are subject to a high degree of uncertainty. We present a probabilistic analysis of the costs to build, operate and decommission the facilities that would be required to reprocess all US spent nuclear fuel generated over a one hundred year time frame, starting from a 2010 power production rate. The analysis suggests a total life-cycle cost of 2.11 ± 0.26 mills/kWh, with a 90% and 99% confidence that the overall cost would remain below 2.45 and 2.75 mills/kWh respectively. The most significant effects on cost come from the efficiency of the reactor fleet and the growth rate of nuclear power. The analysis shows that discounting results in life-cycle costs decreasing as recycling is delayed. However the costs to store spent fuel closely counter the effect of discounting when an intergenerational discount rate is used.

Export control guide: Spent nuclear fuel reprocessing and preparation of plutonium metal

International Nuclear Information System (INIS)

1993-10-01

The international Treaty on the Non-Proliferation of Nuclear Weapons, also referred to as the Non-Proliferation Treaty (NPT), states in Article III, paragraph 2(b) that open-quotes Each State Party to the Treaty undertakes not to provide . . . equipment or material especially designed or prepared for the processing, use or production of special fissionable material to any non-nuclear-weapon State for peaceful purposes, unless the source or special fissionable material shall be subject to the safeguards required by this Article.close quotes This guide was prepared to assist export control officials in the interpretation, understanding, and implementation of export laws and controls relating to the international Trigger List for irradiated nuclear fuel reprocessing equipment, components, and materials. The guide also contains information related to the production of plutonium metal. Reprocessing and its place in the nuclear fuel cycle are described briefly; the standard procedure to prepare metallic plutonium is discussed; steps used to prepare Trigger List controls are cited; descriptions of controlled items are given; and special materials of construction are noted. This is followed by a comprehensive description of especially designed or prepared equipment, materials, and components of reprocessing and plutonium metal processes and includes photographs and/or pictorial representations. The nomenclature of the Trigger List has been retained in the numbered sections of this document for clarity

Development of a real-time detection strategy for process monitoring during nuclear fuel reprocessing using the UREX+3a method

International Nuclear Information System (INIS)

Goddard, Braden; Charlton, William S.; McDeavitt, Sean M.

2010-01-01

Research highlights: → HPGe detectors are suitable for UREX+3a real-time spectroscopy. → HPGe N-type detectors may be suitable for a reprocessing facility. → Gamma ray self-shielding does not occur for pipe diameters less than 2 in. - Abstract: Reprocessing nuclear fuel is becoming more viable in the United States due to the anticipated increase in construction of nuclear power plants, the growing stockpile of existing used nuclear fuel, and a public desire to reduce the amount of this fuel. A new reprocessing facility will likely have state of the art controls and monitoring methods to safeguard special nuclear materials, as well as to provide real-time monitoring for process control. The focus of this research was to create a proof of concept to enable the development of a detection strategy that uses well established gamma and neutron measurement methods to characterize samples from the Uranium Extraction Plus 3a (UREX+3a) reprocessing method using a variety of detector types and measurement times. A facility that implemented real-time gamma detection equipment could improve product quality control and provide additional benefits, such as waste volume reduction. In addition to the spectral analyses, it was determined by Monte Carlo N Particle (MCNP) simulations that there is no noticeable self-shielding for internal pipe diameters less than 5.08 cm, indicating that no self-shielding correction factors are needed. Further, it was determined that High Purity Germanium (HPGe) N-type detectors have the high gamma ray energy resolution and neutron damage resistance that would be required in a reprocessing facility. Finally, the gamma ray spectra for the measured samples were simulated using MCNP and then the model was extended to predict the responses from an actual reprocessing scenario from UREX+3a applied to fuel that had a decay time of 3 years. The 3-year decayed fuel was more representative of commercially reprocessed fuel than the acquired UREX+3a

Requirements for near-real-time accounting of strategic nuclear materials in nuclear fuel reprocessing

International Nuclear Information System (INIS)

Hakkila, E.A.; Cobb, D.D.; Dietz, R.J.; Shipley, J.P.; Smith, D.B.

1978-01-01

A Purex-based nuclear fuel reprocessing plant has been studied for possible incorporation of near-real-time accounting to supplement conventional accounting procedures. Near-real-time accounting of special nuclear materials relies on in-line or at-line flow measurements and plutonium assay of product and waste streams, complemented by conventional analytical chemistry for daily instrument calibrations. In-line alpha monitors could be used for waste stream measurements of plutonium, even in the presence of high beta-gamma fluxes from fission products. X-ray absorption edge densitometry using either K- or L-absorption edges could be used for plutonium concentration measurements in main product streams. Some problem areas identified in waste stream measurements include measurements of leached hulls and of centrifuge sludge. Conventional analytical chemical methods for measuring plutonium in weapons grade material can be modified for reprocessed plutonium. Analytical techniques requiring special precautions will be reviewed

Summary of the seismic analyses of the Nuclear Fuel Services Reprocessing Plant at West Valley, New York

International Nuclear Information System (INIS)

Endebrock, E.G.

1978-03-01

Results are presented from the seismic investigations of the Nuclear Fuel Services Fuel Reprocessing Plant conducted by the Chemical Plants Division of Dravo Corporation (CPD), the Los Alamos Scientific Laboratory (LASL), and the Lawrence Livermore Laboratory (LLL). Results of the different analytical procedures are summarized. The LASL studies showed that structural distress would initially occur in two places, the building piles and the walls of the Mechanical Crane Room. This structural distress would occur at 0.14 g. The LLL investigation showed that the Liquid Waste Cell and the General Purpose Cell would start to show structural distress at 0.09g, and that lateral pile distress would begin at 0.11g

Nuclear fuel cycle: reprocessing. A bibliography

International Nuclear Information System (INIS)

Smith, L.B.

1982-12-01

This bibliography contains information on the reprocessing portion of the nuclear fuel cycle included in the Department of Energy's Energy Data Base from January 1981 through November 1982. The abstracts are grouped by subject category. Entries in the subject index also facilitate access by subject. Within each category the arrangement is by report number for reports, followed by nonreports in reverse chronological order. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

Nuclear fuel reprocessing deactivation plan for the Idaho Chemical Processing Plant, Revision 1

International Nuclear Information System (INIS)

Patterson, M.W.

1994-10-01

The decision was announced on April 28, 1992 to cease all United States Department of Energy (DOE) reprocessing of nuclear fuels. This decision leads to the deactivation of all fuels dissolution, solvent extraction, krypton gas recovery operations, and product denitration at the Idaho Chemical Processing Plant (ICPP). The reprocessing facilities will be converted to a safe and stable shutdown condition awaiting future alternate uses or decontamination and decommissioning (D ampersand D). This ICPP Deactivation Plan includes the scope of work, schedule, costs, and associated staffing levels necessary to achieve a safe and orderly deactivation of reprocessing activities and the Waste Calcining Facility (WCF). Deactivation activities primarily involve shutdown of operating systems and buildings, fissile and hazardous material removal, and related activities. A minimum required level of continued surveillance and maintenance is planned for each facility/process system to ensure necessary environmental, health, and safety margins are maintained and to support ongoing operations for ICPP facilities that are not being deactivated. Management of the ICPP was transferred from Westinghouse Idaho Nuclear Company, Inc. (WINCO) to Lockheed Idaho Technologies Company (LITCO) on October 1, 1994 as part of the INEL consolidated contract. This revision of the deactivation plan (formerly the Nuclear Fuel Reprocessing Phaseout Plan for the ICPP) is being published during the consolidation of the INEL site-wide contract and the information presented here is current as of October 31, 1994. LITCO has adopted the existing plans for the deactivation of ICPP reprocessing facilities and the plans developed under WINCO are still being actively pursued, although the change in management may result in changes which have not yet been identified. Accordingly, the contents of this plan are subject to revision

Evaluation of methods for seismic analysis of nuclear fuel reprocessing plants, part 1

International Nuclear Information System (INIS)

Tokarz, F.J.; Murray, R.C.; Arthur, D.F.; Feng, W.W.; Wight, L.H.; Zaslawsky, M.

1975-01-01

Currently, no guidelines exist for choosing methods of structural analysis to evaluate the seismic hazard of nuclear fuel reprocessing plants. This study examines available methods and their applicability to fuel reprocessing plant structures. The results of this study should provide a basis for establishing guidelines recommending methods of seismic analysis for evaluating future fuel reprocessing plants. The approach taken is: (1) to identify critical plant structures and place them in four categories (structures at or near grade; deeply embedded structures; fully buried structures; equipment/vessels/attachments/piping), (2) to select a representative structure in each of the first three categories and perform static and dynamic analysis on each, and (3) to evaluate and recommend method(s) of analysis for structures within each category. The Barnwell Nuclear Fuel Plant is selected as representative of future commercial reprocessing plants. The effect of site characteristics on the structural response is also examined. The response spectra method of analysis combined with the finite element model for each category is recommended. For structures founded near or at grade, the lumped mass model could also be used. If a time history response is required, a time-history analysis is necessary. (U.S.)

Status of nuclear fuel reprocessing, spent fuel storage, and high-level waste disposal. Nuclear Fuel Cycle Committee, California Energy Resources Conservation and Development Commission. Draft report

International Nuclear Information System (INIS)

Anon.

1978-01-01

An analysis of the current status of technologies and issues in the major portions of the back-end of the nuclear fuel cycle is presented. The discussion on nuclear fuel reprocessing covers the reprocessing requirement, reprocessing technology assessment, technology for operation of reprocessing plants, and approval of reprocessing plants. The chapter devoted to spent fuel storage covers the spent fuel storge problem, the legislative response, options for maintaining full core discharge capacity, prospective availability of alterntive storage options, and the outlook for California. The existence of a demonstrated, developed high-level waste disposal technology is reviewed. Recommendations for Federal programs on high-level waste disposal are made

Energies and media nr 30. Conditions for the nuclear sector. The fuel cycle and wastes. The usefulness of fuel reprocessing. Wastes

International Nuclear Information System (INIS)

2009-10-01

After some comments on recent events in the nuclear sector in different countries (energy policy and projects in the USA, Europe, China, India, Russia), this issue proposes some explanations on the nuclear fuel cycle and on nuclear wastes: involved processes and products from mining to reprocessing and recycling, usefulness of reprocessing (future opportunities of fast neutron reactors, present usefulness of reprocessing with the recycling of separated fissile materials), impact of reprocessing on the environment in La Hague (gas and liquid releases, release standard definition), and the destiny of wastes

Electrochemical reprocessing of nuclear fuels

International Nuclear Information System (INIS)

Brambilla, G.; Sartorelli, A.

1980-01-01

A method is described for the reprocessing of irradiated nuclear fuel which is particularly suitable for use with fuel from fast reactors and has the advantage of being a dry process in which there is no danger of radiation damage to a solvent medium as in a wet process. It comprises the steps of dissolving the fuel in a salt melt under such conditions that uranium and plutonium therein are converted to sulphate form. The plutonium sulphate may then be thermally decomposed to PuO 2 and removed. The salt melt is then subjected to electrolysis conditions to achieve cathodic deposition of UO 2 (and possibly PuO 2 ). The salt melt can then be recycled or conditioned for final disposal. (author)

Reprocessing

International Nuclear Information System (INIS)

Couture, J.; Rougeau, J.-P.

1987-01-01

The course of development of a comprehensive nuclear power industry has its own pace which implies the timely progressive and consistent mastery of each industrial step. In the nuclear fuel it is not surprising that the back-end services have lastly reached the industrial stage. In France, we have now fully completed the industrial demonstration of the closed fuel cycle. Our experience covers all necessary steps : transportation of spent fuel, storage, reprocessing, waste conditioning, recovered uranium recycling, plutonium recycling in thermal MOX fuels, plutonium-based fuel for FBR. While FBR development is a long term target, recycling of fissile materials in present LWR reactors appears to be a source of noticable savings. In the meantime rational management of waste material is the key for increased safety and better environment protection. Reprocessing activity is certainly the major achievement of the back-end strategy. The proven efficiency of this technique as it is implemented at La Hague facility gives the full assurance of a smooth operation of the under completion UP3 unit. The base-load management system which applies during the first ten years of its operation will make possible a noticable reduction of the commercial price for reprocessing services by the end of the century. Industrial maturity being confirmed, economic maturity is now the outstanding merit of the reprocessing and recycling strategy. It is a permanent challenge, to which the response is definitely positive in the sense of reducing the nuclear KWh production cost. (author)

Chemical analysis used in nuclear fuels reprocessing of uranium and thorium

International Nuclear Information System (INIS)

Schvartzman, M.M.A.M.

1986-01-01

An overall review of the analytical chemistry in nuclear fuel reprocessing is done. In Purex and Thorex process flowsheets, the analyses required to the control of the process, balance and accountability of fissile and fertile materials, and final product specification are pointed out. Some analytical methods applied to the determination of uranium, plutonium, thorium, nitric acid, tributylphosphate and fission products are described. Specific features of the analytical laboratories are presented. The radioactivity level of the samples requires facilities as shielded cells and glove boxes, and handling by remote control. Finally it is reported an application of one analytical method to evaluate thorium content in organic and aqueous solutions, in cold tests of Thorex process. These tests were performed at CDTN/NUCLEBRAS. (author) [pt

Laser-enhanced chemical reactions and the liquid state. II. Possible applications to nuclear fuel reprocessing

International Nuclear Information System (INIS)

DePoorter, G.L.; Rofer-DePoorter, C.K.

1976-01-01

Laser photochemistry is surveyed as a possible improvement upon the Purex process for reprocessing spent nuclear fuel. Most of the components of spent nuclear fuel are photochemically active, and lasers can be used to selectively excite individual chemical species. The great variety of chemical species present and the degree of separation that must be achieved present difficulties in reprocessing. Lasers may be able to improve the necessary separations by photochemical reaction or effects on rates and equilibria of reactions

General criteria for the project of nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

1979-01-01

Recommendations are presented establishing the general criteria for the project of nuclear fuel reprocessing plants to be licensed according to the legislation in effect. They apply to all the plant's systems, components and structures which are important to operation safety and to the public's health and safety. (F.E.) [pt

Steel construction in the nuclear reprocessing industry

International Nuclear Information System (INIS)

Jordan, G.W.

1990-01-01

Over the past decade British Nuclear Fuels plc (BNFL) has pursued a large capital expenditure programme at Sellafield in Cumbria. This has used large quantities of structural steelwork. For example, Thorp plant for reprocessing spend AGR and LWR fuels, due for completion in 1992, has 20,000 tonnes. The design of these plants has been entrusted to BNFL Engineering based at Risley near Warrington, England. These safety-related structures are designed, as required by the Nuclear Installations Inspectorate, to withstand the effects of environmental hazards such as extremes of earthquake, wind, temperature, ice, snow, flooding, and lightning strikes. In some cases they may be subjected to impact loading from possible mishandling of lifted loads such as fuel transportation flasks. Design criteria for these structures have been developed by BNFL Engineering. Some examples are mentioned. (author)

Reprocessing of spent fuel and public acceptance

International Nuclear Information System (INIS)

Imai, Ryukichi

1977-01-01

The public acceptance has to be considered regarding whole atomic power rather than the reprocessing of nuclear fuel separately, and the problems concerned are as follows; the release of radioactive materials in the normal and abnormal operations of reprocessing plants, the disposal of wastes with high level radioactivity, the transportation of high level radioactive material, the relation to the economic activity near nuclear plants, the environmental effect of 85 Kr. and 3 H, etc., and the physical protection for reprocessing facility itself, the special handling of the materials of very high radioactivity level such as fission products and plutonium, the radiation exposure of operators, and the demonstration of reprocessing techniques of commercial base, etc., as a part of the nuclear fuel cycle, and the relation between atomic power and other technologies in energy supply, the evalution of atomic power as the symbol of huge scale science, and the energy problem within the confrontation of economic development and the preservation of environment and resources regarding whole nuclear energy. The situations of fuel reprocessing in USA, UK, France, Germany and Japan are explained from the viewpoint of the history. The general background for the needs of nuclear energy in Japan, the image of nuclear energy and fuel reprocessing entertained by the general public, and the special feature of reprocessing techniques are described. (Nakai, Y.)

Experience and prospects in reprocessing

International Nuclear Information System (INIS)

Rougeau, J.-P.

1997-01-01

Reprocessing nuclear fuels is a long and successful industrial story. For decades, commercial reprocessing plants have been operating in France, the United Kingdom and Japan. The industrial outcome is clear and widely recognized: thousand tons of spent fuels have been reprocessed in these plants. Over the years, these facilities have been adapted to new types of fuel. Thus, the nuclear industry has fully demonstrated its ability to cope with technological change and its capacity to adapt itself to improvements. For decades, technical capability has been stressed and emphasized by nuclear industrial leaders as the most important point. This is no longer the case. Today the industry has to face a new commercial reality and to find the most adaptable answer to the utilities' requirements. This paper presents the current achievements and medium and long-term trends of the nuclear reprocessing activity, the ongoing commercial changes and gives an outlook for future evolutions. International political factors will also be examined. (author)

The reprocessing-recycling of spent nuclear fuel. Actinides separation - Application to wastes management

International Nuclear Information System (INIS)

2008-01-01

After its use in the reactor, the spent fuel still contains lot of recoverable material for an energetic use (uranium, plutonium), but also fission products and minor actinides which represent the residues of nuclear reactions. The reprocessing-recycling of the spent fuel, as it is performed in France, implies the chemical separation of these materials. The development and the industrial implementation of this separation process represent a major contribution of the French science and technology. The reprocessing-recycling allows a good management of nuclear wastes and a significant saving of fissile materials. With the recent spectacular rise of uranium prices, this process will become indispensable with the development of the next generation of fast neutron reactors. This book takes stock of the present and future variants of the chemical process used for the reprocessing of spent fuels. It describes the researches in progress and presents the stakes and recent results obtained by the CEA. content: the separation of actinides, a key factor for a sustainable nuclear energy; the actinides, a discovery of the 20. century; the radionuclides in nuclear fuels; the aquo ions of actinides; some redox properties of actinides; some complexing properties of actinide cations; general considerations about treatment processes; some characteristics of nuclear fuels in relation with their reprocessing; technical goals and specific constraints of the PUREX process; front-end operations of the PUREX process; separation and purification operations of the PUREX process; elaboration of finite products in the framework of the PUREX process; management and treatment of liquid effluents; solid wastes of the PUREX process; towards a joint management of uranium and plutonium: the COEX TM process; technical options of treatment and recycling techniques; the fuels of generation IV reactors; front-end treatment processes of advanced fuels; hydrometallurgical processes for future fuel cycles

Turning point of U.S. government decision in US-Japan nuclear fuel reprocessing negotiation in 1977

International Nuclear Information System (INIS)

Izumi, Yoshinori

2010-01-01

U.S. President Carter's Nuclear Nonproliferation Policy, announced in April 1977, which terminated federal funding for reprocessing, was a shock to the Atomic Energy Authority of the Japanese Government that had promoted the construction of Tokai Reprocessing Plant (TRP). After that, it became necessary to negotiate the 'Joint Determination for the Effective Safeguardability of TRP' subject to the 1968 Agreement for cooperation between the Government of Japan and the Government of the United States of America concerning civil use of Atomic Energy. Negotiations for the 'Joint Determination for the Effective Safguardability of TRP' were conducted in the U.S.-Japan Nuclear Fuel Reprocessing Negotiation and Joint Field Work meetings from April to September 1977. Both governments agreed to the TRP operation's terms and conditions including 'Joint Determination for the Effective Safeguardability of TRP' in the third negotiation. In spite of the hard position on reprocessing stated in the Nuclear Nonproliferation Policy enacted by President Carter, these negotiations concluded accepting the operation of TRP with condition. In this paper, I will explore the reasons for the abovementioned political decision by the U.S. government based on its disclosure documents. (author)

Mine... electricity... reprocessing... Nuclear energy, how and why? Second edition

International Nuclear Information System (INIS)

Grisez, F.

2003-01-01

This book makes a short and consistent synthesis of nuclear power: how electricity can be generated by braking up atoms and what is the advantage of this mean with respect to the use of fossil fuels or renewable energy sources. Beside the text, this book contains transparency-like illustrations which give a general overview of the civil nuclear domain. Content: 1 - introduction; 2 - radioactivity and nuclear safety: natural and artificial atoms, radioactivity, exposure, nuclear safety; 3 - nuclear fuel cycle: uranium mines and yellow cake, uranium conversion, uranium enrichment, fuel fabrication, nuclear power plants, reprocessing, recycling and conditioning, wastes, statuses, needs, companies and industrial capacities, R and D; 4 - energy consumption; 5 - what energy sources for even more electricity: available energies, environmental impact and accidents, costs of electricity, energy reserves, summary, opinions and conclusions. (J.S.)

Fuel reprocessing/fabrication interface

International Nuclear Information System (INIS)

Benistan, G.; Blanchon, T.; Galimberti, M.; Mignot, E.

1987-01-01

EDF has conducted a major research, development and experimental programme concerning the recycling of plutonium and reprocessed uranium in pressurized water reactors, in collaboration with its major partners in the nuclear fuel cycle industry. Studies already conducted have demonstrated the technical and economic advantages of this recycling, as also its feasibility with due observance of the safety and reliability criteria constantly applied throughout the industrial development of the nuclear power sector in France. Data feedback from actual experience will make it possible to control the specific technical characteristics of MOX and reprocessed uranium fuels to a higher degree, as also management, viewed from the economic standpoint, of irradiated fuels and materials recovered from reprocessing. The next step will be to examine the reprocessing of MOX for reprocessed uranium fuels, either for secondary recycling in the PWR units, or, looking further ahead, in the fast breeders or later generation PWR units, after a storage period of a few years

Example of material accounting and verification of reprocessing input

International Nuclear Information System (INIS)

Koch, L.; Schoof, S.

1981-01-01

An example is described in this paper of material accounting at the reprocessing input point. Knowledge of the fuel history and chemical analyses of the spent fuel permitted concepts to be tested which have been developed for the determination of the input by the operator and for its verification by nuclear material safeguards with the intention of detecting a protracted as well as an abrupt diversion. Accuracies obtained for a material balance of a PWR fuel reprocessing campaign are given. 6 refs

Pyrolytic electrochemical process for the reprocessing of irradiated nuclear fuels

International Nuclear Information System (INIS)

Brambilla, G.; Sartorelli, A.

1980-01-01

The reprocessing is aimed at synthetic UO 2 -PuO 2 mixed oxides, UC-PuC mixed carbides and at oxides and carbides of U, Pu and Th from fast nuclear reactors. The nuclear fuel is dissolved in a salt melting bath. The conversion of the Pu(SO 4 ) 2 is done thermally and that of UO 2 is done electrolytically. The molten salts are returned to the input of the process and the fission products and the molten salts are conditioned. (DG) [de

A review of liquor transfer systems for use in nuclear reprocessing plants

International Nuclear Information System (INIS)

Singh, J.

1982-01-01

Liquor pumping systems for use in nuclear fuel reprocessing plants are described. Comparison of the operating characteristics and system constants are made between the air lift/Vacuum Operated Slug Lift, power fluidics and ejector pump systems. (author)

Analysis of nuclear proliferation resistance reprocessing and recycling technologies

International Nuclear Information System (INIS)

Paviet-Hartmann, Patricia; Cerefice, Gary; Stacey, Marcela; Bakhtiar, Steven

2011-01-01

The PUREX process has been progressively and continuously improved during the past three decades, and these improvements account for successful commercialization of reprocessing in a few countries. The renewed interest in nuclear energy and the international growth of nuclear electricity generation do not equate - and should not be equated - with increasing proliferation risks. Indeed, the nuclear renaissance presents a unique opportunity to enhance the culture of non-proliferation. With the recent revival of interest in nuclear technology, technical methods for prevention of nuclear proliferation are being revisited. Robust strategies to develop new advanced separation technologies are emerging worldwide for sustainability and advancement of nuclear energy with enhanced proliferation resistance. On the other hand, at this moment, there are no proliferation resistance advanced technologies. Until now proliferation resistance as it applies to reprocessing has been focused on not separating a pure stream of weapons-usable plutonium. France, as an example, has proposed a variant of the PUREX process, the COEX TM process, which does not result on a pure plutonium product stream. A further step is to implement a process based on group extraction of actinides and fission products associated with a homogeneous recycling strategy (UNEX process in the US, GANEX process in France). Such scheme will most likely not be deployable on an industrial scale before 2030 or so because it requires intensive R and D and robust flowsheets. Finally, future generation recycling schemes will handle the used nuclear fuel in fast neutron reactors. This means that the plutonium throughput of the recycling process may increase. The need is obvious for advanced aqueous recycling technologies that are intrinsically more proliferation resistant than the commercial PUREX process. In this paper, we review the actual PUREX process along with the advanced recycling technologies that will enhance

Analysis of nuclear proliferation resistance reprocessing and recycling technologies

Energy Technology Data Exchange (ETDEWEB)

Patricia Paviet-Hartmann; Gary Cerefice; Marcela Stacey; Steven Bakhtiar

2011-05-01

The PUREX process has been progressively and continuously improved during the past three decades, and these improvements account for successful commercialization of reprocessing in a few countries. The renewed interest in nuclear energy and the international growth of nuclear electricity generation do not equate – and should not be equated -with increasing proliferation risks. Indeed, the nuclear renaissance presents a unique opportunity to enhance the culture of non-proliferation. With the recent revival of interest in nuclear technology, technical methods for prevention of nuclear proliferation are being revisited. Robust strategies to develop new advanced separation technologies are emerging worldwide for sustainability and advancement of nuclear energy with enhanced proliferation resistance. On the other hand, at this moment, there are no proliferation resistance advanced technologies. . Until now proliferation resistance as it applies to reprocessing has been focused on not separating a pure stream of weapons-usable plutonium. France, as an example, has proposed a variant of the PUREX process, the COEX TM process, which does not result on a pure plutonium product stream. A further step is to implement a process based on group extraction of actinides and fission products associated with a homogeneous recycling strategy (UNEX process in the US, GANEX process in France). Such scheme will most likely not be deployable on an industrial scale before 2030 or so because it requires intensive R&D and robust flowsheets. Finally, future generation recycling schemes will handle the used nuclear fuel in fast neutron reactors. This means that the plutonium throughput of the recycling process may increase. The need is obvious for advanced aqueous recycling technologies that are intrinsically more proliferation resistant than the commercial PUREX process. In this paper, we review the actual PUREX process along with the advanced recycling technologies that will enhance

The importance of nuclear fuel reprocessing

International Nuclear Information System (INIS)

Allday, C.

1977-01-01

The subject is discussed under the following main headings: introduction; world energy requirement; energy conservation and the economics of recycle; environmental considerations and the timescale of reprocessing; and problems associated with reprocessing. It is concluded that reprocessing is essential to the conservation of the world's energy resources and is an environmentally and probably an economically more acceptable option to the 'throw away' alternative. The associated problems of proliferation and terrorism, although of the utmost importance, can and will be solved. (U.K.)

Fuel reprocessing at THORP: profitability and public liabilities

International Nuclear Information System (INIS)

Berkhout, F.

1992-01-01

Since the economics of British Nuclear Fuels Limited's (BNFL) Thermal Oxide Reprocessing Plant (THORP) were analysed in an earlier report, a number of domestic and international developments have affected the prospects for THORP. The present report outlines these changes, and analyses their implications for the profits and public liabilities associated with the project. Timing is of some significance because once THORP becomes radioactive (planned to occur in March 1993) the bill for decommissioning the plant will rise from a trivial sum to a very large one - Pound 900 million (1992 prices) in BNFL's own estimates. The report begins with a brief outline of reprocessing and the THORP project. It then examines the market prospects for reprocessing beyond THORP's first ten years and revises BNFL's own projections. It then considers the potential profitability of THORP in relation to various possible cost increases and finally outlines the possible implications of different THORP scenarios for the public purse. (author)

Reprocessing the truth

International Nuclear Information System (INIS)

Goldsmith, E.; Bunyard, P.; Hildyard, N.

1978-01-01

Comments are made on the Report by the Inspector, Mr. Justice Parker, after the public inquiry into the application by British Nuclear Fuels Limited for permission to construct and operate a thermal oxide reprocessing plant at their Windscale works. Particular questions raised include: corrosion or storage of spent fuel, vitrification of radioactive waste; radiation effects, and permissible levels; radioactive emissions, critical groups and critical pathways; risks; reprocessing economics; commitment to the FBR; sociological aspects, including employment, nuclear weapon proliferation and terrorism, and Britain's moral responsibilities. (U.K.)

Reprocessing of spent nuclear fuels in OECD countries

International Nuclear Information System (INIS)

1977-01-01

This report deals with the adequacy of projected reprocessing capacity, the short-term measures proposed in view of the lack of sufficient reprocessing capacity, the longer term measures proposed in view of the lack of sufficient reprocessing capacity, the alternatives to reprocessing and the cooperative arrangements

Technical aspects of fuel reprocessing

International Nuclear Information System (INIS)

Groenier, W.S.

1982-02-01

The purpose of this paper is to present a brief description of fuel reprocessing and some present developments which show the reliability of nuclear energy as a long-term supply. The following topics are discussed: technical reasons for reprocessing; economic reasons for reprocessing; past experience; justification for advanced reprocessing R and D; technical aspects of current reprocessing development. The present developments are mainly directed at the reprocessing of breeder reactor fuels but there are also many applications to light-water reactor fuel reprocessing. These new developments involve totally remote operation, and maintenance. To demonstrate this advanced reprocessing concept, pilot-scale demonstration facilities are planned with commercial application occurring sometime after the year 2000

A review of reprocessing, partitioning, and transmutation of spent nuclear fuel and the implications for Canada

International Nuclear Information System (INIS)

Jackson, D.P.

2006-01-01

The current status of the reprocessing, partitioning, and transmutation of used nuclear fuel are reviewed in the context of assessing the possible application of these technologies to used CANDU fuel. The status of commercial reprocessing is briefly surveyed and recent progress in world R and D programs on the transmutation of FP's and actinides using Accelerator Driven Systems is summarized. The implications of reprocessing for Canada are explored from the point of view of a long strategy for managing used CANDU fuel in terms of the costs of initiating reprocessing domestically at some time in the future including public and occupational radiation doses, and the wastes generated. (author)

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

International Nuclear Information System (INIS)

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

1984-08-01

The risks involved in the routine release of 85 Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of 85 Kr. Instead of releasing the 85 Kr to the environment when fuel is reprocessed, it can be captured, immobilized and stored. Two alternative methods of capturing 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 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 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 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 3 H and 14 C also encourage delaying implementation of the 85 Kr recovery in the early plants

Reprocessing of nuclear fuels

International Nuclear Information System (INIS)

Hatfield, G.W.

1960-11-01

One of the persistent ideas concerning nuclear power is that the fuel costs are negligible. This, of course, is incorrect and, in fact, one of the major problems in the development of economic nuclear power is to get the cost of the fuel cycles down to an acceptable level. The irradiated fuel removed from the nuclear power reactors must be returned as fresh fuel into the system. Aside from the problems of handling and shipping involved in the reprocessing cycles, the two major steps are the chemical separation and the refabrication. The chemical separation covers the processing of the spent fuel to separate and recover the unburned fuel as well as the new fuel produced in the reactor. This includes the decontamination of these materials from other radioactive fission products formed in the reactor. Refabrication involves the working and sheathing of recycled fuel into the shapes and forms required by reactor design and the economics of the fabrication problem determines to a large extent the quality of the material required from the chemical treatment. At present there appear to be enough separating facilities in the United States and the United Kingdom to handle the recycling of fuel from power reactors for the next few years. However, we understand the costs of recycling fuel in these facilities will be high or low depend ing on whether or not the capital costs of the plant are included in the processing cost. Also, the present plants may not be well adapted to carry out the chemical processing of the very wide variety of power reactor fuel elements which are being considered and will continue to be considered over the years to come. (author)

Spent nuclear fuel reprocessing and international law. Germany's obligations under international law in matters of spent fuel reprocessing and the relevant contracts concluded with France and the United Kingdom

International Nuclear Information System (INIS)

Heintschel v Heinegg, W.

1999-01-01

The review presented is an excerpt from an expert opinion written by the author in December last year, in response to changes in nuclear energy policy announced by the new German government. The reprocessing of spent nuclear fuels from German power reactors in the reprocessing facilities of France (La Hague) and the UK (Sellafield) is not only based on contracts concluded by the German electric utilities and the French COGEMA or the British BNFL, but has been agreed as well by an exchange of diplomatic notes between the French Ministry of Foreign Affairs and the German ambassador in Paris, the German Foreign Ministry and the French ambassador as well as the British ambassador in Bonn. The article therefore first examines from the angle of international law the legal obligations binding the states involved, and Germany in particular, in matters of spent fuel reprocessing contracts. The next question arising in this context and discussed by the article is that of whether and how much indemnification can be demanded by the reprocessing companies, or their governments, resp., if Germany should discontinue spent fuel reprocessing and thus might be made liable for breach of the bilateral agreements. (orig/CB) [de

Operating experience in reprocessing

International Nuclear Information System (INIS)

Schueller, W.

1983-01-01

Since 1953, reprocessing has accumulated 180 years of operating experience in ten plants, six of them with 41 years of operation in reprocessing oxide fuel from light water reactors. After abortive, premature attempts at what is called commercial reprocessing, which had been oriented towards the market value of recoverable uranium and plutonium, non-military reprocessing technologies have proved their technical feasibility, since 1966 on a pilot scale and since 1976 on an industrial scale. Reprocessing experience obtained on uranium metal fuel with low and medium burnups can now certainly be extrapolated to oxide fuel with high burnup and from pilot plants to industrial scale plants using the same technologies. The perspectives of waste management of the nuclear power plants operated in the Federal Republic of Germany should be viewed realistically. The technical problems still to be solved are in a balanced relationship to the benefit arising to the national economy out of nuclear power generation and can be solved in time, provided there are clearcut political boundary conditions. (orig.) [de

Reprocessing of spent nuclear fuel; Prerada isluzenog nuklearnog goriva

Energy Technology Data Exchange (ETDEWEB)

Gal, I [Institute of Nuclear Sciences Boris Kidric, Laboratorija za hemiju visoke aktivnosti, Vinca, Beograd (Serbia and Montenegro)

1964-12-15

This volume contains the following reports: Experimental facility for testing and development of pulsed columns and auxiliary devices; Chemical-technology study of the modified 'Purex' process; Chemical and radiometric control analyses; Chromatographic separation of rare earth elements on paper treated by di-n butylphosphate; Preliminary study of some organic nitrogen extracts significant in fuel reprocessing.

Possible toxic effects from the nuclear reprocessing at Sellafield and Cap de la Hague

Energy Technology Data Exchange (ETDEWEB)

Schneider, M.; Coeytaux, X.; Faid, Y.B.; Marignac, Y.; Rouy, E. [Wise, 75 - Paris (France); Thompson, G. [IRSS, Cambridge (United States); Fairlie, I.; Lowry, D.; Sumner, D

2001-11-15

The principal aim of this report is to assist the Committee of Petitions of the European Parliament in its consideration of Petition 393/95 brought by Dr. W. Nachtwey. The Petition expresses concerns about radioactive discharges from nuclear reprocessing plants at Sellafield in the UK and La Hague in France, and their possible adverse health effects. Six years after the Petition was introduced, the Petitioner main concerns remain relevant. This report concludes that reprocessing discharges are a valid matter for the Committee consideration. It also concludes that, on balance, the Petitioner's concerns over radioactive discharges from Sellafield and La Hague are justified. The report presents evidence and data on: 1) radioactive discharges from the Sellafield and La Hague sites; 2) resulting nuclide concentrations in environmental media including foodstuffs; 3) radiation doses from nuclide discharges to critical groups near the sites; 4) adverse health effects near the two sites; and 5) resulting collective doses from nuclide discharges. The report also examines a number of current issues in radiobiology concerning health effects from exposure to ionising radiation, in particular genetic and in utero effects. In addition, in accordance with contract specifications, the report examines other major factors that might influence future decision-making on reprocessing. It provides information on the legal framework, the operational history of the plants and the economic case for reprocessing compared with available alternatives for spent nuclear fuel management. The report also makes policy-related recommendations that take into account current knowledge and uncertainties in risk assessment and the availability of alternatives to reprocessing in spent fuel management. (authors)

Possible toxic effects from the nuclear reprocessing at Sellafield and Cap de la Hague

International Nuclear Information System (INIS)

Schneider, M.; Coeytaux, X.; Faid, Y.B.; Marignac, Y.; Rouy, E.; Thompson, G.; Fairlie, I.; Lowry, D.; Sumner, D.

2001-11-01

The principal aim of this report is to assist the Committee of Petitions of the European Parliament in its consideration of Petition 393/95 brought by Dr. W. Nachtwey. The Petition expresses concerns about radioactive discharges from nuclear reprocessing plants at Sellafield in the UK and La Hague in France, and their possible adverse health effects. Six years after the Petition was introduced, the Petitioner main concerns remain relevant. This report concludes that reprocessing discharges are a valid matter for the Committee consideration. It also concludes that, on balance, the Petitioner's concerns over radioactive discharges from Sellafield and La Hague are justified. The report presents evidence and data on: 1) radioactive discharges from the Sellafield and La Hague sites; 2) resulting nuclide concentrations in environmental media including foodstuffs; 3) radiation doses from nuclide discharges to critical groups near the sites; 4) adverse health effects near the two sites; and 5) resulting collective doses from nuclide discharges. The report also examines a number of current issues in radiobiology concerning health effects from exposure to ionising radiation, in particular genetic and in utero effects. In addition, in accordance with contract specifications, the report examines other major factors that might influence future decision-making on reprocessing. It provides information on the legal framework, the operational history of the plants and the economic case for reprocessing compared with available alternatives for spent nuclear fuel management. The report also makes policy-related recommendations that take into account current knowledge and uncertainties in risk assessment and the availability of alternatives to reprocessing in spent fuel management. (authors)

Deactivating a major nuclear fuels reprocessing facility

International Nuclear Information System (INIS)

LeBaron, G.J.

1997-01-01

This paper describes three key processes used in deactivating the Plutonium Uranium Extraction (PUREX) Facility, a large, complex nuclear reprocessing facility, 15 months ahead of schedule and $77 million under budget. The organization was reengineered to refine its business processes and more effectively organize around the deactivation work scope. Multi-disciplined work teams were formed to be self-sufficient and empowered to make decisions and perform work. A number of benefits were realized by reengineering. A comprehensive process to develop end points which clearly identified specific results and the post-project facility configuration was developed so all areas of a facility were addressed. Clear and specific end points allowed teams to focus on completing deactivation activities and helped ensure there were no unfulfilled end-of-project expectations. The RCRA regulations require closure of permitted facilities within 180 days after cessation of operations which may essentially necessitate decommissioning. A more cost effective approach was adopted which significantly reduced risk to human health and the environment by taking the facility to a passive, safe, inexpensive-to-maintain surveillance and maintenance condition (deactivation) prior to disposition. PUREX thus became the first large reprocessing facility with active TSD [treatment, storage, and disposal] units to be deactivated under the RCRA regulations

Available reprocessing and recycling services for research reactor spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Tozser, Sandor Miklos; Adelfang, Pablo; Bradley, Ed [International Atomic Energy Agency, Vienna (Austria); Budu, Madalina [SOSNY Research and Development Company, Moscow (Russian Federation); Chiguer, Mustapha [AREVA, Paris (France)

2015-05-15

International activities in the back-end of the research reactor (RR) fuel cycle have so far been dominated by the programmes of acceptance of highly-enriched uranium (HEU) spent nuclear fuel (SNF) by the country where it was originally enriched. These programmes will soon have achieved their goals and the SNF take-back programmes will cease. However, the needs of the nuclear community dictate that the majority of the research reactors continue to operate using low enriched uranium (LEU) fuel in order to meet the varied mission objectives. As a result, inventories of LEU SNF will continue to be created and the back-end solution of RR SNF remains a critical issue. In view of this fact, the IAEA, based on the experience gained during the decade of international cooperation in supporting the objectives of the HEU take-back programmes, will draw up a report presenting available reprocessing and recycling services for research reactor spent nuclear fuel. This paper gives an overview of the guiding document which will address all aspects of Reprocessing and Recycling Services for RR SNF, including an overview of solutions, decision making support, service suppliers, conditions (prerequisites, options, etc.), services offered by the managerial and logistics support providers with a focus on available transport packages and applicable transport modes.

An analysis of development and research on spent nuclear fuel reprocessing

International Nuclear Information System (INIS)

Borges Silverio, Leticia; Queiroz Lamas, Wendell de

2011-01-01

Nuclear energy comes back to the discussions on the world stage as an energy source that does not contribute to global warming during production process. It can be chosen as the main source of power generation in some countries or complement the energy matrix in others. In this context, there is the need to develop new technologies for the management of radioactive waste generated by the production process. Final repositories for spent fuel are not yet in commercial operation, and techniques for fuel reprocessing have been developed, because after use, the fuel still has materials that produce energy. Some countries already use reprocessing, and develop research to make it more secure and more competitive, while others prefer to adopt policies to prevent developments in this area due to the problem of nuclear proliferation. In another line of research, new reactors are being developed in order to reduce the amount of waste in energy production and some will be designed to work in closed loop, recycling the materials generated.

An analysis of development and research on spent nuclear fuel reprocessing

Energy Technology Data Exchange (ETDEWEB)

Borges Silverio, Leticia; Lamas, Wendell de Queiroz [University of Taubate, Postgraduate Programme in Mechanical Engineering, Rua Daniel Danelli, s/n, Jd. Morumbi, Taubate, SP 12060-440 (Brazil)

2011-01-15

Nuclear energy comes back to the discussions on the world stage as an energy source that does not contribute to global warming during production process. It can be chosen as the main source of power generation in some countries or complement the energy matrix in others. In this context, there is the need to develop new technologies for the management of radioactive waste generated by the production process. Final repositories for spent fuel are not yet in commercial operation, and techniques for fuel reprocessing have been developed, because after use, the fuel still has materials that produce energy. Some countries already use reprocessing, and develop research to make it more secure and more competitive, while others prefer to adopt policies to prevent developments in this area due to the problem of nuclear proliferation. In another line of research, new reactors are being developed in order to reduce the amount of waste in energy production and some will be designed to work in closed loop, recycling the materials generated. (author)

Corrosion control in nuclear fuel reprocessing

International Nuclear Information System (INIS)

Steele, D.F.

1986-01-01

This article looks in detail at tribology-related hazards of corrosion in irradiated fuel reprocessing plants and tries to identify and minimize problems which could contribute to disaster. First, the corrosion process is explained. Then the corrosion aspects at each of four stages in reprocessing are examined, with particular reference to oxide fuel reprocessing. The four stages are fuel receipt and storage, fuel breakdown and dissolution, solvent extraction and product concentration and waste management. Results from laboratory and plant corrosion trails are used at the plant design stage to prevent corrosion problems arising. Operational procedures which minimize corrosion if it cannot be prevented at the design stage, are used. (UK)

Worldwide reprocessing supply and demand

International Nuclear Information System (INIS)

Pinto, S.

1987-01-01

The aim of this paper is to broadly examine the current situation in the LWR fuel reprocessing services market on a worldwide basis through 2010. The main factors influencing this market (nuclear programs, fuel discharges, reprocessing capacities, buyer philosophies, etc.) are identified in the paper and the most important are highlighted and discussed in more detail. Emphasis has been placed on the situation with respect to reprocessing in those countries having a significant influence on the reprocessing market

Power Reactor Fuel Reprocessing Plant-1: a stepping stone in Indian PHWR spent fuel reprocessing

International Nuclear Information System (INIS)

Pradhan, Sanjay; Dubey, K.; Qureshi, F.T.; Lokeswar, S.P.

2017-01-01

India has low reserves of uranium and high reserves of thorium. In order to optimize resource utilization India has adopted a closed fuel cycle to ensure long-term energy security. The optimum resource utilization is feasible only by adopting reprocessing, conditioning and recycle options. It is very much imperative to view spent fuel as a vital resource material and not a waste to be disposed off. Thus, spent nuclear fuel reprocessing forms an integral part of the Indian Nuclear Energy Programme. Aqueous reprocessing based on PUREX technology is in use for more than 50 years and has reached a matured status

Corrosion resistance of metallic materials for use in nuclear fuel reprocessing

International Nuclear Information System (INIS)

Legry, J.P.; Pelras, M.; Turluer, G.

1989-01-01

This paper reviews the corrosion resistance properties required from metallic materials to be used in the various developments of the PUREX process for nuclear fuel reprocessing. Stainless steels, zirconium or titanium base alloys are considered for the various plant components, where nitric acid is the main electrolyte with differing acid and nitrate concentrations, temperature and oxidizing species. (author)

Available reprocessing and recycling services for research reactor spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Tozser, Sandor; Marshall, Frances M.; Adelfang, Pablo; Bradley, Edward [International Atomic Energy Agency, Vienna (Austria); Budu, Madalina Elena [SOSNY Research and Development Company, Moscow (Russian Federation); Chiguer, Mustapha [AREVA, Paris La Defense (France)

2016-03-15

International activities in the back end of the research reactor (RR) fuel cycle have so far been dominated by the programmes of acceptance of highly-enriched uranium (HEU) spent nuclear fuel (SNF) by the country where it was originally enriched. In the future inventories of LEU SNF will continue to be created and the back end solution of RR SNF remains a critical issue. The IAEA, based on the experience gained during the decade of international cooperation in supporting the objectives of the HEU take-back programmes, drew up a report presenting available reprocessing and recycling services for RR SNF. This paper gives an overview of the report, which will address all aspects of reprocessing and recycling services for RR SNF.

The regulations concerning the reprocessing business of spent fuels

International Nuclear Information System (INIS)

1981-01-01

This rule is stipulated under the provisions of reprocessing business in the law concerning regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and to execute them. Basic terms are defined, such as exposure radiation dose, cumulative dose, control area, security area, surrounding monitoring area, worker, radioactive waste and facility for discharging into the sea. The application for the designation for reprocessing business under the law shall include the maximum reprocessing capacities per day and per year of each kind of spent fuel, to be reprocessed and the location, structure and equipment of reprocessing facilities as specified in the regulation. Records shall be made in each works or enterprise on the inspection, operation and maintenance of reprocessing facilities, radiation control, accidents and weather, and kept for particular periods respectively. Reprocessing enterprisers shall set up control area, security area and surrounding monitoring area to restrict entrance, etc. Specified measures shall be taken by these enterprisers concerning the exposure radiation doses of workers. Reprocessing facilities shall be inspected and examined more than once a day. The regular self-inspection and operation of reprocessing facilities, the transport and storage of nuclear fuel materials, the disposal of radioactive wastes in works or enterprises where reprocessing facilities are located, and security rules are defined in detail, respectively. (Okada, K.)

The impact of nuclear power stations and of a fuel reprocessing plant on the Rhone river and its prodelta

International Nuclear Information System (INIS)

Foulquier, L.; Garnier-Laplace, J.; Lambrechts, A.; Charmasson, S.; Pally, M.

1992-01-01

The Rhone, with its 6 nuclear sites (17 reactors of various types and a fuel reprocessing unit), presents a relevant example for comparing the impact of these various installations on the aquatic ecosystem. Artificial radioactivity (γ emitters, Pu, 3 H, 90 Sr...) and natural radioactivity are monitored in sediments and various living organisms in the river and its prodelta. A summary of the radioecological procedure is given and illustrated with examples selected from results obtained over the last fifteen years (data resulting from about 7500 samples taken up- and downstream of the installations and in the prodelta). The evolution of results obtained during this period by γ spectrometry on fish up- and downstream of the nuclear power station at Bugey and the Marcoule fuel reprocessing unit is presented. The role of aquatic vegetation as indicator of radiocontamination is also illustrated. The evolution in the concentration levels of γ emitting artificial radionuclides in sediments and mussels in the prodelta is commented on in order to show the global radioecological impact of the Rhone in the Mediterranean sea. The analyses presented show that it is possible to quantify the influence of each source term on the total artificial radioactivity of the compartments of the ecosystem. The source terms are atmospheric fallout from early nuclear weapon tests and of the Chernobyl accident, and liquid wastes of various composition from nuclear installations

Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

Directory of Open Access Journals (Sweden)

Nick R. Soelberg

2013-01-01

Full Text Available The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radionuclide control and immobilization problems. In this paper, we focus on the control requirements and methodologies for 85Kr and 129I. Numerous candidate technologies have been studied and developed at laboratory and pilot-plant scales in an effort to meet the need for high iodine control efficiency and to advance alternatives to cryogenic separations for krypton control. Several of these show promising results. Iodine decontamination factors as high as 105, iodine loading capacities, and other adsorption parameters including adsorption rates have been demonstrated under some conditions for both silver zeolite (AgZ and Ag-functionalized aerogel. Sorbents, including an engineered form of AgZ and selected metal organic framework materials (MOFs, have been successfully demonstrated to capture Kr and Xe without the need for separations at cryogenic temperatures.

Development of remote maintenance technology for nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Kawahara, Akira; Saito, Masayuki; Kawamura, Hironobu; Yamade, Atsushi; Sugiyama, Sen; Sugiyama, Sakae.

1986-01-01

In the plants for reprocessing spent nuclear fuel containing fission products, due to the facts that the facilities are in high radiations fields, and the surfaces of equipments are contaminated with radioactive substances, the troubles of process equipments are directly connected to the remarkable drop of the rate of operation of the facilities. Therefore, the development of various remote maintenance techniques has been carried out so far, but this time, Hitachi Ltd. got a chance to take part in the repair of spent fuel dissolving tanks in the Tokai Reprocessing Plant of Power Reactor and Nuclear Fuel Development Corp. and the development of several kinds of remote checkup equipment related to the repair work. Especially in the repair of the dissolving tanks, a radiation-withstanding checkup and repair apparatus which has high remote operability taking the conditions of radioactive environment and the restriction of the repaired objects in consideration was required, and a dissolving tank repairing robot composed of six kinds has been developed. The key points of the development were the selective use of high radiation-withstanding parts and materials, small size structure and the realization of full remote operability. The full remote maintenance apparatus of this kind is unique in the world, and applicable to wide fields. (Kako, I.)

Reprocessing of nuclear fuels - status report

International Nuclear Information System (INIS)

Schueller, W.

1976-01-01

The paper gives a survey on reprocessing plants at present under construction, in operation, and planned, as well as on the most important process steps such as receipt, storage, conversion, the extraction process, purification of the end products, gaseous waste treatment and waste treatment, and repair and maintenance of reprocessing plants. An outline on operational experience with WAK follows. (HR/LN) [de

A survey of methods to immobilize tritium and carbon-14 arising from a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Taylor, P.

1991-02-01

This report reviews the literature on methods to separate and immobilize tritium ( 3 H) and carbon-14 ( 14 C) released from U0 2 fuel in a nuclear fuel reprocessing plant. It was prepared as part of a broader review of fuel reprocessing waste management methods that might find future application in Canada. The calculated inventories of both 3 H and 14 C in used fuel are low; special measures to limit releases of these radionuclides from reprocessing plants are not currently in place, and may not be necessary in future. If required, however, several possible approaches to the concentration and immobilization of both radionuclides are available for development. Technology to control these radionuclides in reactor process streams is in general more highly developed than for reprocessing plant effluent, and some control methods may be adaptable to reprocessing applications

Contaminants of the bismuth phosphate process as signifiers of nuclear reprocessing history

International Nuclear Information System (INIS)

Schwantes, Jon M.; Sweet, Lucas E.

2012-01-01

Reagents used in spent nuclear fuel recycling impart unique contaminant patterns into the product stream of the process. Efforts are underway at Pacific Northwest National Laboratory to characterize and understand the relationship between these patterns and the process that created them. A main challenge to this effort, recycling processes that were employed at the Hanford site from 1944-1989 have been retired for decades. This precludes direct measurements of the contaminant patterns that propagate within product streams of these facilities. In the absence of any operating recycling facilities at Hanford, we have taken a multipronged approach to cataloging contaminants of U.S. reprocessing activities using: (1) historical records summarizing contaminants within the final Pu metal button product of these facilities; (2) samples of opportunity that represent intermediate products of these processes; and (3) lab-scale experiments and model simulations designed to replicate contaminant patterns at each stage of nuclear fuel reprocessing. This report provides a summary of the progress and results from Fiscal Year (April 1, 2010-September 30) 2011.

Trends for minimization of radioactive waste arising from spent nuclear fuel reprocessing

International Nuclear Information System (INIS)

Polyakov, A.S.; Koltunov, V.S.; Marchenko, V.I.; Ilozhev, A.P.; Mukhin, I.V.

2000-01-01

Research and development of technologies for radioactive waste (RAW) minimization arising from spent nuclear fuel reprocessing are discussed. Novel reductants of Pu and Np ions, reagents of purification recycled extractant, possibility of the electrochemical methods are studied. The partitioning of high activity level waste are considered. Examples of microbiological methods decomposition of radioactive waste presented. (authors)

Cryotechnics used for activity retention in nuclear reactors and in the reprocessing of nuclear fuels

International Nuclear Information System (INIS)

Cavalieri, L.; Gutowski, H.; Patzelt, A.; Schroeder, E.

The use of low temperature technology for cleaning waste gas is demonstrated by four examples from nuclear technology: 1. Treatment of the gaseous fission products and oxyhydrogen gas components (catalytic H 2 oxidation, cold drying, Kr/Xe delay by adsorption) in the primary circuit of a 1300 MWe light water reactor. 2. Cleaning of the helium cooling gas of a high temperature reactor (delay adsorption for short-lived Kr/Xe isotopes, CO/H 2 oxidation CO 2 /H 2 O adsorption and finally low temperature adsorption of Kr/Xe/N 2 and N 2 recondensation). 3. Reprocessing of heavy water moderator by separation of the tritium with low temperature rectification and 4. Cleaning of solvent waste gas of a reprocessing plant (precleaning with various stages of process for separating aerosols, oil, Kr/Xe/N 2 , H 2 , NOsub(x) and low temperature rectification of krypton). (RB) [de

Management of radioactive waste from reprocessing plants

International Nuclear Information System (INIS)

Kanwar Raj

2010-01-01

Reprocessing and recycling of both fissile and fertile components back into appropriate reactor systems is an integral part of three stage nuclear energy programme of India. Different steps involved in processing of spent nuclear fuel (SNF) are decladding, dissolution and recovery of fissile and fertile materials. Reprocessing of SNF is a complex process involving handling of large quantity of radioactive materials and processing chemicals. There are three reprocessing plants in operation in the country at Trombay, Tarapur and Kalpakkam. Out of these plants, Trombay reprocessing plant is engaged in reprocessing of SNF from research reactors and other two plants are processing of SNF from PHWRs. A facility is being built for reprocessing of thorium based spent fuel at BARC, Trombay based on the experience of pilot plant scale. Like other industrial activities of nuclear fuel cycle, fuel reprocessing facilities too generate various types of radioactive waste streams. These are generated in all the three physical forms namely solid, liquid and gas. These waste streams are primarily categorized on the basis of concentration of radionuclides, their half lives and toxicity. Management of these wastes aims at (a) recovery and recycle of useful materials, (b) concentration and confinement of radioactivity in inert and stable matrices, (c) minimization of final waste volume for disposal, (d) decontamination of effluents following ALARA principle and (e) minimization of radioactive discharge to the environment. The present paper outlines the salient features of management of different types of radioactive waste generated in reprocessing plants handling SNF from research reactors and PHWR

Recycling of reprocessed uranium

International Nuclear Information System (INIS)

Randl, R.P.

1987-01-01

Since nuclear power was first exploited in the Federal Republic of Germany, the philosophy underlying the strategy of the nuclear fuel cycle has been to make optimum use of the resource potential of recovered uranium and plutonium within a closed fuel cycle. Apart from the weighty argument of reprocessing being an important step in the treatment and disposal of radioactive wastes, permitting their optimum ecological conditioning after the reprocessing step and subsequent storage underground, another argument that, no doubt, carried weight was the possibility of reducing the demand of power plants for natural uranium. In recent years, strategies of recycling have emerged for reprocessed uranium. If that energy potential, too, is to be exploited by thermal recycling, it is appropriate to choose a slightly different method of recycling from the one for plutonium. While the first generation of reprocessed uranium fuel recycled in the reactor cuts down natural uranium requirement by some 15%, the recycling of a second generation of reprocessed, once more enriched uranium fuel helps only to save a further three per cent of natural uranium. Uranium of the second generation already carries uranium-232 isotope, causing production disturbances, and uranium-236 isotope, causing disturbances of the neutron balance in the reactor, in such amounts as to make further fabrication of uranium fuel elements inexpedient, even after mixing with natural uranium feed. (orig./UA) [de

Legal problems connected with irradiated fuel reprocessing and its waste storage

International Nuclear Information System (INIS)

Nercy, B. de.

1981-10-01

In view of its nature, an irradiated nuclear fuel reprocessing operation -and the contracts implementing it between the reprocessor and the customer- raises certain difficult legal problems. This paper analyses this question from the legal viewpoint, in particular as regards nuclear fuel and material ownership and products or waste arising therefrom, as well as in the context of rules of international trade and non-proliferation standards. (NEA) [fr

Used mixed oxide fuel reprocessing at RT-1 plant

Energy Technology Data Exchange (ETDEWEB)

Kolupaev, D.; Logunov, M.; Mashkin, A.; Bugrov, K.; Korchenkin, K. [FSUE PA ' Mayak' , 30, Lenins str, Ozersk, 460065 (Russian Federation); Shadrin, A.; Dvoeglazov, K. [ITCP ' PRORYV' , 2/8 Malaya Krasmoselskay str, Moscow, 107140 (Russian Federation)

2016-07-01

Reprocessing of the mixed uranium-plutonium spent nuclear fuel of the BN-600 reactor was performed at the RT-1 plant twice, in 2012 and 2014. In total, 8 fuel assemblies with a burn-up from 73 to 89 GW day/t and the cooling time from 17 to 21 years were reprocessed. The reprocessing included the stages of dissolution, clarification, extraction separation of U and Pu with purification from the fission products, refining of uranium and plutonium at the relevant refining cycles. Dissolution of the fuel composition of MOX used nuclear fuel (UNF) in nitric acid solutions in the presence of fluoride ion has occurred with the full transfer of actinides into solution. Due to the high content of Pu extraction separation of U and Pu was carried out on a nuclear-safe equipment designed for the reprocessing of highly enriched U spent nuclear fuel and Pu refining. Technological processes of extraction, separation and refining of actinides proceeded without deviations from the normal mode. The output flow of the extraction outlets in their compositions corresponded to the regulatory norms and remained at the level of the compositions of the streams resulting from the reprocessing of fuel types typical for the RT-1 plant. No increased losses of Pu into waste have been registered during the reprocessing of BN-600 MOX UNF an compare with VVER-440 uranium UNF reprocessing. (authors)

Analysis and study of spent fuel reprocessing technology from birth to present

International Nuclear Information System (INIS)

Takahashi, Keizo

2006-01-01

As for the nuclear fuel reprocessing of the spent fuel, although there was argument of pros and cons, it was decided to start Rokkasho reprocessing project further at the Japan Atomic Energy Commission of ''Long-Term Program for Research, Development and Utilization of Nuclear Energy'' in year 2004. The operation of Tokai Reprocessing is going steadily to reprocess spent fuel more than 1,100 tons. In this paper, history, present status and future of reprocessing technology is discussed focusing from military Pu production, Magnox fuel reprocessing to oxide fuel reprocessing. Amount of reprocessed fuel are estimated based on fuel type. Then, history of reprocessing, US, UK, France, Germany, Russian, Belgian and Japan is presented and compared on technology, national character, development organization, environmental protection, and high active waste vitrification. Technical requirements are increased from Pu production fuel, Magnox fuel and oxide fuel mainly because of higher burnup. Reprocessing technology is synthetic of engineering and accumulation of operational experience. The lessons learned from the operational experience of the world will be helpful for establishment of nuclear fuel reprocessing technology in Japan. (author)

Economics and resources analysis of the potential use of reprocessing options by the current Spanish nuclear reactor park

Energy Technology Data Exchange (ETDEWEB)

Alvarez-Velarde, F.; Merino Rodriguez, I.; Gonzalez-Romero, E.

2014-07-01

Reprocessing of irradiated nuclear fuel serves multiple purposes, from Pu separation and recovery for MOX fuel fabrication to reduction of high level waste volume, and is nowadays being implemented in several countries like France, Japan, Russia or United Kingdom. This work is aimed at exploring the possibility (in resources and economic terms) of implementing reprocessing for MOX fabrication in Spain. (Author)

Fuel handling, reprocessing, and waste and related nuclear data aspects

International Nuclear Information System (INIS)

Kuesters, H.; Lalovic, M.; Wiese, H.W.

1979-06-01

The essential processes in the out-of-pile nuclear fuel cycle are described, i.e. mining and milling of uranium ores, enrichment, fuel fabrication, storage, transportation, reprocessing of irradiated fuel, waste treatment and waste disposal. The aspects of radiation (mainly gammas and neutrons) and of heat production, as well as special safety considerations are outlined with respect to their potential operational impacts and long-term hazards. In this context the importance of nuclear data for the out-of-pile fuel cycle is discussed. Special weight is given to the LWR fuel cycle including recycling; the differences of LMFBR high burn-up fuel with large PuO 2 content are described. The HTR fuel cycle is discussed briefly as well as some alternative fuel cycle concepts. (orig.) [de

Reprocessing plants safety

International Nuclear Information System (INIS)

Davies, A.G.; Leighton, C.; Millington, D.

1989-01-01

The reprocessing of irradiated nuclear fuel at British Nuclear Fuels (BNFL) Sellafield site consists of a number of relatively self-contained activities carried out in separate plants across the site. The physical conditions and time scales applied in reprocessing and storage make it relatively benign. The potential for minor releases of radioactivity under fault conditioning is minimised by plant design definition of control procedures, training and supervision. The risks to both the general public and workforce are shown to be low with all the safety criteria being met. Normal operating conditions also have the potential for some occupational radiation exposure and the plant and workers are monitored continuously. Exposure levels have been reduced steadily and will continue to fall with plant improvements. (U.K.)

Fuel reprocessing at a loss to prove its justification

International Nuclear Information System (INIS)

Traube, K.

1986-01-01

Commercial utilization of nuclear energy is possible with or without fuel reprocessing of spent fuel elements. Demands on terminal storage are about equal in both cases. There is no reason - excluding the military one - to decide in favour of fuel reprocessing instead of direct terminal storage, for neither does fuel reprocessing offer advantages in regard of the safety of nuclear waste disposal, nor is it necessary to produce plutonium for the breeder reactor. Fuel reprocessing is analyzed considering those changed aspects with a view to scarcer uranium resources, juridical motives, and what is termed the development deficit. (DG) [de

Corrosion studies on materials of construction for spent nuclear fuel reprocessing plant equipment

International Nuclear Information System (INIS)

Kamachi Mudali, U.; Dayal, R.K.; Gnanamoorthy, J.B.

1993-01-01

Corrosion studies on specimens of commercial Type 304L stainless steel (SS), nuclear grade type 304L SS, extra low-carbon nitric acid grade (NAG) Uranus-16 SS, NAG Uranus-65 SS, Ti, Ti-5% Ta, Ti-0.25% Pd, Zircaloy-2, weldments of Ti and of Ti-5% Ta, and surface-modified (thermally oxidised and anodised) Ti were carried out to assess their corrosion resistance in nitric acid medium. The results indicated that Zircaloy-2, Ti-5% Ta, Uranus-16 SS and Uranus-65 SS have excellent corrosion resistance in boiling nitric acid solution. Specimens of Zircaloy-2, Ti-5% Ta and thermally-oxidised Ti showed excellent corrosion resistance also in a simulated uranium-containing reprocessing medium in a concentrated nitric acid solution. SEM and XRD analyses were carried out on the tested specimens to examine the scale morphology and phases present on the surface. (orig.)

Dynamic considerations in the development of centrifugal separators used for reprocessing nuclear fuel

International Nuclear Information System (INIS)

Strunk, W.D.; Singh, S.P.; Tuft, R.M.

1988-01-01

The development of centrifugal separators has been a key ingredient in improving the process used for reprocessing of spent nuclear fuel. The separators are used to segregate uranium and plutonium from the fission products produced by a controlled nuclear reaction. The separators are small variable speed centrifuges, designed to operate in a harsh environment. Dynamic problems were detected by vibration analysis and resolved using modal analysis and trending. Problems with critical speeds, resonances in the base, balancing, weak components, precision manufacturing, and short life have been solved

Qualitative simulation for supervision of a nuclear reprocessing plant

International Nuclear Information System (INIS)

Leyval, L.; Ledoux, A.

1991-01-01

This paper deals with the first application of a supervision support system to a part of a nuclear reprocessing plant. The system is called DIAPASON; its role is to help the operators to understand the behaviour of the process, and to diagnose failures if needed. This paper is only concerned with the simulation of the behaviour of the process and the associated explanations provided by DIAPASON during the normal operation periods. The modeling, simulation techniques are presented, when applied to a nuclear process. A causal graph linking the relevant variables by Qualitative Transfer Functions models the process behaviour. The simulation consists in propagating through the entire graph the significant events detected on the input variables or on measurable disturbances of the process. As a result, the evolutions of all the other variables are obtained. The explanations that can be provided at the present time are deduced from the simulation

Simulation of nuclear fuel reprocessing for safeguards

International Nuclear Information System (INIS)

Canty, M.J.; Dayem, H.A.; Kern, E.A.; Spannagel, G.

1983-11-01

For safeguarding the chemical process area of future reprocessing plants the near-real-time material accountancy (NRTMA) method might be applied. Experimental data are not yet available for testing the capability of the NRTMA method but can be simulated using a digital computer. This report describes the mathematical modeling of the Pu-bearing components of reprocessing plants and presents first results obtained by simulation models. (orig.) [de

Occupational exposure at the nuclear fuel reprocessing plant at Sellafield in Cumbria

International Nuclear Information System (INIS)

Coyle, A.; Partington, C.

1991-01-01

The nuclear reprocessing plant at Sellafield employs approximately 6500 people in a wide range of activities involving radioactive materials. The exposure to personnel over the period 1978-1989 is reviewed. Information is presented on collective and average dose exposure which both show significant downward trends. The current annual collective dose for reprocessing operations is 21.4 man Sv and the average whole body exposure 3.7 mSv.y -1 , taking account of both internal and external exposure. The introduction of radiological design targets for new plants and the use of formal ALARP assessments on projects has contributed substantially to the observed reduction in dose uptake. Experience also indicates that significant dose reduction can be achieved by heightening the awareness of both managers and workers of the dose implications of their work and working methods. (author)

The regulations concerning the reprocessing business of spent fuels

International Nuclear Information System (INIS)

1979-01-01

The regulations are defined under provisions concerning the reprocessing business in the law for the regulations of nuclear source materials, nuclear fuel materials and reactors. The basic concepts and terms are explained, such as: exposure dose; accumulative dose; controlled area; safeguarded area; inspected surrounding area; employee; radioactive waste and marine discharging facilities. Any person who gets permission for design of reprocessing facilities and method of the construction shall file an application, listing name and address of the person and the works or the place of enterprise where reprocessing facilities are to be set up, design of such facilities and method of the construction, in and out-put chart of nuclear fuel materials in reprocessing course, etc. Records shall be made and kept for particularly periods in each works or enterprise on inspection of reprocessing facilities, control of dose, operation, maintenance, accident of reprocessing facilities and weather. Detailed prescriptions are settled on entrance limitation to controlled area, exposure dose, inspection and check, regular independent examination and operation of reprocessing facilities, transportation in the works or the enterprise, storage, disposal, safeguard and measures in dangerous situations, etc. Reports shall be filed on exposure dose of employees and other specified matters in the forms attached and in the case otherwise defined. (Okada, K.)

Trends in fuel reprocessing safety research

International Nuclear Information System (INIS)

Tsujino, Takeshi

1981-01-01

With the operation of a fuel reprocessing plant in the Power Reactor and Nuclear Fuel Development Corporation (PNC) and the plan for a second fuel reprocessing plant, the research on fuel reprocessing safety, along with the reprocessing technology itself, has become increasingly important. As compared with the case of LWR power plants, the safety research in this field still lags behind. In the safety of fuel reprocessing, there are the aspects of keeping radiation exposure as low as possible in both personnel and local people, the high reliability of the plant operation and the securing of public safety in accidents. Safety research is then required to establish the safety standards and to raise the rate of plant operation associated with safety. The following matters are described: basic ideas for the safety design, safety features in fuel reprocessing, safety guideline and standards, and safety research for fuel reprocessing. (J.P.N.)

Working conditions in nuclear reprocessing plants

International Nuclear Information System (INIS)

1986-12-01

In the context of the project, the working conditions of workers in reprocessing plants and associated plant of the fuel circuit were thoroughly examined. The project design and course of the project are a good example of a precautionary technical assessment necessary for social policy reasons, which is in the public interest and is required by the Trade Unions. By working conditions, one means the whole set of scientific/technical, medical, legal, economic and political conditions for the permanent employment of workers in reprocessing plants including the associated parts of the fuel circuit. (orig./HP) [de

In-line analytical instrumentation in nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Rao, V.K.; Bhargava, V.K.; Marathe, S.G.

1979-01-01

In nuclear fuel reprocessing plants where uranium and plutonium are separated from highly radioactive fission products, continuous monitoring of these constituents is helpful in many ways. Apart from quick detection of possible process malfunctions, in-line monitoring protects operating personnel from radiation hazards, reduces the cost of laboratory analysis and increases the overall efficiency of the process. A review of a proqramme of work on the design, fabrication and testing of some in-line instruments viz. gamma absorptiometer for uranium, neutron monitor for plutonium, acidity monitor for scrub nitric acid etc., their feasibility studies in the laboratory as well as in the pilot plant is presented. (auth.)

Behavior of Nb fission product during nuclear fuel reprocessing

International Nuclear Information System (INIS)

Gue, J.P.

1977-02-01

Investigations on niobium fission product behavior in nitric acid and tributyl phosphate media have been carried out in order to explain the difficulties encountered in separating this element from fissile materials during spent nuclear fuel reprocessing. The studies have shown that in nitric acid solution, pentavalent niobium has a colloidal hydroxide form. The so-obtained sols were characterized by light scattering, electronic microscopy, electrophoresis and ultracentrifugation methods. In heterogeneous extracting media containing tributyl phosphate and dibutyl phosphoric acid the niobium hydroxide sols could be flocculated by low dibutyl phosphoric acid concentration or extracted into the organic phase containing an excess of dibutyl phosphoric acid [fr

MOX fuel reprocessing and recycling

International Nuclear Information System (INIS)

Guillet, J.L.

1990-01-01

This paper is devoted to the reprocessing of MOX fuel in UP2-800 plant at La Hague, and to the MOX successive reprocessing and recycling. 1. MOX fuel reprocessing. In a first step, the necessary modifications in UP2-800 to reprocess MOX fuel are set out. Early in the UP2-800 project, actions have been taken to reprocess MOX fuel without penalty. They consist in measures regarding: Dissolution; Radiological shieldings; Nuclear instrumentation; Criticality. 2. Mox successive reprocessing and recycling. The plutonium recycling in the LWR is now a reality and, as said before, the MOX fuel reprocessing is possible in UP2-800 plant at La Hague. The following actions in this field consist in verifying the MOX successive reprocessing and recycling possibilities. After irradiation, the fissile plutonium content of irradiated MOX fuel is decreased and, in this case, the re-use of plutonium in the LWR need an important increase of initial Pu enrichment inconsistent with the Safety reactor constraints. Cogema opted for reprocessing irradiated MOX fuel in dilution with the standard UO2 fuel in appropriate proportions (1 MOX for 4 UO2 fuel for instance) in order to save a fissile plutonium content compatible with MOX successive recycling (at least 3 recyclings) in LWR. (author). 2 figs

Examination of methods of proliferation control for application to nuclear fuel reprocessing facilities

International Nuclear Information System (INIS)

O'Hara, F.A.

1980-01-01

Potential methods are examined that could be applied to the nuclear fuel reprocessing facility as a means of more effectively controlling the proliferation threat and, at the same time, permitting the further development of nuclear power as an energy source. The proposed remedies for this problem are basically technical or economic and political in nature and include: ''technical fixes'', institutional arrangements, and international political solutions. Each of these approaches to the problem is examined, along with a consideration of their interaction and an estimation of their effectiveness, either individually or in combination. 22 refs

Evaluation of methods for seismic analysis of nuclear fuel reprocessing and fabrication facilities

International Nuclear Information System (INIS)

Arthur, D.F.; Dong, R.G.; Murray, R.C.; Nelson, T.A.; Smith, P.D.; Wight, L.H.

1978-01-01

Methods of seismic analysis for critical structures and equipment in nuclear fuel reprocessing plants (NFRPs) and mixed oxide fuel fabrication plants (MOFFPs) are evaluated. The purpose of this series of reports is to provide the NRC with a technical basis for assessing seismic analysis methods and for writing regulatory guides in which methods ensuring the safe design of nuclear fuel cycle facilities are recommended. The present report evaluates methods of analyzing buried pipes and wells, sloshing effects in large pools, earth dams, multiply supported equipment, pile foundations, and soil-structure interactions

Methodology for evaluation of alternative technologies applied to nuclear fuel reprocessing

International Nuclear Information System (INIS)

Selvaduray, G.S.; Goldstein, M.K.; Anderson, R.N.

1977-07-01

An analytic methodology has been developed to compare the performance of various nuclear fuel reprocessing techniques for advanced fuel cycle applications including low proliferation risk systems. The need to identify and to compare those processes, which have the versatility to handle the variety of fuel types expected to be in use in the next century, is becoming increasingly imperative. This methodology allows processes in any stage of development to be compared and to assess the effect of changing external conditions on the process

Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

International Nuclear Information System (INIS)

Crawford, J.M.; Ehinger, M.H.; Joseph, C.; Madeen, M.L.

1979-07-01

A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system

Power Reactor Fuel Reprocessing Plant-2, Tarapur: a benchmark in Indian PHWR spent fuel reprocessing

International Nuclear Information System (INIS)

Pradhan, Sanjay; Dubey, K.; Qureshi, F.T.; Lokeswar, S.P.

2017-01-01

Power Reactor Fuel Reprocessing Plant-2 (PREFRE-2) is latest operating spent nuclear fuel reprocessing plant in India. This plant has improved design based on latest technology and feedback provided by the earlier plants. The design of PREFRE-2 plant is in five cycles of solvent extraction using TBP as extractant. The plant is commissioned in year 2011 after regulatory clearances

The reprocessing of irradiated MTR fuel and the nuclear material accountancy - Dounreay, UKAEA

Energy Technology Data Exchange (ETDEWEB)

Barrett, T.R.; Harrison, R. [UKAEA, Nuclear Materials Control Dep., Dounreay (United Kingdom)

1997-07-01

The reprocessing of irradiated HEU MTR fuel is a sensible part of a safeguards regime. It brings together fuel otherwise scattered around the world into a concerted accountancy and protection arrangement. From a nuclear material accountants view the overall accountancy performance has been excellent. While investigations have been required for a few individual MUFs or trends, very little effort has required to be expended by the Nuclear Materials Control Department. That is a definition of a 'good plant'; it operates, measures and records input and output streams, and then the accountancy falls into place. As identified in this paper, the accountancy of the nuclear material processed in the plant is well founded and sound. The accountancy results over several decades confirm the adequacy of the safeguards arrangements at Dounreay. The processing makes good commercial sense and meets the current philosophy of recycling valuable resource materials. The risk of operating the full fuel cycle are less than those of extended storage of irradiated fuel at disparate diverse locations. The reprocessing at Dounreay accords with all of these philosophies. The assessed risk is at a very low level, well within published UK HSE 'tolerability of risk' regulatory guidelines. The impact of the operations are similarly low within the guidelines, for the operators and for the general public. (author)

The reprocessing of irradiated MTR fuel and the nuclear material accountancy - Dounreay, UKAEA

International Nuclear Information System (INIS)

Barrett, T.R.; Harrison, R.

1997-01-01

The reprocessing of irradiated HEU MTR fuel is a sensible part of a safeguards regime. It brings together fuel otherwise scattered around the world into a concerted accountancy and protection arrangement. From a nuclear material accountants view the overall accountancy performance has been excellent. While investigations have been required for a few individual MUFs or trends, very little effort has required to be expended by the Nuclear Materials Control Department. That is a definition of a 'good plant'; it operates, measures and records input and output streams, and then the accountancy falls into place. As identified in this paper, the accountancy of the nuclear material processed in the plant is well founded and sound. The accountancy results over several decades confirm the adequacy of the safeguards arrangements at Dounreay. The processing makes good commercial sense and meets the current philosophy of recycling valuable resource materials. The risk of operating the full fuel cycle are less than those of extended storage of irradiated fuel at disparate diverse locations. The reprocessing at Dounreay accords with all of these philosophies. The assessed risk is at a very low level, well within published UK HSE 'tolerability of risk' regulatory guidelines. The impact of the operations are similarly low within the guidelines, for the operators and for the general public. (author)

Nuclear fuel cycle: (5) reprocessing of irradiated fuel

Energy Technology Data Exchange (ETDEWEB)

Williams, J.A.

1977-09-01

The evolution of the reprocessing of irradiated fuel and the recovery of plutonium from it is traced out, starting by following the Manhatten project up to the present time. A brief description of the plant and processes used for reprocessing is given, while the Purex process, which is used in all plants today, is given special attention. Some of the important safety problems of reprocessing plants are considered, together with the solutions which have been adopted. Some examples of the more important safety aspects are the control of activity, criticality control, and the environmental impact. The related topic of irradiated fuel transport is briefly discussed.

Remote handling equipment for laboratory research of fuel reprocessing in Nuclear Research Institute at Rez

International Nuclear Information System (INIS)

Fidler, J.; Novy, P.; Kyrs, M.

1985-04-01

Laboratory installations were developed for two nuclear fuel reprocessing methods, viz., the solvent extraction process and the fluoride volatility process. The apparatus for solvent extraction reprocessing consists of a pneumatically driven rod-chopper, a dissolver, mixer-settler extractors, an automatic fire extinguishing device and other components and it was tested using irradiated uranium. The technological line for the fluoride volatility process consists of a fluorimater, condensers, sorption columns with NaF pellets and a distillation column for the separation of volatile fluorides from UF 6 . The line has not yet been tested using irradiated fuel. Some features of the remote handling equipment of both installations are briefly described. (author)

A numerical simulation of 129I in the atmosphere emitted from nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Nishizawa, Masato; Suzuki, Takashi; Nagai, Haruyasu; Togawa, Orihiko

2010-01-01

A global chemical transport model, MOZART-4, is applied to investigate the behavior of 129 I emitted from nuclear fuel reprocessing plants in Europe (Sellafield in the UK and La Hague in France). The result of numerical simulation for more than fifty-year period from the 1950s is validated by comparison with measurements of 129 I around the world and analyzed to clarify the characteristic of the distributions of concentration and deposition of 129 I. The modeled concentrations of 129 I in precipitation in Europe and the United States and inventories in the seawater around Japan and the Gulf of Mexico are in the same order as measurements. the emitted 129 I to the atmosphere is distributed all over the Northern Hemisphere due mainly to the prevailing westerlies and can be an important source of supply of artificial 129 I for the seawater remote from the point source such as a nuclear fuel reprocessing plant. (author)

Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

International Nuclear Information System (INIS)

Crawford, J.M.; Ehinger, M.H.; Joseph, C.; Madeen, M.L.

1979-01-01

A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system. 2 refs

Back-end of the nuclear fuel cycle. A comparison of the direct disposal and reprocessing options

International Nuclear Information System (INIS)

Allan, C.J.; Baumgartner, P.

1997-01-01

Based on the need to address public concerns, the need to ensure long-term safety and an ethical concern for future generations, many countries are developing technology to dispose of nuclear fuel waste. The waste substances in used fuel can be disposed of either by directly disposing of the used fuel assemblies themselves, or by disposing of the long-lived waste from fuel reprocessing. The basic thesis of this paper is that the direct disposal of either used fuel or of the long-lived heat-generating and non-heat generating waste that arise from reprocessing is technically and economically feasible and that both options will meet the fundamental objectives of protecting human health and the environment. Decisions about whether, or when, to reprocess used fuel, or about whether to dispose of used fuel directly, are not fundamentally waste management issues. (author)

A global-scale dispersion analysis of iodine-129 from nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Nishizawa, Masato; Suzuki, Takashi; Nagai, Haruyasu; Togawa, Orihiko

2010-01-01

A three-dimensional global chemical transport model, MOZART-2, is applied to investigate the global-sale dispersion of Iodine-129 from nuclear fuel reprocessing plants. The concentration and deposition of 129 I obtained by MOZART-2 are dispersed all over the Northern Hemisphere. The emission of 129 I to the atmosphere is thus important in considering the transport of 129 I to remote sites. (author)

Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

Energy Technology Data Exchange (ETDEWEB)

Grison, J [Compagnie Generale des Matieres Nucleaires (COGEMA), Centre de la Hague, 50 - Cherbourg (France)

1980-10-01

The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis.

Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Grison, J.

1980-01-01

The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis [fr

Development of a model to optimize global use of nuclear energy considering competition of seawater uranium and reprocessing

International Nuclear Information System (INIS)

Undarmaa, Baatarkhuu; Horio, Kenta; Fujii, Yasumasa; Komiyama, Ryoichi

2017-01-01

In order to sustain long-term energy security and to mitigate the climate change, nuclear power remains an important baseload option for the global power generation mix. To utilize nuclear power in long-term, some important concerns such as economics, stability of fuel supply and spent fuel amount should be evaluated. Model developed in this study optimizes the global use nuclear power considering such issues. The Model is based on linear programming and calculates the best mix of nuclear reactor types by minimizing the current value of total power generation cost within the target period (next 100 years). Possibility of fuel cycle options such as reprocessing, seawater uranium and thorium utilization are also taken in to account, along with remaining spent fuel and plutonium stock. As result. reprocessing and uranium from seawater become essential part of nuclear fuel cycle in the long run. Amount of stored spent fuel is reduced following the deployment of Fast Breeder Reactor. Also, as an extension of current model, a baseload power generation mix model, which estimates the optimal mix of nuclear and coal-fired power generation will be introduced. (author)

The regulations concerning the reprocessing business of spent fuels

International Nuclear Information System (INIS)

1980-01-01

The office ordinance is established under the provisions related to reprocessing businesses of the law concerning regulation of nuclear raw materials, nuclear fuel materials and reactors, to enforce the provisions. The basic terms are defined, such as exposure radiation dose; accumulated dose; controlled area; maintenance area; surrounding watch area; employee; radioactive waste; the facilities for discharge to sea. An application for the designation of reprocessing businesses shall be filed, listing the following matters: the maximum daily and yearly reprocessing capacities for each kind of spent fuel; the location and general structure of reprocessing facilities; the structures of buildings; the structure and equipments of main reprocessing facilities, the storage facilities for products and the disposal facilities for radioactive wastes; the equipments of measuring and control system facilities and radiation control facilities, etc. Records shall be made on the inspection of reprocessing facilities, radiation control, operation, maintenance, the accidents of reprocessing facilities and weather, and kept for the period from one to ten years, respectively. Any person engaging in reprocessing businesses shall set up control, maintenance and surrounding watch areas, and take specified measures to restrict the entrance of persons. The measures to be taken against exposure radiation dose, the inspection, regular independent examination and operation of reprocessing facilities and other related matters are stipulated in detail. (Okada, K.)

Method for recovering palladium and technetium values from nuclear fuel reprocessing waste solutions

Science.gov (United States)

Horwitz, E. Philip; Delphin, Walter H.

1979-07-24

A method for recovering palladium and technetium values from nuclear fuel reprocessing waste solutions containing these and other values by contacting the waste solution with an extractant of tricaprylmethylammonium nitrate in an inert hydrocarbon diluent which extracts the palladium and technetium values from the waste solution. The palladium and technetium values are recovered from the extractant and from any other coextracted values with a strong nitric acid strip solution.

Practice and prospects of creation of equipment for reprocessing and utilization of contaminated metal wastes of plants of nuclear industry in Russia

International Nuclear Information System (INIS)

Popov, G.P.

2005-01-01

Program of reprocessing and utilization of metallic radioactive wastes exists in Russia. In the framework of this program in nuclear industry it is accumulated forty years experience on taking-off-service, disassembly, decontamination and reprocessing of technological facilities. Some technical characteristics of the units used for these operations are represented [ru

Reprocessing in Sweden: History and perspective

International Nuclear Information System (INIS)

Hultgren, Aa.; Oesterlund, C.G.

1990-10-01

Against the background of nuclear power development and installation in Sweden an overview is presented of the parallel domestic development of the reprocessing of spent nuclear fuel. The original selection of the natural uranium - heavy water reactor in the 1950s included spent fuel reprocessing and recycle, and process and plant studies were performed to that end. The switch to light water reactors in the 1960s did not change the planning to recycle; however, the participation in the Eurochemic undertaking, and the delay in the nuclear programme stopped further domestic development work. A number of governmental committee investigations in the 1970s on the radioactive waste issue and, above all, the decision to phase out nuclear power by 2010, after a referendum following the TMI-accident, finally resulted in a decision to plan only for direct disposal of spent nuclear fuel. This policy still prevails. (42 refs.)

Economic assessment factors relating to spent nuclear fuel reprocessing

International Nuclear Information System (INIS)

This paper is in two parts. Part I discusses the factors to be applied in an economic assessment of reprocessing. It sets forth three basic cost components, namely capital costs, operating costs and the cost of capital utilization. It lists the various components of each cost area. Part II proposes a relationship between these respective cost areas, tabulates a range of costs and then develops unit costs for reprocessing operations. Finally, an addendum to the paper gives a more detailed breakdown of the capital costs of a reprocessing plant

Reprocessing of nuclear fuels: economical, ecological and technical aspects

International Nuclear Information System (INIS)

Kueffer, K.

1994-01-01

The report deals with the questions on reprocessing and final storage of spent fuel elements from the point of view of the Swiss. The contractual obligations were discussed, of the present situation of reprocessing and their assessment. 1 fig

Evaluation of subcritical hybrid systems loaded with reprocessed fuel

International Nuclear Information System (INIS)

Velasquez, Carlos E.; Barros, Graiciany de P.; Pereira, Claubia; Veloso, Maria Auxiliadora F.; Costa, Antonella L.

2015-01-01

Highlights: • Accelerator driven systems (ADS) and fusion–fission systems are investigated for transmutation and fuel regeneration. • The calculations were performed using Monteburns code. • The results indicate the most suitable system for achieve transmutation. - Abstract: Two subcritical hybrid systems containing spent fuel reprocessed by Ganex technique and spiked with thorium were submitted to neutron irradiation of two different sources: ADS (Accelerator-driven subcritical) and Fusion. The aim is to investigate the nuclear fuel evolution using reprocessed fuel and the neutronic parameters under neutron irradiation. The source multiplication factor and fuel depletion for both systems were analysed during 10 years. The simulations were performed using MONTEBURNS code (MCNP/ORIGEN). The results indicate the main differences when irradiating the fuel with different neutron sources as well as the most suitable system for achieving transmutation

Will the world SNF be reprocessed in Russia?

International Nuclear Information System (INIS)

Gagarinski, A.

2000-01-01

Russia's possibilities in nuclear fuel reprocessing are well known. RT-1 plant with 400 tons/year in the Chelyabinsk region can provide reprocessing of fuel from Russian and Central European WWER-440 reactors, as well as from transport and research reactors. Former military complex Krasnoyarsk-26 with unique underground installations situated in rock galleries, already has an aqueous facility for storage of 6000 tons of spent nuclear fuel (SNF), half-built plant RT-2 for nuclear fuel reprocessing with 1500 tons/year capacity, as well as the projects of dry storage facility for 30000 tons of SNF and of MOX fuel production plant. Russian nuclear specialists understand well, that the economic efficiency of nuclear fuel reprocessing industry is shown only in case of large-scale production, which would require consolidation of the countries, which develop nuclear energy. They also understand, that Russia has all the possibilities to become one of the centers of such a consolidation and to use these possibilities for the benefit of the country. The idea of foreign nuclear fuel reprocessing (for a long time realized for East and Central European countries, which operate Soviet-design reactors) has existed in the specialists' minds, and sometimes has appeared in the mass media. On the other hand, rehabilitation of territories of nuclear fuel cycle enterprises in Russia continues, including the Karachai lake, which contains 120 million Curie of radioactivity. Unfortunately, Russia simply has no money for complete solution of the problems of radiation military legacy. During discussion of the budget for 2000, the Russian Minatom has made a daring step. A real program, how to find money needed for solving the 'radiation legacy' problem, was proposed. With this purpose, it was proposed to permit storage and further reprocessing of other countries' SNF on Russian territory. It is well known, that another countries' SNF is accepted for reprocessing by UK and France, and Russia

Data used for safety assessment of reprocessing facilities

International Nuclear Information System (INIS)

Nomura, Yasushi; Suzuki, Atsuyuki; Kanagawa, Akira

1990-08-01

For safety assessment of a reprocessing facility, it is important to know performance of radioactive materials in their accidental release and transfer. Accordingly, it is necessary to collect and prepare data for use in analyses for their performance. In JAERI, experiments such as for data acquisition, for source-term evaluation and for radioactive material transfer, are now planned to be performed. Prior to these experiments, it is decided to investigate data in use for accidental safety assessment of reprocessing plants and their based experimental data, thus to make it possible to recommend reasonable values for safety analysis parameters by evaluating the investigated results, to select the experimental items, to edit a safety assessment handbook and so on. In this line of objectives, JAERI rewarded a two-year contract of investigation to Nuclear Safety Research Association, to make a working group under a special committee on data investigation for reprocessing facility safety assessment. This report is a collection of results reviewed and checked by the working group. The contents consist of two parts, one for investigation and review of data used for safety assessment of domestic or oversea reprocessing facilities, and the other for investigation, review and evaluation of ANSI recommended American standard data reported by E. Walker together with their based experimental data resorting to the original referred reports. (author)

Nuclear fuel reprocessing is challenged

International Nuclear Information System (INIS)

Anon.

1994-01-01

This article is a brief discussion of litigation to determine if the Thermal Oxide Reprocessing Plant (THORP) in the United Kingdom will be allowed to operate. Litigants (including Greenpeace) contend that the government's December approval of discharge permits for the plant was unlawful without a public hearing. A description of the THORP process is also provided in this article

Handling of spent nuclear fuel and final storage of nitrified high level reprocessing waste

International Nuclear Information System (INIS)

The following stages of handling and transport of the fuel on its way to final storage are dealt with in the report. 1) The spent nuclear fuel is stored at the power station or in the central fuel storage facility awaiting reprocessing. 2) The fuel is reprocessed, i.e. uranium, plutonium and waste are separated from each other. Reprocessing does not take place in Sweden. The highlevel waste is vitrified and can be sent back to Sweden in the 1990s. 3) Vitrified waste is stored for about 30 years awaiting deposition in the final repository. 4) The waste is encapsulated in highly durable materials to prevent groundwater from coming into contact with the waste glass while the radioactivity of the waste is still high. 5) The canisters are emplaced in a final repository which is built at a depth of 500 m in rock of low permeability. 6) All tunnels and shafts are filled with a mixture of clay and sand of low permeability. A detailed analysis of possible harmful effects resulting from normal acitivties and from conceivable accidents is presented in a special section. (author)

Industrial experience of irradiated nuclear fuel reprocessing

International Nuclear Information System (INIS)

Delange, M.

1981-01-01

At the moment and during the next following years, France and La Hague plant particularly, own the greatest amount of industrial experience in the field of reprocessing, since this experience is referred to three types of reactors, either broadly spread all through the world (GCR and LWR) or ready to be greatly developed in the next future (FBR). Then, the description of processes and technologies used now in France, and the examination of the results obtained, on the production or on the security points of view, are a good approach of the actual industrial experience in the field of spent fuel reprocessing. (author)

Study of the stability of organic ligands usable for the spent nuclear fuel reprocessing

International Nuclear Information System (INIS)

Draye, Micheline

1994-01-01

The first part of this research thesis on the stability of organic ligands in radioactive environment, reports the study of the stability of the dicyclohexano-18-crown-6 (DCH18C6) in radioactive environment by using several analytical techniques (nuclear magnetic resonance or NMR, X-ray diffraction, Fourier transform infrared spectroscopy or FTIR, gas chromatography or GC, and coupled gas chromatography/mass spectroscopy). The seven main radiolysis products of DCH18C6 are identified and then synthesised to be tested in radioactive environment. These products are soluble in nitric medium, and partially precipitate plutonium, but cannot in any case disturb the reprocessing process based on a continuous extraction system. Chemical yields are computed and DCH18C6 appears to be a serious candidate for the reprocessing of spent nuclear fuels. The second part reports the study of the stability of the poly(4-vinylpyridine) or P4VP in radioactive environment. It appears that gamma radiations produce radicals in the P4VP which recombine in function of the irradiation dose. However, this material is very stable in acid environment and radioactive environment [fr

Review of experience with plutonium exposure assessment methodologies at the nuclear fuel reprocessing site of British Nuclear Fuels plc

International Nuclear Information System (INIS)

Strong, R.

1988-01-01

British Nuclear Fuels plc and its predecessors have provided a complete range of nuclear fuel services to utilities in the UK and elsewhere for more than 30 years. Over 30,000 ton of Magnox and Oxide fuel have been reprocessed at Sellafield. During this time substantial experience has accumulated of methodologies for the assessment of exposure to actinides, mainly isotopes of plutonium. For most of the period monitoring of personnel included assessment of systemic uptake deduced from plutonium-in-urine results. The purpose of the paper is to present some conclusions of contemporary work in this area

Spent fuel reprocessing system availability definition by process simulation

International Nuclear Information System (INIS)

Holder, N.; Haldy, B.B.; Jonzen, M.

1978-05-01

To examine nuclear fuel reprocessing plant operating parameters such as maintainability, reliability, availability, equipment redundancy, and surge storage requirements and their effect on plant throughput, a computer simulation model of integrated HTGR fuel reprocessing plant operations is being developed at General Atomic Company (GA). The simulation methodology and the status of the computer programming completed on reprocessing head end systems is reported

Equipment specifications for an electrochemical fuel reprocessing plant

International Nuclear Information System (INIS)

Hemphill, Kevin P.

2010-01-01

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.

Standard model for the safety analysis report of nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

1980-02-01

This norm establishes the Standard Model for the Safety Analysis Report of Nuclear Fuel Reprocessing Plants, comprehending the presentation format, the detailing level of the minimum information required by the CNEN for evaluation the requests of Construction License or Operation Authorization, in accordance with the legislation in force. This regulation applies to the following basic reports: Preliminary Safety Analysis Report - PSAR, integrating part of the requirement of Construction License; and Final Safety Analysis Report (FSAR) which is the integrating part of the requirement for Operation Authorization

Research on advanced aqueous reprocessing of spent nuclear fuel: literature study

Energy Technology Data Exchange (ETDEWEB)

Van Hecke, K.; Goethals, P.

2006-07-15

The goal of the partitioning and transmutation strategy is to reduce the radiotoxicity of spent nuclear fuel to the level of natural uranium in a short period of time (about 1000 years) and thus the required containment period of radioactive material in a repository. Furthermore, it aims to reduce the volume of waste requiring deep geological disposal and hence the associated space requirements and costs. Several aqueous as well as pyrochemical separation processes have been developed for the partitioning of the long-lived radionuclides from the remaining of the spent fuel. This report aims to describe and compare advanced aqueous reprocessing methods.

Research on advanced aqueous reprocessing of spent nuclear fuel: literature study

International Nuclear Information System (INIS)

Van Hecke, K.; Goethals, P.

2006-01-01

The goal of the partitioning and transmutation strategy is to reduce the radiotoxicity of spent nuclear fuel to the level of natural uranium in a short period of time (about 1000 years) and thus the required containment period of radioactive material in a repository. Furthermore, it aims to reduce the volume of waste requiring deep geological disposal and hence the associated space requirements and costs. Several aqueous as well as pyrochemical separation processes have been developed for the partitioning of the long-lived radionuclides from the remaining of the spent fuel. This report aims to describe and compare advanced aqueous reprocessing methods.

Composite reprocessing of spent nuclear fuel - is a way to low waste nuclear power

International Nuclear Information System (INIS)

Kosyakov, Valentin

2005-01-01

Further development of nuclear power in many respects depend on the solution of the problems connected to high level radioactive wastes (HLRW), containing highly toxic long-lived radionuclides. Long-term controlled storage of HLRW manages expensively and any advanced technology of reprocessing of spent nuclear fuel (SNF), besides recovery of the basic products, should be aimed at the reduction of this waste amount. However, the existing SNF reprocessing technology, using PUREX - process, is aimed only at extraction of uranium and plutonium, considering the remaining fraction (other transuranium elements and all fission products) as HLRW. In this work an attempt is made to give quantitative and qualitative characteristics to the isotopes and the elements which are included in the composition of HLRW after 15-years storage. Depending on the radiation properties of the isotopes included, these elements were divided into three categories: 1. The elements represented by only stable isotopes; 2. The elements represented by mostly low radioactive isotopes; 3. The elements represented by highly toxic long-lived radionuclides. As a result it appeared, that the weight percentage of the elements of the first, the second and the third categories in HLRW was: 60, 25 and 15% respectively. It means, that the amount of the real HLRW to be disposed in a deep geological repository could be reduced at least by a factor of 6, if to recover completely only 7 most dangerous elements (Sr, J, Cs, Sm, Np, Am and Cm) from the solution remaining after extraction of uranium and plutonium. Then it is meaningful to recover the elements of the first category from the remaining mix. As the main part of this fraction is represented by rare earth elements and noble metals, which can easily find many useful application. (author)

Status of project design work for a German reprocessing plant

International Nuclear Information System (INIS)

Lang, K.; Zuehlke, P.

1976-01-01

A reprocessing plant will be built within the framework of a comprehensive waste management center planned by the Federal Government to treat the fuel elements unloaded from German nuclear power stations. On the basis of an annual throughput of 1,400 te of uranium averaged over the life of the plant, the center will be able to serve between 45,000 and 50,000 MWe of installed nuclear generating capacity. A comprehensive conceptual design study of the reprocessing plant to be built has been completed on the basis of the operating experience accumulated at the Karlsruhe reprocessing plant and the development work carried out by the Karlsruhe Nuclear Research Center and in the light also of an intensive exchange of experience with British and French reprocessing companies within the framework of United Reprocessors GmbH. This conceptual design study is the foundation for the preliminary project to be carried out on a collaborative basis by KEWA and PWK. (orig.) [de

Present status of foreign reprocessing technology

International Nuclear Information System (INIS)

Otagaki, Takao; Ishikawa, Yasusi; Mori, Jyunichi

2000-03-01

In considering extensively and evaluating advanced nuclear fuel recycle technologies then selecting credible one among those technology options and establishing practicable plan of future fast reactor fuel recycle technology, it is important to investigate foreign reprocessing information extensively and minutely as much as possible then to know trends of reprocessing technology development in the world and present technology level of each country. This report is intending to present information of the status and the technology of operating, constructing and closed foreign reprocessing facilities in the world, including, mixed oxide (MOX) fuel reprocessing technology. The conceptual study of 'Foreign Reprocessing Technology Database' was also performed in order to add or revise the information easily. The eight countries, France, The U.K., Russia, The U.S., Germany, Belgium, India and China, were studied regarding outline of the facilities, operation status, future plan, technical information of process flow sheet, primary components, maintenance system etc, construction and operating costs, accidents or troubles, decommissioning status. (author)

Economic evaluation of reprocessing

International Nuclear Information System (INIS)

This paper, which also appears as an Appendix to the Final Working Group 4 report, considers the economics of the four basic options available in nuclear programmes namely: the once-through cycle; reprocessing with uranium recycle and plutonium storage; reprocessing with both uranium and plutonium recycle; and the fast reactor. These options are represented by four separate areas on a ''phase diagram'' showing the relationship between relative generating costs and uranium ore price. The basic algebra defining each component of electricity cost is given for each option. The diagram can take different forms depending upon the relative magnitudes of the costs of reprocessing and MOX fuel fabrication and whether the once-through fuel cycle is acceptable or not on grounds other than strictly economic, i.e. environmental grounds. The shortcomings of this form of presentation are also identified

Reprocessing decision: a study in policymaking under uncertainty

International Nuclear Information System (INIS)

Heising, C.D.

1978-01-01

The U.S. reprocessing decision is examined in this thesis. Decision analysis is applied to develop a rational framework for the assessment of policy alternatives. Benefits and costs for each alternative are evaluated and compared in dollar terms to determine the optimal decision. A fuel cycle simulation model is constructed to assess the economic value of reprocessing light water reactor (LWR) spent fuel and recycling plutonium. In addition, a dynamic fuel substitution model is used to estimate the economic effects of the reprocessing decision's influence on the introduction date of the liquid metal fast breeder reactor (LMFBR). Risks estimated in dollar terms for comparison with the economic values include those related to health, the environment and safety, nuclear theft and sabotage, and nuclear proliferation

Evironmental assessment factors relating to reprocessing of spent nuclear fuel

International Nuclear Information System (INIS)

1978-05-01

This document is in two parts. Part I presents the criteria and evaluation factors, based primarily on US experience, which may be used to carry out an environmental assessment of spent fuel reprocessing. The concept of As Low as is Reasonably Achievable (ALARA) is introduced in limiting radiation exposure. The factors influencing both occupational and general public radiation exposure are reviewed. Part II provides information on occupational and general public radiation exposure in relation to reprocessing taken from various sources including UNSCEAR and GESMO. Some information is provided in relation to potential accidents at reprocessing or MOX fuel refabrication plants. The magnitude of the services, energy, land use and non-radiological effluents for the reference design of reprocessing plant are also presented

Spent Nuclear Fuel Reprocessing Flowsheet. A Report by the WPFC Expert Group on Chemical Partitioning of the NEA Nuclear Science Committee

International Nuclear Information System (INIS)

Na, Chan; Yamagishi, Isao; Choi, Yong-Joon; Glatz, Jean-Paul; Hyland, Bronwyn; Uhlir, Jan; Baron, Pascal; Warin, Dominique; De Angelis, Giorgio; Luce, Alfredo; INOUE, Tadashi; Morita, Yasuji; Minato, Kazuo; Lee, Han Soo; Ignatiev, Victor V.; Kormilitsyn, Mikhail V.; Caravaca, Concepcion; Lewin, Robert G.; Taylor, Robin J.; Collins, Emory D.; Laidler, James J.

2012-06-01

Under the auspices of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues of the Fuel Cycle (WPFC) has been established to co-ordinate scientific activities regarding various existing and advanced nuclear fuel cycles, including advanced reactor systems, associated chemistry and flowsheets, development and performance of fuel and materials, and accelerators and spallation targets. The WPFC has different expert groups to cover a wide range of scientific fields in the nuclear fuel cycle. The Expert Group on Chemical Partitioning was created in 2001 to (1) perform a thorough technical assessment of separations processes in application to a broad set of partitioning and transmutation (P and T) operating scenarios and (2) identify important research, development and demonstration necessary to bring preferred technologies to a deployable stage and (3) recommend collaborative international efforts to further technological development. This report aims to collect spent nuclear fuel reprocessing flowsheet of various processes developed by member states: aqueous, pyro and fluoride volatility. Contents: 1 - Hydrometallurgy process: Standard PUREX, Extended PUREX, UREX+3, Grind/Leach; 2 - Pyrometallurgy process: pyro-process (CRIEPI - Japan), 4-group partitioning process, pyro-process (KAERI - Korea), Direct electrochemical processing of metallic fuel, PyroGreen (reduce radiotoxicity to the level of low and intermediate level waste - LILW); 3 - Fluoride volatility process: Fluoride volatility process, Uranium and protactinium removal from fuel salt compositions by fluorine bubbling, Flowsheet studies on non-aqueous reprocessing of LWR/FBR spent nuclear fuel; Appendix A: Flowsheet studies of RIAR (Russian Federation), List of contributors, Members of the expert group

Fuel reprocessing experience in India: Technological and economic considerations

International Nuclear Information System (INIS)

Prasad, A.N.; Kumar, S.V.

1983-01-01

The approach to the reprocessing of irradiated fuel from power reactors in India is conditioned by the non-availability of highly enriched uranium with the consequent need for plutonium for the fast-reactor programme. With this in view, the fuel reprocessing programme in India is developing in stages matching the nuclear power programme. The first plant was set up in Trombay to reprocess the metallic uranium fuel from the research reactor CIRUS. The experience gained in the construction and operation of this plant, and in its subsequent decommissioning and reconstruction, has not only provided the know-how for the design of subsequent plants but has indicated the fruitful areas of research and development for efficient utilization of limited resources. The Trombay plant also handled successfully, on a pilot scale, the reprocessing of irradiated thorium fuel to separate uranium-233. The second plant at Tarapur has been built for reprocessing spent fuels from the power reactors at Tarapur (BWR) and Rajasthan (PHWR). The third plant, at present under design, will reprocess the spent fuels from the power reactors (PHWR) and the Fast Breeder Test Reactor (FBTR) located at Kalpakkam. Through the above approach experience has been acquired which will be useful in the design and construction of even larger plants which will become necessary in the future as the nuclear power programme grows. The strategies considered for the sizing and siting of reprocessing plants extend from the idea of small plants, located at nuclear power station sites, to a large-size central plant, located at an independent site, serving many stations. The paper discusses briefly the experience in reprocessing uranium and thorium fuels and also in decommissioning. An attempt is made to outline the technological and economic aspects which are relevant under different circumstances and which influence the size and siting of the fuel reprocessing plants and the expected lead times for construction

Reprocessing method of ceramic nuclear fuels in low-melting nitrate molten salts

International Nuclear Information System (INIS)

Brambilla, G.; Caporali, G.; Zambianchi, M.

1976-01-01

Ceramic nuclear fuel is reprocessed through a method wherein the fuel is dispersed in a molten eutectic mixture of at least two alkali metal nitrates and heated to a temperature in the range between 200 and 300 0 C. That heated mixture is then subjected to the action of a gaseous stream containing nitric acid vapors, preferably in the presence of a catalyst such as sodium fluoride. Dissolved fuel can then be precipitated out of solution in crystalline form by cooling the solution to a temperature only slightly above the melting point of the bath

Development of remote repair robots for dissolvers in nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Sugiyama, Sen; Kunikata, Michio; Kawamura, Hironobu.

1985-01-01

For nuclear facilities, various types of remote maintenance and inspection devices have been developed to reduce radiation exposure to workers, save labor, and improve the operating rate of the plant. Existing robot technology, however, could not be employed when we were recently called upon to inspect and repair pinhole defects which had occurred in the spent fuel dissolvers of the Power Reactor and Nuclear Fuel Development Corporation's Tokai Reprocessing Plant, because the work had to be done in an extremely radioactive environment, conditions too extreme for conventional robots. For this reason, we developed highly radiation-resistant repair robots capable of fully remote-controlled operation inside the barrels of the dissolvers, which have the inconvenient shape of 270 mm inside diameter and 6 m length. The process for developing the six different repair robots and the their functions are described in this paper. This development was sponsored by the Power Reactor and Nuclear Fuel Development Corporation (PNC) under contract with Hitachi, Ltd. (author)

The threat of nuclear terrorism: from analysis to caution measures; La menace du terrorisme nucleaire: de l'analyse aux mesures de precaution

Energy Technology Data Exchange (ETDEWEB)

Schneider, M

2001-12-15

In this work are analysed the different cases of terrorism attacks, the potential sources of risks, such reprocessing plants, nuclear power plants, every facility where is stored radioactive material. The vulnerability of these facilities is also evoked. Some solutions are recommended but more specially, further thought needs to be given to that kind of problems. (N.C.)

Optimization of the sizes and dates of starting up of reprocessing plants

International Nuclear Information System (INIS)

Nagashima, Kikusaburo

1977-01-01

It is desirable to complete the nuclear fuel cycle domestically for promoting nuclear power generation in Japan, and the reprocessing of spent fuel is indispensable. However, the capacity of the reprocessing plant in PNC and the reprocessing by the commissioning to foreign countries will be insufficient by the latter half of 1980s. In the planning of the second reprocessing plant in Japan, the following problems remain yet to be solved. The international regulation and the laws in Japan regarding the storage and transport of spent fuel, the disposal of radioactive wastes, and the recycling of plutonium must be established. The consensus of the public on the necessity and the safety of fuel reprocessing must be obtained. The technical investigation about fuel reprocessing and related business must be carried out sufficiently, including the necessity of introducing the technology from abroad. The economy and various conditions for industrializing fuel reprocessing must be studied. The economy of fuel reprocessing plants, the reprocessing cost taking escalation into account, mean reprocessing cost, the optimization of the time of starting full operation and the time of starting-up, the rise of reprocessing cost due to the escalation of operational cost are explained. Numerical calculation was carried out about the second reprocessing plant in Japan, and the results are examined. (Kako, I.)

Status and trends in spent fuel reprocessing

International Nuclear Information System (INIS)

2005-09-01

The management of spent fuel arising from nuclear power production is a crucial issue for the sustainable development of nuclear energy. The IAEA has issued several publications in the past that provide technical information on the global status and trends in spent fuel reprocessing and associated topics, and one reason for this present publication is to provide an update of this information which has mostly focused on the conventional technology applied in the industry. However, the scope of this publication has been significantly expanded in an attempt to make it more comprehensive and by including a section on emerging technologies applicable to future innovative nuclear systems, as are being addressed in such international initiatives as INPRO, Gen IV and MICANET. In an effort to be informative, this publication attempts to provide a state-of-the-art review of these technologies, and to identify major issues associated with reprocessing as an option for spent fuel management. It does not, however, provide any detailed information on some of the related issues such as safety or safeguards, which are addressed in other relevant publications. This report provides an overview of the status of reprocessing technology and its future prospects in terms of various criteria in Section 2. Section 3 provides a review of emerging technologies which have been attracting the interest of Member States, especially in the international initiatives for future development of innovative nuclear systems. A historical review of IAEA activities associated with spent fuel reprocessing, traceable back to the mid-1970s, is provided in Section 4, and conclusions in Section 5. A list of references is provided at the end the main text for readers interested in further information on the related topics. Annex I summarizes the current status of reprocessing facilities around the world, including the civil operational statistics of Purex-based plants, progress with decommissioning and

Disaggregation of collective dose-a worked example based on future discharges from the Sellafield nuclear fuel reprocessing site, UK

International Nuclear Information System (INIS)

Jones, S R; Lambers, B; Stevens, A

2004-01-01

Collective dose has long been advocated as an important measure of the detriment associated with practices that involve the use of radioactivity. Application of collective dose in the context of worker protection is relatively straightforward, whereas its application in the context of discharges to the environment can yield radically different conclusions depending upon the population groups and integration times that are considered. The computer program PC-CREAM98 has been used to provide an indicative disaggregation into individual dose bands of the collective dose due to potential future radioactive discharges from the nuclear fuel reprocessing site at Sellafield in the UK. Two alternative discharge scenarios are considered, which represent a 'stop reprocessing early, minimum discharge' scenario and a 'reprocessing beyond current contracts' scenario. For aerial discharges, collective dose at individual effective dose rates exceeding 0.015 μSv y -1 is only incurred within the UK, and at effective dose rates exceeding 1.5 μSv y -1 is only incurred within about 20 km of Sellafield. The geographical distribution of collective dose from liquid discharges is harder to assess, but it appears that collective dose incurred outside the UK is at levels of individual effective dose rate below 1.5 μSv y -1 , with the majority being incurred at rates of 0.002 μSv y -1 or less. In multi-attribute utility analyses, the view taken on the radiological detriment to be attributed to the two discharge scenarios will depend critically on the weight or monetary value ascribed to collective doses incurred within the differing bands of individual dose rate

Advances in reprocessing

International Nuclear Information System (INIS)

Giraud, J.P.; Guais, J.C.

1993-01-01

In a comprehensive nuclear energy program based on Light Water Reactor, closing the nuclear fuel cycle by reprocessing the spent fuel and recycling the recovered fissile materials is a key activity which is now fully mastered at the industrial level. In France a large, modern commercial reprocessing plant called UP3 is operating at La Hague since 18 months in excellent conditions regarding products quality, plant availability, safety and waste management. At the same time, industrial capacities for plutonium recycling by MOX fuel fabrication are under operation and larger units are in construction in France and in Europe. Our customers, the utilities which are engaged in a complete closed fuel cycle in Japan, in Germany, Switzerland, Belgium, the Netherlands, and in France, are having a comprehensive industrial system available for their spent fuel management. Three main objectives are being met by this system: (1) saving natural resources by recycling energetic material: plutonium and uranium; (2) solving the waste management question by a segregating the waste according to their characteristics for a proper conditioning, in particular with vitrification for HLW; and (3) preparing the future developments of nuclear power generation with advanced reactors, and best Pu use, and keeping open progresses in long lived waste processing and disposal

Advanced teleoperation in nuclear applications: consolidated fuel reprocessing program

International Nuclear Information System (INIS)

Hamel, W.R.; Feldman, M.J.; Martin, H.L.

1984-01-01

A new generation of integrated remote maintenance systems is being developed to meet the needs of future nuclear fuel reprocessing at the Oak Ridge National Laboratory. Development activities cover all aspects of an advanced teleoperated maintenance system with particular emphasis on a new force-reflecting servomanipulator concept. The new manipulator, called the advanced servomanipulator, is microprocessor controlled and is designed to achieve force-reflection performance near that of mechanical master/slave manipulators. The advanced servomanipulator uses a gear-drive transmission which permits modularization for remote maintainability (by other advanced servomanipulators) and increases reliability. Human factors analysis has been used to develop an improved man/machine interface concept based upon colographic displays and menu-driven touch screens. Initial test and evaluation of two advanced servomanipulator slave arms and several other development components have begun. 9 references, 5 figures

World-wide redistribution of 129Iodine from nuclear fuel reprocessing facilities: Results from meteoric, river, and seawater tracer studies

International Nuclear Information System (INIS)

Moran, J.E.; Oktay, S.; Santschi, P.H.; Schink, D.R.; Fehn, U.; Snyder, G.

1999-01-01

Releases of the long-lived radioisotope of iodine, 129 I, from commercial nuclear fuel reprocessing facilities in England and France have surpassed natural, and even bomb test inventories. 129 I/ 127 I ratios measured in a variety of environmental matrices from Europe, North America and the southern hemisphere show the influence of fuel reprocessing-derived 129 I, which is transported globally via the atmosphere. Transport and cycling of I and 129 I in the hydrosphere and in soils are described based on a spatial survey of 129 I in freshwater. (author)

Safety guide data on radiation shielding in a reprocessing facility

International Nuclear Information System (INIS)

Sekiguchi, Noboru; Naito, Yoshitaka

1986-04-01

In a reprocessing facility, various radiation sources are handled and have many geometrical conditions. To aim drawing up a safety guidebook on radiation shielding in order to evaluate shielding safety in a reprocessing facility with high reliability and reasonableness, JAERI trusted investigation on safety evaluation techniques of radiation shielding in a reprocessing facility to Nuclear Safety Research Association. This report is the collection of investigation results, and describes concept of shielding safety design principle, radiation sources in reprocessing facility and estimation of its strength, techniques of shielding calculations, and definite examples of shielding calculation in reprocessing facility. (author)

Fuel reprocessing and waste management

International Nuclear Information System (INIS)

Philippone, R.L.; Kaiser, R.A.

1989-01-01

Because of different economic, social and political factors, there has been a tendency to compartmentalize the commercial nuclear power industry into separate power and fuel cycle operations to a greater degree in some countries compared to other countries. The purpose of this paper is to describe how actions in one part of the industry can affect the other parts and recommend an overall systems engineering approach which incorporates more cooperation and coordination between individual parts of the fuel cycle. Descriptions are given of the fuel cycle segments and examples are presented of how a systems engineering approach has benefitted the fuel cycle. Descriptions of fuel reprocessing methods and the waste forms generated are given. Illustrations are presented describing how reprocessing options affect waste management operations and how waste management decisions affect reprocessing

Modeling for thermodynamic activities of components in simulated reprocessing solutions

International Nuclear Information System (INIS)

Sasahira, Akira; Hoshikawa, Tadahiro; Kawamura, Fumio

1992-01-01

Analyses of chemical reactions have been widely carried out for soluble fission products encountered in nuclear fuel reprocessing. For detailed analyses of reactions, a prediction of the activity or activity coefficient for nitric acid, water, and several nitrates of fission products is needed. An idea for the predicted nitric acid activity was presented earlier. The model, designated the hydration model, does not predict the nitrate activity. It did, however, suggest that the activity of water would be a function of nitric acid activity but not the molar fraction of water. If the activities of nitric acid and water are accurately predicted, the activity of the last component, nitrate, can be calculated using the Gibbs-Duhem relation for chemical potentials. Therefore, in this study, the earlier hydration model was modified to evaluate the water activity more accurately. The modified model was experimentally examined in stimulated reprocessing solutions. It is concluded that the modified model was suitable for water activity, but further improvement was needed for the activity evaluation of nitric acid in order to calculate the nitrate activity

Characterization of the head end cells at the West Valley Nuclear Fuel Reprocessing Plant

International Nuclear Information System (INIS)

Vance, R.F.

1986-11-01

The head-end cells at the West Valley Nuclear Fuel Reprocessing Plant are characterized in this report. These cells consist of the Process Mechanical Cell (PMC) where irradiated nuclear fuel was trimmed of excess hardware and sheared into short segments; and the General Purpose Cell (GPC) where the segments were collected and stored prior to dissolution, and leached hulls were packaged for disposal. Between 1966 and 1972, while Nuclear Fuels Services operated the plant, these cells became highly contaminated with radioactive materials. The purpose of this characterization work was to develop technical information as a basis of decontamination and decommissioning planning and engineering. It was accomplished by performing remote in-cell visual examinations, radiation surveys, and sampling. Supplementary information was obtained from available written records, out-of-cell inspections, and interviews with plant personnel

Fuel reprocessing and environmental problem

International Nuclear Information System (INIS)

Ichikawa, Ryushi

1977-01-01

The radioactive nuclides which are released from the reprocessing plants of nuclear fuel are 137 Cs, 106 Ru, 95 Zr and 3 H in waste water and 85 Kr in the atmosphere. This release affects the environment for example, the reprocessing plant of the Nuclear Fuel Service Co in the USA releases about 2 x 10 5 Ci/y of 85 Kr, which is evaluated as about 0.025 mr/y as external exposure dose. The radioactivity in milk around this plant was measured as less than 10 pCi/lit of 129sup(I. The radioactive concentration in the sea, especially in fish and shellfish, was measured near the reprocessing plant of Windscale in UK. The radioactive release rate from this plants more than 10)5sup( Ci/y as the total amount of )137sup(Cs, )3sup(H, )106sup(Ru, )95sup(Zr, )95sup(Nb, )90sup(Sr, )144sup(Ce, etc., and the radioactivity in seaweeds near Windscale is about 400 pCi/g as the maximum value, and the mayonnaise which was made of this seaweeds contained about 1 pCi/g of )106sup(Ru, which is estimated as about 7 mr/y for the digestive organ if 100 g is eaten every day. On the other hand, the experimental result is presented for the reprocessing plant of La Hague in France, in which the radioactive release rate from this plant is about 10)4sup( Ci/y, and the radioactivity in sea water and shellfish is about 4 pCi/l of )106sup(Ru and about 400 pCi/kg of )137 Cs, respectively, near this plant. The philosophy of ALAP (as low as practicable) is also applied to reprocessing plants. (Nakai, Y.)

Iodine-129 in the environment of a nuclear fuel reprocessing plant: Pt. 5

International Nuclear Information System (INIS)

Hauschild, J.; Aumann, D.C.

1989-01-01

A field investigation of the transfer of 129 I and of natural 127 I in the soil-pasture-cow-milk/meat pathway has been carried out at a dairy farm situated 5400 m to the north of the small Karlsruhe nuclear fuel reprocessing plant. Soil and herbage samples were collected during the period between April 1986 and April 1987. Milk samples were collected during the 1986 grazing season. The concentrations of 129 I and 127 I were determined in all soil, herbage and milk samples. (author)

Future of the reprocessing business at the RT-1 plant

International Nuclear Information System (INIS)

Bukharin, O.

1995-01-01

Economic viability of reprocessing operations at the RT-1 plant is provided by the contracts with nuclear utilities from Finland and Hungary. Finland will stop sending fuel to Mayak for reprocessing after 1996. Hungary will be capable to resolve the problem of spent fuel domestically some time in the future. This increases vulnerability of the reprocessing business at Mayak to future political uncertainties. (author)

Modeling of Pu(IV) extraction and HNO3 speciation in nuclear fuel reprocessing

International Nuclear Information System (INIS)

De-Sio, S.

2012-01-01

The PUREX process is a solvent extraction method dedicated to the reprocessing of irradiated nuclear fuel in order to recover pure uranium and plutonium from aqueous solutions of concentrated nitric acid. The tri-n-butylphosphate (TBP) is used as the extractant in the organic phase. The aim of this thesis work was to improve the modeling of liquid-liquid extraction media in nuclear fuel reprocessing. First, Raman and 14 N NMR measurements, coupled with theoretical calculations based on simple solutions theory and BIMSA modeling, were performed in order to get a better understanding of nitric acid dissociation in binary and ternary solutions. Then, Pu(IV) speciation in TBP after extraction from low nitric acid concentrations was investigated by EXAFS and vis-NIR spectroscopies. We were able to show evidence of the extraction of Pu(IV) hydrolyzed species into the organic phase. A new structural study was conducted on An(VI)/TBP and An(IV)/TBP complexes by coupling EXAFS measurements with DFT calculations. Finally, extraction isotherms modeling was performed on the Pu(IV)/HNO 3 /H 2 O/TBP 30%/dodecane system (with Pu at tracer scale) by taking into account deviation from ideal behaviour in both organic and aqueous phases. The best modeling was obtained when considering three plutonium (IV) complexes in the organic phase: Pu(OH) 2 (NO 3 ) 2 (TBP) 2 , Pu(NO 3 ) 4 (TBP) 2 and Pu(NO 3 ) 4 (TBP) 3 . (author) [fr

Ion chromatographic separation for analysis of radiostrontium in nuclear reprocessing solutions of high ionic strength

International Nuclear Information System (INIS)

Lamb, J.D.; Nordmeyer, F.R.; Drake, P.A.; Elder, M.P.; Miles, R.W.

1989-01-01

An ion chromatography (IC)-based method was developed for Sr 2+ concentration and separation showing high recoveries of strontium. This procedure permits complete automation. One of the potential weaknesses of the IC approach to sample preconcentration, i.e. sensitivity to solutions of high acid content, common in nuclear reprocessing solution, has been overcome by a novel application of acid suppression technology. (author) 12 refs.; 8 figs.; 3 tabs

Status of power reactor fuel reprocessing in India

International Nuclear Information System (INIS)

Kansra, V.P.

1999-01-01

Spent fuel reprocessing in India started with the commissioning of the Trombay Plutonium Plant in 1964. This plant was intended for processing spent fuel from the 40 MWth research reactor CIRUS and recovering plutonium required for the research and development activities of the Indian Atomic Energy programme. India's nuclear energy programme aims at the recycle of plutonium in view of the limited national resources of natural uranium and abundant quantities of thorium. This is based on the approach which aims at separating the plutonium from the power reactor spent fuel, use it in the fast reactors to breed 233 U and utilise the 233 U generated to sustain a virtually endless source of power through thorium utilisation. The separated plutonium is also being utilised to fabricate MOX fuel for use in thermal reactors. Spent fuel treatment and extracting plutonium from it makes economic sense and a necessity for the Indian nuclear power programme. This paper describes the status and trends in the Indian programme for the reprocessing of power reactor fuels. The extraction of plutonium can also be seen as a far more positive approach to long-term waste management. The closed cycle approach visualised and pursued by the pioneers in the field is now steadily moving India towards the goal of a sustainable source of power through nuclear energy. The experience in building, operating and refurbishing the reprocessing facilities for uranium and thorium has resulted in acquiring the technological capability for designing, constructing, operating and maintaining reprocessing plants to match India's growing nuclear power programme. (author)

Trivalent lanthanide/actinide separation in the spent nuclear fuel wastes' reprocessing

International Nuclear Information System (INIS)

Narbutt, J.; Krejzler, J.

2006-01-01

Separation of trivalent actinides, in particular americium and curium, from lanthanides is an important step in an advanced partitioning process for future reprocessing of spent nuclear fuels. Since the trivalent actinides and lanthanides have similar chemistries, it is rather difficult to separate them from each other. The aim of presented work was to study solvent extraction of Am(III) and Eu(III) in a system containing diethylhemi-BTP (6-(5,6-diethyl-1,2,4-triazin-3-yl)-2,2'-bipyridine) and COSAN (protonated bis(chlorodicarbollido)cobalt(III)). The system was chosen by several groups working in the integrated EC research Project EUROPART. Several physicochemical properties of the extraction system were analyzed and discussed

Microbial transformations of radionuclides released from nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Francis, A.J.

2007-01-01

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. (author)

Apparatus and method for reprocessing and separating spent nuclear fuels

International Nuclear Information System (INIS)

Krikorian, O.H.; Grens, J.Z.; Parrish, W.H.; Coops, M.S.

1983-01-01

A method and apparatus for separating and reprocessing spent nuclear fuels includes a separation vessel housing a molten metal solvent in a reaction region, a reflux region positioned above and adjacent to the reaction region, and a porous filter member defining the bottom of the separation vessel in a supporting relationship with the metal solvent. Spent fuels are added to the metal solvent. A non-oxidizing nitrogen-containing gas is introduced into the separation vessel, forming solid actinide nitrides in the metal solvent from actinide fuels, while leaving other fission products in solution. A pressure of about 1.1 to 1.2 atm is applied in the reflux region, forcing the molten metal solvent and soluble fission products out of the vessel, while leaving the solid actinide nitrides in the separation vessel. (author)

Reprocessing technology of liquid metal cooled fast breeder reactor fuel

International Nuclear Information System (INIS)

Baetsle, L.H.; Broothaerts, J.; Heylen, P.R.; Eschrich, H.; Geel, J. van

1974-11-01

All the important aspects of LMFBR fuel reprocessing are critically reviewed in this report. Storage and transportation techniques using sodium, inert gas, lead, molten salts and organic coolants are comparatively discussed in connection with cooling time and de-activation techniques. Decladding and fuel disaggregation of UO 2 -PuO 2 fuel are reviewed according to the present state of R and D in the main nuclear powers. Strong emphasis is put on on voloxidation, mechanical pulverization and molten salt disaggregation in connection with volatilization of gaseous fission products. Release of fission gases and the resulting off-gas treatment are discussed in connection with cooling time, burn up and dissagregation techniques. The review is limited to tritium, iodine xenon-krypton and radioactive airborne particulates. Dissolution, solvent extraction and plutonium purification problems specifically connected to LMFBR fuel are reviewed with emphasis on the differences between LWR and fast fuel reprocessing. Finally the categories of wastes produced by reprocessing are analysed according to their origin in the plant and their alpha emitters content. The suitable waste treatment techniques are discussed in connection with the nature of the wastes and the ultimate disposal technique. (author)

Thoria-based nuclear fuels thermophysical and thermodynamic properties, fabrication, reprocessing, and waste management

CERN Document Server

Bharadwaj, S R

2013-01-01

This book presents the state of the art on thermophysical and thermochemical properties, fabrication methodologies, irradiation behaviours, fuel reprocessing procedures, and aspects of waste management for oxide fuels in general and for thoria-based fuels in particular. The book covers all the essential features involved in the development of and working with nuclear technology. With the help of key databases, many of which were created by the authors, information is presented in the form of tables, figures, schematic diagrams and flow sheets, and photographs. This information will be useful for scientists and engineers working in the nuclear field, particularly for design and simulation, and for establishing the technology. One special feature is the inclusion of the latest information on thoria-based fuels, especially on the use of thorium in power generation, as it has less proliferation potential for nuclear weapons. Given its natural abundance, thorium offers a future alternative to uranium fuels in nuc...

Design of vertical thermosiphon reboilers for operation under vacuum conditions application in nuclear fuel reprocessing

International Nuclear Information System (INIS)

Moore, M.J.C.; Keys, M.H.; Plumb, G.R.

1988-01-01

Reprocessing of nuclear fuel requires concentration of uranium, plutonium and other active effluent streams at various stages for purification, storage or solidification. This is usually achieved by evaporation and in U.K. plant such processes are often carried out under reduced pressure. For high throughput streams, there are considerable advantages in using vertical thermosiphon systems for evaporation and for recovery of nitric acid. However, data for such systems at reduced pressure is limited and the development by John Brown E and C Ltd of a computer program for reliable prediction of thermosiphon performance was carried out on behalf of British Nuclear Fuels Plc using data from operating plant. (author)

International and institutional aspects of reprocessing and plutonium management

International Nuclear Information System (INIS)

1978-09-01

Various institutional alternatives applicable to reprocessing, plutonium management and recycle are considered, not as a definitive analysis but rather as a basis for identifying the institutional approaches and measures which the Working Group might wish to examine more thoroughly. Seven alternatives arrangements for reprocessing are presented. These range from suspending the operation of existing reprocessing plants through placing national facilities under safeguards to limiting reprocessing to a few large facilities subject to plutonium management, multinational or international control. Finally, the comprehensive alternative of an International Nuclear Fuel Authority with worldwide responsibility for reprocessing and plutonium management is considered. Plutonium management alternatives to complement the reprocessing options, are then outlined. These include national discretion on the separation and disposition of plutonium under safeguards, an agreed Code of Practice for plutonium management at national facilities and the international storage of plutonium. The advantages and disadvantages of the alternative are discussed tentatively. It is recognised that the alternatives are presented in a simplified form and that their elements can be combined or separated in many ways. Although strengthening the institutions relating to the peaceful uses of nuclear energy is imperative and can contribute to non-proliferation, such arrangements might open other proliferation risks through the spread of sensitive materials, facilities and technology. While there are risks with any fuel cycle, where plutonium in quantity is separated these risks are of a high order. Although these can be mitigated, they will have to be set against the energy and economic case for reprocessing and alternatives other than plutonium considered

Decommissioning of nuclear reprocessing plants French past experience and approach to future large scale operations

International Nuclear Information System (INIS)

Jean Jacques, M.; Maurel, J.J.; Maillet, J.

1994-01-01

Over the years, France has built up significant experience in dismantling nuclear fuel reprocessing facilities or various types of units representative of a modern reprocessing plant. However, only small or medium scale operations have been carried out so far. To prepare the future decommissioning of large size industrial facilities such as UP1 (Marcoule) and UP2 (La Hague), new technologies must be developed to maximize waste recycling and optimize direct operations by operators, taking the integrated dose and cost aspects into account. The decommissioning and dismantling methodology comprises: a preparation phase for inventory, choice and installation of tools and arrangement of working areas, a dismantling phase with decontamination, and a final contamination control phase. Detailed description of dismantling operations of the MA Pu finishing facility (La Hague) and of the RM2 radio metallurgical laboratory (CEA-Fontenay-aux-Roses) are given as examples. (J.S.). 3 tabs

Development of safety evaluation technology for fire and explosion in reprocessing plant

International Nuclear Information System (INIS)

Miura, Akihiko

2005-01-01

Based on some lessons learned from the accidents in the reprocessing plant all over the world, Japan Nuclear Cycle Development Institute (JNC) has researched and developed the safety technologies for the reprocessing plants and its related facilities. This paper describes some accidental information around the reprocessing plants and its related research activities in JNC. (author)

Safety aspects in fuel reprocessing and radioactive waste management

International Nuclear Information System (INIS)

Agarwal, K.

2018-01-01

Nuclear energy is used for generation of electricity and for production of a wide range of radionuclides for use in research and development, healthcare and industry. Nuclear industry uses nuclear fission as source of energy so a large amount of energy is available from very small amount of fuel. As India has adopted c losed fuel cycle , spent nuclear fuel from nuclear reactor is considered as a material of resource and reprocessed to recovery valuable fuel elements. Main incentive of reprocessing is to use the uranium resources effectively by recovering/recycling Pu and U present in the spent fuel. This finally leads to a very small percentage of residual material present in spent nuclear fuel requiring their management as radioactive waste. Another special feature of the Indian Atomic Energy Program is the attention paid from the very beginning to the safe management of radioactive waste

Direction of reprocessing technology development based on 30 years operation of Tokai reprocessing plant

International Nuclear Information System (INIS)

Nomura, S; Tanaka, T.; Ohshima, H.

2006-01-01

Full text: Full text: Recent global interest focuses the possibility of recycling of spent fuel with advanced fast reactor fuel cycle system. Goal of closed fuel cycle is to achieve the maximum use of uranium resources and minimum disposal of waste by multi recycle of TRU as a competitive nuclear energy system. The future reprocessing and fuel fabrication system should be synchronized completely with the advanced reactor system and waste treatment and disposal back-end system to complete closed fuel cycle. To realize such system, current reprocessing system should be changed to handle Pu-U-Minor Actinide with more reductions in the cost and less waste volume, as well as an inherent proliferation resistance. For the successful industrialization of advanced reprocessing technology, it is necessary to combine three key elements of R and D efforts, engineering base demonstration and experiences of plant operation. Tokai Reprocessing Facilities licensed a maximum capacity of 0.7tHM/day began a hot operation in 1977 and reprocessed l,100tHM U02 spent fuel and 20tHM ATR-MOX with a continuous technological improvements under IAEA full scope safeguards. With 30 years experience, candidate of key technologies proposed for realizing the next advanced reprocessing are as follows: 1) Simplified co-extraction process of Pu-Np-U by using multistage centrifugal extractors in stead of pulsed columns; 2) Corrosion free components in acid condition by using corrosion resistant refractory alloys and ceramics; 3) Co-conversion technology to MA containing MOX powder by micro-wave heating method for a short process for MA containing MOX pellets fabrication; 4) Advanced verification of high level radioactive liquid waste combining separation technology of TRU and LLFP elements; 5) Advanced chemical analysis and monitoring system for TRU elements in a plant. These advanced reprocessing technologies will be applied mainly to reprocess the LWR spent fuel accumulated past and future

Confinement of ruthenium oxides volatilized during nuclear fuels reprocessing

International Nuclear Information System (INIS)

Maas, E.T. Jr.; Longo, J.M.

1980-01-01

While many materials have been suggested and employed as trapping agents for gaseous oxides of fission product ruthenium volatilized during nuclear fuels reprocessing, none that is known to form thermodynamically stable compounds with rutheniunm has been utilized. We have employed alkaline earth metal compounds for this purpose because of their ability to form stable mixed metal oxide phases with ruthenium. Results of experiments in which RuO 4 was volatilized from either a solid source (RuO 2 .xH 2 O) or from solution [Ru(NO)(NO 3 ) 3 ] in HNO 3 and passed through beds of alkaline earth metal carbonates and calcium oxide held at 600 to 750 0 C have demonstrated that compounds of formulation MRuO 3 (M = calcium, strontium, barium) are formed. Under oxidizing conditions, these materials exist as stable ceramic phases, whereas under reducing conditions, they are transformed into intimate mixtures of the alkaline earth metal oxide and nonvolatile ruthenium metal

Thermochemical properties of media for pyrometallurgical nuclear fuel reprocessing

International Nuclear Information System (INIS)

Hosoya, Yuji; Terai, Takayuki

1998-01-01

Molten chloride/cadmium system is considered to be applied to a solvent in pyrochemical reprocessing of spent nuclear fuel. In this work, phase diagrams for molten chloride systems were constructed, using NdCl 3 as an imitative substance in place of UCl 3 or PuCl 3 . Hastelloy-X (Ni/Cr21/Fe18/Mo9/W) was examined as a structural material for the corrosion-resistance against molten chloride baths containing NdCl 3 . The process of corrosion was thermochemically discussed and the form of the corrosion was illustrated. Rutherford backscattering spectroscopy was successfully applied to determine the elemental distribution profile of specimens tested on the compatibility with molten chloride mixture at elevated temperature. Ferritic steel was also examined as another candidate material for the compatibility with molten cadmium covered with LiCl-KCl eutectic salt. Variation of near-surface composition was observed by comparing the results of Rutherford backscattering spectroscopy obtained before and after the dipping. (author)

Mass spectrometry in nuclear technology - a review of application of thermal ionization mass spectrometry in fuel reprocessing plants. PD-7-1

International Nuclear Information System (INIS)

Dakshinamoorthy, A.

2007-01-01

Mass spectrometry finds the widespread application in nuclear science and technology due to the fact that it can be employed for isotope composition measurements of different elements of interest and also concentration measurements of these elements using isotope dilution techniques. Thermal ionization mass spectrometer (TIMS), Inductively coupled plasma mass spectrometer (ICP-MS) and gas chromatography mass spectrometer (GC-MS) are the different types of mass spectrometers used in nuclear industry for the analyses of isotope composition of special nuclear material, trace impurities in nuclear fuels and components and characterization of various solvents respectively. Among them, TIMS plays a vital role in the nuclear fuel cycle in determining precisely the isotope composition of uranium, plutonium, D/H ratio in heavy water etc. TIMS is an indispensable analytical tool for nuclear material accounting at the input stage of a reprocessing plant by carrying out precise and accurate concentration measurement of plutonium and uranium by isotope dilution mass spectrometry (IDMS). It is the only accepted measurement technique for the purpose because of its high precision, better sensitivity and no quantitative separation is needed. The isotope abundance measurements of uranium and plutonium at this point are also useful for burn-up studies and isotope correlations. Mass spectrometric analysis of uranium and plutonium is also required for nuclear data measurements and calibrating other chemical methods

Conditions for Australian consent to reprocessing

International Nuclear Information System (INIS)

Anon.

1980-01-01

This article contains the text of the statement by the Australian Minister for Foreign Affairs to the House of Representatives, Noember 1980, on conditions for Australian consent to the reprocessing of nuclear material of Australian origin

Available Reprocessing and Recycling Services for Research Reactor Spent Nuclear Fuel

International Nuclear Information System (INIS)

2017-01-01

The high enriched uranium (HEU) take back programmes will soon have achieved their goals. When there are no longer HEU inventories at research reactors and no commerce in HEU for research reactors, the primary driver for the take back programmes will cease. However, research reactors will continue to operate in order to meet their various mission objectives. As a result, inventories of low enriched uranium spent nuclear fuel will continue to be created during the research reactors' lifetime and, therefore, there is a need to develop national final disposition routes. This publication is designed to address the issues of available reprocessing and recycling services for research reactor spent fuel and discusses the various back end management aspects of the research reactor fuel cycle.

Radiological impact of emissions from reprocessing plants during normal operation

International Nuclear Information System (INIS)

Bonka, H.; Gruendler, D.; Hesel, D.; Muenster, M.; Schmidtlein, P.; Suender, B.

1977-01-01

When comparing the expected radiation exposure due to emissions from reprocessing plants with those from nuclear power plants it can be seen that the emissions from reprocessing plants contribute much more to the radiation exposure of the population than those from nuclear power plants. In the vicinity of reprocessing plants the highest contributions to the radiation exposure of the population are delivered by the following radionuclides: T, C 14 , Kr 85 , Sr 90 , Ru 106 , I 129 , Cs 134 , Cs 137 and Ce 144 as will as the Pu- and Cm-isotopes. Among these nuclides T, C 14 , Kr 85 und I 129 are globally distributed. While for T the contribution to the collective dose due to globally distributed T is small in comparison with the first pass exposure, the global contribution predominates for C 14 and Kr 85 . If an integration time of less than 10 5 years is considered, the contribution due to first pass exposure predominates for I 129 . When taking the radiation protection of the population into consideration, it seems sensible to retain 10% of T, 80 to 90% of C 14 , 90% of Kr 85 and 99,5% of I 129 in reprocessing plants and dispose of this material in a controlled manner. The fraction of the aerosols released should be about 10 -9 . Considering the global effects and the increasing number of nuclear power plants and reprocessing plants, an international agreement should be reached on these matters. (orig.) [de

Green light for Japanese reprocessing

International Nuclear Information System (INIS)

Patermann, C.

1981-01-01

In the last few years, international discussions of peaceful nuclear energy use and non-proliferation have been greatly influenced by the attitude of the US Government. Since the mid-Seventies, in the Carter area, this attitude has changed due to the fear that world-wide use of so-called sensitive technologies, i.e. uranium enrichment, reprocessing, and fast breeder development may increase the hazard of misuse for the production of nuclear weapons. (orig.) [de

Removal of carbon dioxide in reprocessing spent nuclear fuel off gas by adsorption

International Nuclear Information System (INIS)

Fukumatsu, Teruki; Munakata, Kenzo; Tanaka, Kenji; Yamatsuki, Satoshi; Nishikawa, Masabumi

1998-01-01

The off gas produced by reprocessing spent nuclear fuel includes various radioactivities and these nuclei should be removed. In particular, 14 C mainly released as the form of carbon dioxide is one of the most required gaseous radioactivities to be removed because it has long a half-life. One of the methods to remove gaseous nuclei is the use of adsorption technique. The off gas contains water vapor which influences adsorption process of carbon dioxide. In this report, behavior of adsorption of carbon dioxide on various adsorbent and influence on adsorption behavior of carbon dioxide by containing water vapor are discussed. (author)

The economic influence of reprocessing strategy in the early stages of a commercial breeder programme

International Nuclear Information System (INIS)

Pounder, F.

1982-01-01

The effect on reprocessing cost of constructing fast reactors in nuclear parks is examined and compared with carrying out reprocessing for a range of installation programmes of fast reactor in central reprocessing facilities. Consideration is also given to the economics of storing irradiated fuel to improve the load factor of reprocessing plants and to reprocessing both thermal reactor and fast reactor fuel in a common plant. (author)

Spent fuel reprocessing and minor actinide partitioning safety related research at the UK National Nuclear Laboratory

International Nuclear Information System (INIS)

Carrott, Michael; Flint, Lauren; Gregson, Colin; Griffiths, Tamara; Hodgson, Zara; Maher, Chris; Mason, Chris; McLachlan, Fiona; Orr, Robin; Reilly, Stacey; Rhodes, Chris; Sarsfield, Mark; Sims, Howard; Shepherd, Daniel; Taylor, Robin; Webb, Kevin; Woodall, Sean; Woodhead, David

2015-01-01

The development of advanced separation processes for spent nuclear fuel reprocessing and minor actinide recycling is an essential component of international R and D programmes aimed at closing the nuclear fuel cycle around the middle of this century. While both aqueous and pyrochemical processes are under consideration internationally, neither option will gain broad acceptance without significant advances in process safety, waste minimisation, environmental impact and proliferation resistance; at least when compared to current reprocessing technologies. The UK National Nuclear Laboratory (NNL) is developing flowsheets for innovative aqueous separation processes. These include advanced PUREX options (i.e. processes using tributyl phosphate as the extractant for uranium, plutonium and possibly neptunium recovery) and GANEX (grouped actinide extraction) type processes that use diglycolamide based extractants to co-extract all transuranic actinides. At NNL, development of the flowsheets is closely linked to research on process safety, since this is essential for assessing prospects for future industrialisation and deployment. Within this context, NNL is part of European 7. Framework projects 'ASGARD' and 'SACSESS'. Key topics under investigation include: hydrogen generation from aqueous and solvent phases; decomposition of aqueous phase ligands used in separations prior to product finishing and recycle of nitric acid; dissolution of carbide fuels including management of organics generated. Additionally, there is a strong focus on use of predictive process modelling to assess flowsheet sensitivities as well as engineering design and global hazard assessment of these new processes. (authors)

The Planning of a Small Pilot Plant for Development Work on Aqueous Reprocessing of Nuclear Fuels

Energy Technology Data Exchange (ETDEWEB)

Sjoeborg, T U; Haeffner, E; Hultgren, Aa

1963-10-15

A shielded volume (42 m{sup 3}) in the hot laboratory at Kjeller, Norway, has been used for the installation of a small pilot plant intended for studies on nuclear fuel reprocessing. During the first period of operation (1963) a plutonium separation method (the Silex process) developed at AB Atomenergi will be studied. This document is a description of the project during the stage of technical planning and chemical process development.

Air conditioning facilities in a fuel reprocessing plant

International Nuclear Information System (INIS)

Kawasaki, Michitaka; Oka, Tsutomu

1987-01-01

Reprocessing plants are the facilities for separating the plutonium produced by nuclear reaction and unconsumed remaining uranium from fission products in the spent fuel taken out of nuclear reactors and recovering them. The fuel reprocessing procedure is outlined. In order to ensure safety in handling radioactive substances, triple confinement using vessels, concrete cells and buildings is carried out in addition to the prevention of criticality and radiation shielding, and stainless steel linings and drip trays are installed as occasion demands. The ventilation system in a reprocessing plant is roughly divided into three systems, that is, tower and tank ventilation system to deal with offgas, cell ventilation system for the cells in which main towers and tanks are installed, and building ventilation system. Air pressure becomes higher from tower and tank system to building system. In a reprocessing plant, the areas in a building are classified according to dose rate. The building ventilation system deals with green and amber areas, and the cell ventilation system deals with red area. These three ventilation systems are explained. Radiation monitors are installed to monitor the radiation dose rate and air contamination in working places. The maintenance and checkup of ventilation systems are important. (Kako, I.)

A technical review of liquid/liquid and solid/liquid separation equipment in the field of nuclear-fuel reprocessing

International Nuclear Information System (INIS)

Vassallo, G.

1981-01-01

Liquid/liquid extraction is generally accepted as the preferred method in nuclear-fuel reprocessing. However, although many types of liquid/liquid contactors are available, only a few meet the stringent specifications set by the nuclear industry. This report discusses the criteria for contactor selection and then reviews the most important types, namely packed columns, pulsed columns, mixer-setters and centrifugal contactors. Finally, a short section concerned with solid/liquid separations is included because of the possible deleterious effects caused by solids in liquid/liquid contactors

Technical study report on reprocessing system

International Nuclear Information System (INIS)

Tanaka, Hiroshi; Kasai, Yoshimitsu; Kawamura, Fumio

2000-07-01

The feasibility studies on commercialized fast breeder reactor (FBR) recycle system, in which reactor system and recycle technologies are related on consideration, are performed considering the attainable perspectives for the followings: ensuring safety, economic competitiveness to future LWRs, efficient utilization of resources, reduction of environmental burden, and enhancement of nuclear non-proliferation. In the studies of Reprocessing system of FBR, evaluation was made for the non-aqueous reprocessing of pyrochemical and fluoride volatility process and also for the aqueous reprocessing with a view to streamlining. As a result, it was estimated that each system has prospects of coming into practical use in terms of technique. In the economical efficiency assessment, it was estimated to have economic competitiveness to future LWRs. And the technical research items of each system are picked out. Hereafter, more detail design study will be performed for each system. (author)

Silver iodide reduction in aqueous solution: application to iodine enhanced separation during spent nuclear fuels reprocessing

International Nuclear Information System (INIS)

Badie, Jerome

2002-01-01

Silver iodide is a key-compound in nuclear chemistry either in accidental conditions or during the reprocessing of spent nuclear fuel. In that case, the major part of iodine is released in molecular form into the gaseous phase at the time of dissolution in nitric acid. In French reprocessing plants, iodine is trapped in the dissolver off-gas treatment unit by two successive steps: the first consists in absorption by scrubbing with a caustic soda solution and in the second, residual iodine is removed from the gaseous stream before the stack by chemisorption on mineral porous traps made up of beds of amorphous silica or alumina porous balls impregnated with silver nitrate. Reactions of iodine species with the impregnant are assumed to lead to silver iodide and silver iodate. Enhanced separation policy would make necessary to recover iodine from the filters by silver iodide dissolution during a reducing treatment. After a brief silver-iodine chemical bibliographic review, the possible reagents listed in the literature were studied. The choice has been made to use ascorbic acid and hydroxylamine. An experimental work on silver iodide reduction by this two compounds allowed us to determinate reaction products, stoichiometry and kinetics parameters. Finally, the process has been initiated on stable iodine loaded filters samples. (author) [fr

Gas chromatographic analysis of extractive solvent in reprocessing plants

International Nuclear Information System (INIS)

Marlet, B.

1984-01-01

Operation of a reprocessing plant using the Purex process is recalled and analytical controls for optimum performance are specified. The aim of this thesis is the development of analytical methods using gas chromatography required to follow the evolution of the extraction solvent during spent fuel reprocessing. The solvent at different concentrations, is analysed along the reprocessing lines in organic or aqueous phases. Solvent degradation interferes with extraction and decomposition products are analysed. The solvent becomes less and less efficient, also it is distilled and quality is checked. Traces of solvent should also be checked in waste water. Analysis are made as simple as possible to facilitate handling of radioactive samples [fr

Fast reactor fuel reprocessing. An Indian perspective

International Nuclear Information System (INIS)

Natarajan, R.; Raj, Baldev

2005-01-01

The Department of Atomic Energy (DAE) envisioned the introduction of Plutonium fuelled fast reactors as the intermediate stage, between Pressurized Heavy Water Reactors and Thorium-Uranium-233 based reactors for the Indian Nuclear Power Programme. This necessitated the closing of the fast reactor fuel cycle with Plutonium rich fuel. Aiming to develop a Fast Reactor Fuel Reprocessing (FRFR) technology with low out of pile inventory, the DAE, with over four decades of operating experience in Thermal Reactor Fuel Reprocessing (TRFR), had set up at the India Gandhi Center for Atomic Research (IGCAR), Kalpakkam, R and D facilities for fast reactor fuel reprocessing. After two decades of R and D in all the facets, a Pilot Plant for demonstrating FRFR had been set up for reprocessing the FBTR (Fast Breeder Test Reactor) spent mixed carbide fuel. Recently in this plant, mixed carbide fuel with 100 GWd/t burnup fuel with short cooling period had been successfully reprocessed for the first time in the world. All the challenging problems encountered had been successfully overcome. This experience helped in fine tuning the designs of various equipments and processes for the future plants which are under construction and design, namely, the DFRP (Demonstration Fast reactor fuel Reprocessing Plant) and the FRP (Fast reactor fuel Reprocessing Plant). In this paper, a comprehensive review of the experiences in reprocessing the fast reactor fuel of different burnup is presented. Also a brief account of the various developmental activities and strategies for the DFRP and FRP are given. (author)

A safety evaluation of fire and explosion in nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Nishio, Gunji; Takada, Junichi; Tukamoto, Michio; Watanabe, Kouji; Miyata, Teijirou

1996-01-01

The demonstration test was performed in JAERI to prove the adequacy of a safety evaluation for an air-ventilation system in the case of solvent fire and red-oil explosion in a nuclear fuel reprocessing plant. The test objectives were to obtain data of the safety evaluation on a thermofluid behavior and a confinement effect of radioactive materials during fire and explosion while the system is operating in a cell. The computer code was developed to evaluate the safety of associated network in the ventilation system and to estimate the confinement of radioactive materials in the system. The code was verified by comparison of code calculations with results of the demonstration test. (author)

Compilation of papers presented to the KTG conference on 'Advanced LWR fuel elements: Design, performance and reprocessing', 17-18 November 1988, Karlsruhe Nuclear Research Center

International Nuclear Information System (INIS)

Bahm, W.

1989-05-01

The two expert groups of the Nuclear Society (KTG), 'chemistry and waste disposal' and 'fuel elements' discussed interdisciplinary problems concerning the development and reprocessing of advanced fuel elements. The 10 lectures deal with waste disposal, mechanical layout, operating behaviour, operating experiences and new developments of fuel elements for water moderated reactors as well as operational experiences of the Karlsruhe reprocessing plant (WAK) with reprocessing of high burnup LWR and MOX fuel elements, the distribution of fission products, the condition of the fission products during dissolution and with the effects of the higher burnup of fuel elements on the PUREX process. (DG) [de

Reprocessing techniques of LWR spent fuel for reutilization in hybrid systems and IV generation reactors

Energy Technology Data Exchange (ETDEWEB)

Aruquipa, Wilmer; Velasquez, Carlos E.; Pereira, Claubia; Veloso, Maria Auxiliadora F.; Costa, Antonella L. [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Barros, Graiciany de P. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

2017-07-01

Since the era of nuclear technology begins, nuclear reactors have been produced spent fuel. This spent fuel contains material that could be recycle and reprocessed by different processes. All these processes aim to reduce the contribution to the final repository through the re-utilization of the nuclear material. Therefore, some new reprocessing options with non-proliferation characteristics have been proposed and the goal is to compare the different techniques used to maximize the effectiveness of the spent fuel utilization and to reduce the volume and long-term radiotoxicity of high-level waste by irradiation with neutron with high energy such as the ones created in hybrid reactors. In order to compare different recovery methods, the cross sections of fuels are calculated with de MCNP code, the first set consists of thorium-232 spiked with the reprocessed material and the second set in depleted uranium that containing 4.5% of U-235 spiked with the reprocessed material; These sets in turn are compared with the cross section of the UO{sub 2} in order to evaluate the efficiency of the reprocessed fuel as nuclear fuel. (author)

Cleanup of a HLW nuclear fuel-reprocessing center using 3-D database modeling technology

International Nuclear Information System (INIS)

Sauer, R.C.

1992-01-01

A significant challenge in decommissioning any large nuclear facility is how to solidify the large volume of residual high-level radioactive waste (HLW) without structurally interfering with the existing equipment and piping used at the original facility or would require rework due to interferences which were not identified during the design process. This problem is further compounded when the nuclear facility to be decommissioned is a 35 year old nuclear fuel reprocessing center designed to recover usable uranium and plutonium. Facilities of this vintage usually tend to lack full documentation of design changes made over the years and as a result, crude traps or pockets of high-level contamination may not be fully realized. Any miscalculation in the construction or modification sequences could compound the overall dismantling and decontamination of the facility. This paper reports that development of a 3-dimensional (3-D) computer database tool was considered critical in defining the most complex portions of this one-of-a-kind vitrification facility

The regulations concerning the reprocessing business of spent fuels

International Nuclear Information System (INIS)

1978-01-01

In compliance with ''The law for the regulations of nuclear source material, nuclear fuel material and reactors'' these regulations prescribe concerning reprocessing facilities: The procedures to apply for the approval of the design and method of construction and the approval of the change thereof; as well as the procedure to apply for the inspection of the facilities, and details of the inspection (in sections 2-6). After that, the regulations require the enterpriser of reprocessing business to keep necessary records and take necessary measures for safety concerning the facilities, operation of reprocessing equipments, and transportation, storage on disposal of used fuel, materials separated therefrom or materials contaminated by either of them (in sections 8-16). Further, the regulations prescribe the procedure to apply for the approval of the safety rule required to the enterpriser of reprocessing business by above mentioned law and specifies items which should be included into the rule (section 17). Moreover, the regulations require the enterpriser to submit reports of each use of the internationally controllled material and specifies the items which should be included into these reports (section 19). (Matsushima, A.)

Study of assessing aqueous reprocessing process for the pipeless reprocessing plant

International Nuclear Information System (INIS)

Hanzawa, Masatoshi; Morioka, Nobuo; Fumoto, Hiromichi; Nishimura, Kenji; Chikazawa, Takahiro

2000-02-01

The purpose of this study is to investigate the possibility of new reprocessing process for the purpose of introducing pipeless plant concept, where aqueous separation methods other than solvent extraction method are adopted in order to develop more economical FBR fuel (MOX fuel) reprocessing process. At it's first stage, literature survey on precipitation method, crystallization method and ion-exchange method was performed. Based on the results, following processes were candidated for pipeless reprocessing plant. (1) The process adopting crystallization method and peroxide precipitation method (2) The process adopting oxalate precipitation method (3) The process under mild aqueous conditions (crystallization method and precipitation method) (4) The process adopting crystallization method and ion-exchange method (5) The process adopting crystallization method and solvent extraction method. The processes (1)-(5) were compared with each others in terms of competitiveness to the conventional reference process, and merits and demerits were evaluated from the viewpoint of applicability to pipeless reprocessing plant, safety, economy, Efficiencies in consumption of Resources, non-proliferation, and, Operation and Maintenance. As a result, (1) The process adopting crystallization method and peroxide precipitation method was selected as the most reasonable process to pipeless plant. Preliminary criticality safety analyses, main process chemical flowsheet, main equipment list and layout of mobile vessels and stations were reported for the (1) process. (author)

Management and disposal of used nuclear fuel and reprocessing wastes

International Nuclear Information System (INIS)

1983-01-01

The subject is dealt with in chapters, entitled: introduction (general statement of problem); policy framework (criteria for waste management policy); waste management and disposal, as practised and planned (general; initial storage; reprocessing and conditioning of reprocessing wastes; intermediate storage; transportation; packaging; disposal); international co-operation. Details of the situation in each country concerned (Australia, Belgium, Canada, France, Federal Republic of Germany, Spain, Sweden, Switzerland and United Kingdom) are included as annexes. (U.K.)

Remote repair robots for dissolvers in nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Sugiyama, Sen; Hirose, Yasuo; Kawamura, Hironobu; Minato, Akira; Ozaki, Norihiko.

1984-01-01

In nuclear facilities, for the purpose of the reduction of radiation exposure of workers, the shortening of working time and the improvement of capacity ratio of the facilities, the technical development of various devices for remote maintenance and inspection has been advanced so far. This time, an occasion came to inspect and repair the pinhole defects occurred in spent fuel dissolving tanks in the reprocessing plant of Tokai Establishment, Power Reactor and Nuclear Fuel Development Corp. However, since the radiation environmental condition and the restricting condition due to the object of repair were extremely severe, it was impossible to cope with them using conventional robot techniques. Consequently, a repair robot withstanding high level radiation has been developed anew, which can work by totally remote operation in the space of about 270 mm inside diameter and about 6 m length. The repair robot comprises a periscope reflecting mirror system, a combined underwater and atmospheric use television, a grinder, a welder, a liquid penetrant tester and an ultrasonic flaw detector. The key points of the development were the parts withstanding high level radiation and the selection of materials, to make the mechanism small size and the realization of totally remote operation. (Kako, I.)

Consolidated fuel reprocessing program

International Nuclear Information System (INIS)

Kuban, D.P.; Noakes, M.W.; Bradley, E.C.

1987-01-01

The Advanced Servomanipulator (ASM) System consists of three major components: the ASM slave, the dual arm master controller or master, and the control system. The ASM is a remotely maintainable force-reflecting servomanipulator developed at the Oak Ridge National Laboratory (ORNL) as part of the Consolidated Fuel Reprocessing Program of (CFRP). This new manipulator addresses requirements of advanced nuclear fuel reprocessing with emphasis on force reflection, remote maintainability, and reliability. It uses an all-gear force transmission system. The master arms were designed as a kinematic replica of ASM and use cable force transmission. Special digital control algorithms were developed to improve the system performance. The system is presently operational and undergoing evaluation. Preliminary testing has been completed and is reported. The system is now undergoing commercialization by transferring the technology to the private sector

On the Potential of Nuclear Fission Energy for Effective Reduction of Carbon Emission under the Constraint of Uranium Resources Use without Spent Fuel Reprocessing

International Nuclear Information System (INIS)

Knapp, V.; Pevec, D.; Matijevic, M.

2010-01-01

Urgency to stop further increase of greenhouse gases emissions and reverse the trends, as stated in the Fourth Intergovernmental Panel on Climate Change (IPPC) Report and in Copenhagen discussions, limits the realistic choice of energy technologies to those available now or in the near future of few decades. In the coming fifty years neither nuclear fusion nor carbon capture and storage (CCS) can be expected to give a significant contribution to world energy production. Two perspective intermittent sources such as wind and solar together with nuclear fission energy covering the base load consumption appears to be a combination with a potential to produce a large share of carbon free energy in the total world energy production. This contribution considers the issues, associated with required large scale deployment of nuclear fission energy. A serious question associated with nuclear energy is nuclear proliferation. Spread of uranium enrichment and spent fuel reprocessing installations in many new countries constructing nuclear reactors would be a major concern in present political environment. We investigate whether uranium resources would be sufficient to support nuclear build-up in next 50-60 years sufficiently large to significantly reduce carbon emission without reprocessing of spent nuclear fuel. A positive answer would mean that 50-60 years can be available to develop effective international control of nuclear fuel cycle installations. Our results show that a maximum nuclear build-up which would consume currently estimated uranium resources by 2065 without reprocessing could reduce by 2065 carbon emission by 39.6% of the total reduction needed to bring the WEO 2009 Reference Scenario prediction of total GHG emissions in 2065 to the level of the WEO 450 Scenario limiting global temperature increase to 2 degrees of C. The less demanding strategy of the nuclear replacement of all non-CCS coal power plants retiring during the 2025-2065 period would reduce emission

Open problems in reprocessing of a molten salt reactor fuel

International Nuclear Information System (INIS)

Lelek, Vladimir; Vocka, Radim

2000-01-01

The study of fuel cycle in a molten salt reactor (MSR) needs deeper understanding of chemical methods used for reprocessing of spent nuclear fuel and preparation of MSR fuel, as well as of the methods employed for reprocessing of MSR fuel itself. Assuming that all the reprocessing is done on the basis of electrorefining, we formulate some open questions that should be answered before a flow sheet diagram of the reactor is designed. Most of the questions concern phenomena taking place in the vicinity of an electrode, which influence the efficiency of the reprocessing and sensibility of element separation. Answer to these questions would be an important step forward in reactor set out. (Authors)

Spent fuel reprocessing past experience and future prospects

International Nuclear Information System (INIS)

Megy, J.

1983-09-01

A large experience has been gathered from the early fifties till now in the field of spent fuel reprocessing. As the main efforts in the world have been made for developping the reactors and the fuel fabrication industry to feed them, the spent fuel reprocessing activities came later and have not yet reached the industrial maturity existing to day for plants such as PWRs. But in the principal nuclear countries spent fuel reprocessing is to day considered as a necessity with two simultaneous targets: 1. Recovering the valuable materials, uranium and plutonium. 2. Conditionning the radioactive wastes to ensure safe definitive storage. The paper reviews the main steps: 1. Reprocessing for thermal reactor fuels: large plants are already operating or in construction, but in parallel a large effort of R and D is still under way for improvements. 2. The development of fast breeder plants implies associated fuel reprocessing facilities: pilot plants have demonstrated the closing of the cycle. The main difficulties encountered will be examined and particularly the importance of taking into account the problems of effluents processing and wastes storage [fr

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

Science.gov (United States)

Jin, Yutaka

2008-01-01

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.

Head-end reprocessing equipment remote maintenance demonstration

International Nuclear Information System (INIS)

Evans, J.H.; Metz, C.F. III.

1989-01-01

Prototype equipment for reprocessing breeder reactor nuclear fuel was installed in the Remote Operation and Maintenance Demonstration (ROMD) area of the Consolidated Fuel Reprocessing Program (CFRP) facility at the Oak Ridge National Laboratory (ORNL) in order to evaluate the design of this equipment in a cold mock-up of a remotely maintained hot cell. This equipment included the Remote Disassembly System (RDS) and the Remote Shear System (RSS). These systems were disassembled and reassembled remotely by using the extensive remote handling systems that are installed in this simulated hot-cell environment. 5 refs., 5 figs

Light water reactor fuel reprocessing and recycling

International Nuclear Information System (INIS)

1977-07-01

This document was originally intended to provide the basis for an environmental impact statement to assist ERDA in making decisions with respect to possible LWR fuel reprocessing and recycling programs. Since the Administration has recently made a decision to indefinitely defer reprocessing, this environmental impact statement is no longer needed. Nevertheless, this document is issued as a report to assist the public in its consideration of nuclear power issues. The statement compares the various alternatives for the LWR fuel cycle. Costs and environmental effects are compared. Safeguards for plutonium from sabotage and theft are analyzed

Theoretical study of trivalent element complexes for the nuclear waste reprocessing

International Nuclear Information System (INIS)

Petit, L.

2007-10-01

Current energetic and environmental concerns have made the nuclear waste reprocessing to be a major issue in numerous countries. One avenue to treat nuclear spent fuel requires separating selectively trivalent minor actinides An (Am 3+ , Cm 3+ ) from lanthanides Ln. In this regard, nitrogen extractants are under study. Their selectivity toward actinides is still unclear, but could be the result of enhanced covalency effects with trivalent minor actinides with respect to lanthanides (III). In this thesis, we have performed DFT calculations (Density Functional Theory) to study covalency effects within the actinide-ligand bond, following three main axes of research: advanced study of the nature of the chemical bonding, spectroscopic characterization of covalency, and preliminary tests of ab initio molecular dynamics for future calculations in solvent. Methods that are not regularly applied to trivalent actinides complexes have been used: topological methods, TDDFT, LDDFT, ab initio molecular dynamics. We have managed to show that the selectivity of the BTP ligand - the most effective An/Ln extractant to date - comes at least for a part from stronger covalency effects within the An-BTP bond with respect to the Ln-BTP bond, which has never been proved before. (author)

Numerical simulations of waste forms from the reprocessing of nuclear fuel

International Nuclear Information System (INIS)

Schneider, Stephan

2014-01-01

The usage of fissile material for nuclear fuel causes that alongside radioactive wastes are produced. These waste materials are created during all handling or usage operations within the nuclear fuel cycle. The main source of radiotoxicity is produced during the usage of nuclear fuel within the reactor. Energy is released by neutron induced fission reactions in heavy isotopes. Parts of the created fission products have large radiotoxicities. Due to neutron capture within the nuclear fuel the radiotoxicity is furthermore increased. These waste streams from the nuclear fuel cycle must be stored in a safe way to prevent any contamination of the biosphere and any harm to the civilization or the environment. The waste packages must be treated and conditioned for the final disposal. These created packages are subject to an independent product control to ensure there acceptability for transport, interim and final storage. The independent product control is a significant component of an effective waste management system. The aim of this work is the development of a software system used for the assessment of radioactive waste packages. The software shall permit the auditor to perform scenario analysis to forecast the product properties of a certain waste stream and therefore optimize the needed inspection scope in preparation of a new campaign. The software is designed as a modular library this permits the most flexible use of the software components and a high reusability of written analysis software. The software system is used for coupling of established and well-known simulation programs used for nuclear systems. The results of Monte-Carlo simulations and burn-up calculations are automatically imported and prepared for user interaction. The usage of simulation programs cause different challenges to the computing infrastructure. The scenario analyses need a large number of parameter variations which are bound to the computing time. For this reason additional to the

Maintenance experiences at analytical laboratory at the Tokai reprocessing plant

International Nuclear Information System (INIS)

Suzuki, Hisanori; Nagayama, Tetsuya; Horigome, Kazushi; Ishibashi, Atsushi; Kitao, Takahiko; Surugaya, Naoki

2014-01-01

The Tokai Reprocessing Plant (TRP) is developing the technology to recover uranium and plutonium from spent nuclear fuel. There is an analytical laboratory which was built in 1977, as one of the most important facilities for process and material control analyses at the TRP. Samples taken from each process are analyzed by various analytical methods using hot cells, glove boxes and hume-hoods. A large number of maintenance work have been so far carried out and different types of experience have been accumulated. This paper describes our achievements in the maintenance activities at the analytical laboratory at the TRP. (author)

Experience in construction of a spent nuclear fuel reprocessing plant in Japan

International Nuclear Information System (INIS)

Hashimoto, K.; Sakuma, A.; Inoue, K.

1977-01-01

In June 1970, Japan Gasoline Co., Ltd (JGC)and Saint-Goblan Techniques Nouvelles of France received an order for the construction of a reprocessing plant from Power Reactor and Nuclear Fuel Development Corporation, as a joint prime contractor. JGC was responsible for: procurement, inspection, and schedule control of equipment and materials other than those imported from Europe; for conclusion of contracts with various subcontractors relating to the building construction, piping, and similar work; and for supervision of field work. Field work began in June 1971 and was completed in about 40 months. This paper describes the experiences of JGC during the period of the entire operation, and on the basis of this experience recommends modifications to their approach to similar projects in the future

Improved annular centrifugal contactor for solvent extraction reprocessing of nuclear reactor fuel

International Nuclear Information System (INIS)

Bernstein, G.J.; Leonard, R.A.; Ziegler, A.A.; Steindler, M.J.

1978-01-01

An improved annular centrifugal contactor has been developed for solvent extraction reprocessing of spent nuclear reactor fuel. The design is an extension of a contactor developed several years ago at Argonne National Laboratory. Its distinguishing features are high throughput, high stage efficiency and the ability to handle a broad range of aqueous-to-organic phase flow ratios and density ratios. Direct coupling of the mixing and separating rotor to a motorized spindle simplifies the design and makes the contactor particularly suitable for remote maintenance. A unit that is critically safe by geometry is under test and a larger unit is being fabricated. Multi-stage miniature contactors operating on the annular mixing principle are being used for laboratory flow sheet studies. 8 figures

Identification of potential safety-related incidents applicable to a breeder fuel reprocessing plant

International Nuclear Information System (INIS)

Perkins, W.C.

1980-01-01

The current emphasis on safety in all phases of the nuclear fuel cycle requires that safety features be identified and included in designs of nuclear facilities at the earliest possible stage. A popular method for the early identification of these safety features is the Preliminary Hazards Analysis. An extension of this analysis is to illustrate the nature of a hazard by its effects in accident situations, that is, to identify what are called safety-related incidents. Some useful tools are described which have been used at the Savannah River Laboratory, SRL, to make Preliminary Hazards Analyses as well as safety analyses of facilities for processing spent nuclear fuels from both power and production reactors. These tools have also been used in safety studies of waste handling operations at the Savannah River Plant. The tools are the SRL Incidents Data Bank and the What If meeting. The application of this methodology to a proposed facility which has breeder fuel reprocessing capability, the Hot Experimental Facility (HEF) is illustrated

Simplified nuclear fuel reprocessing flowsheet: a single-cycle Purex process

International Nuclear Information System (INIS)

Montuir, M.; Dinh, B.; Baron, P.

2004-01-01

A simplified flowsheet with only one purification cycle instead of three is proposed for reprocessing spent nuclear fuel using the Purex process. A single-cycle flowsheet minimizes the process equipment required, the number of control points before transfer between process units, and the solvent and effluent quantities. For the uranium stream, an alpha barrier is used to strip any residual contaminants (Np, Th, Pu) from the uranium-loaded solvent. This additional step eliminates the need for a second uranium cycle. For the plutonium stream, an additional βγ co-decontamination step and a higher plutonium concentration are required before the oxalate conversion step; a plutonium 'half-cycle' is added downstream. The unloaded solvent from this half-cycle is returned to the selective plutonium stripping step, allowing significant plutonium half-cycle losses. It should be possible to reduce the number of stages in the half-cycle extraction step by recycling the raffinate to the upstream separation process. (authors)

Falling film evaporators: organic solvent regeneration in nuclear fuel reprocessing

International Nuclear Information System (INIS)

Garcin, I.

1989-01-01

The aim of this work was to improve knowledge about working of falling film evaporators used in nuclear fuel reprocessing plants for organic solvent regeneration. The first part deals with a non evaporation film. An original film thickness measuring technique was used; infrared thermography. It gave indications on hydrodynamics and wave amplitude and pointed out thermocapillary forces to be the cause of bad wetting of the heated wall. By another way we showed that a small slit spacing on the film distributor, an enhanced surface roughness and an important liquid flow rate favour a better wetting. The second part deals with evaporation of a binary solvent mixture. Experiments in an industrial evaporator corroborated the fact that it is essential for the efficiency of the apparatus to work at high flow rates. We propose an over-simple model which can be used to estimate performances of co-current falling film evaporators of the process [fr

A spectrophotometric study of cerium IV and chromium VI species in nuclear fuel reprocessing process streams

International Nuclear Information System (INIS)

Nickson, I D; Boxall, C; Jackson, A; Whillock, G O H

2010-01-01

Nuclear fuel reprocessing schemes such as PUREX and UREX utilise HNO 3 media. An understanding of the corrosion of process engineering materials such as stainless steel in such media is a major concern for the nuclear industry. Two key species are cerium and chromium which, as Ce(IV), Cr(VI), may act as corrosion accelerants. An on-line analytical technique for these quantities would be useful for determining the relationship between corrosion rate and [Ce(IV)] and [Cr(VI)]. Consequently, a strategy for simultaneous quantification of Ce(IV), Cr(VI) and Cr(III) in the presence of other ions found in average burn-up Magnox / PWR fuel reprocessing stream (Fe, Mg, Nd, Al) is being developed. This involves simultaneous UV-vis absorbance measurement at 620, 540, 450 nm, wavelengths where Ce and Cr absorb but other ions do not. Mixed solutions of Cr(VI) and Ce(IV) are found to present higher absorbance values at 540 nm than those predicted from absorbances recorded from single component solutions of those ions. This is attributed to the formation of a 3:1 Cr(VI)-Ce(IV) complex and we report on the complexation and UV-visible spectrophotometric characteristics of this species. To the best of our knowledge this is the first experimental study of this complex in aqueous nitric acid solution systems.

Integrated international safeguards concepts for fuel reprocessing

International Nuclear Information System (INIS)

Hakkila, E.A.; Gutmacher, R.G.; Markin, J.T.; Shipley, J.P.; Whitty, W.J.; Camp, A.L.; Cameron, C.P.; Bleck, M.E.; Ellwein, L.B.

1981-12-01

This report is the fourth in a series of efforts by the Los Alamos National Laboratory and Sandia National Laboratories, Albuquerque, to identify problems and propose solutions for international safeguarding of light-water reactor spent-fuel reprocessing plants. Problem areas for international safeguards were identified in a previous Problem Statement (LA-7551-MS/SAND79-0108). Accounting concepts that could be verified internationally were presented in a subsequent study (LA-8042). Concepts for containment/surveillance were presented, conceptual designs were developed, and the effectiveness of these designs was evaluated in a companion study (SAND80-0160). The report discusses the coordination of nuclear materials accounting and containment/surveillance concepts in an effort to define an effective integrated safeguards system. The Allied-General Nuclear Services fuels reprocessing plant at Barnwell, South Carolina, was used as the reference facility

Material control for a reprocessing plant

International Nuclear Information System (INIS)

Rundquist, D.; Bray, G.; Donelson, S.; Glancy, J.; Gozani, T.; Harris, L.; McNamera, R.; Pence, D.; Ringham, M.

1976-01-01

Adequate control of special nuclear material (SNM) implies a basic knowledge of the quantities of SNM processed through or contained within a fuels processing facility with sufficient accuracy that diversion of the SNM for deleterious purposes can be detected in a timely manner. This report to the Lawrence Livermore Laboratory (LLL) describes the primary process streams containing plutonium that are handled routinely within a spent fuel reprocessing plant and conversion facility. As an aid in implementing the objectives of the accountability system in a realistic situation, the Allied General Nuclear Services (AGNS) reprocessing plant now under construction near Barnwell, South Carolina, was chosen as the study model. The AGNS plant processes are discussed in detail emphasizing those portions of the process that contain significant quantities of plutonium. The unit processes within the separations plant, nitrate storage, plutonium product facility and the analytical laboratory are described with regard to the SNM control system currently planned for use in the facilities. A general discussion of laboratory techniques, nondestructive assay and process instrumentation for plutonium process and product material from a reprocessing plant is included. A comprehensive discussion is given of holdup measurements in plutonium recycle facilities. A brief preliminary overview is presented of alternative processing strategies for LWR fuel. An extensive review and summary of modeling efforts for liquid-liquid extraction cycles is included. A comprehensive bibliography of previous modeling efforts is covered

Nuclear accountability data at the EUREX reprocessing plant

International Nuclear Information System (INIS)

Ilardi, S.; Pozzi, F.

1976-01-01

In the present work the physical inventory's and fissile material balance's data, which have been collected during the irradiated MTR fuel reprocessing campaign at the EUREX plant in Saluggia (VC), are reported, together with the most important procedures of fissile material accountability

Study on the possibility of supercritical fluid extraction for reprocessing of spent nuclear fuel from high temperature gas-cooled reactor

International Nuclear Information System (INIS)

Duan Wuhua; Zhu Liyang; Zhu Yongjun; Xu Jingming

2011-01-01

International interest in high temperature gas-cooled reactor (HTGR) has been increasing in recent years. It is important to study on reprocessing of spent nuclear fuel from HTGR for recovery of nuclear resource and reduction of nuclear waste. Treatment of UO 2 pellets for preparing fuel elements of the 10 MW high temperature gas-cooled reactor (HTR-10) using supercritical fluid extraction was investigated. UO 2 pellets are difficult to be directly dissolved and extracted with TBP-HNO 3 complex in supercritical CO 2 (SC-CO 2 ), and the extraction efficiency is only about 7% under experimental conditions. UO 2 pellets are also difficult to be converted completely into nitrate with N 2 O 4 . When UO 2 pellets break spontaneously into U 3 O 8 powders with particle size below 100 μm under O 2 flow and 600degc, the extraction efficiency of U 3 O 8 powders with TBP-HNO 3 complex in SC-CO 2 can reach more than 98%. U 3 O 8 powders are easy to be completely converted into nitrate with N 2 O 4 . The extraction efficiency of the nitrate product with TBP in SC-CO 2 can reach more than 99%. So it has a potential prospect that application of supercritical fluid extraction in reprocessing of spent nuclear fuel from HTGR. (author)

Fast reactor system factors affecting reprocessing plant design

International Nuclear Information System (INIS)

Allardice, R.H.; Pugh, O.

1982-01-01

The introduction of a commercial fast reactor electricity generating system is very dependent on the availability of an efficient nuclear fuel cycle. Selection of fuel element constructional materials, the fuel element design approach and the reactor operation have a significant influence on the technical feasibility and efficiency of the reprocessing and waste management plants. Therefore the fast reactor processing plant requires liaison between many design teams -reactor, fuel design, reprocessing and waste management -often with different disciplines and conflicting objectives if taken in isolation and an optimised approach to determining several key parameters. A number of these parameters are identified and the design approach discussed in the context of the reprocessing plant. Radiological safety and its impact on design is also briefly discussed. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2011-08-01

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.

Alpha-contaminated waste from reprocessing of nuclear fuel

International Nuclear Information System (INIS)

Sumner, W.

1982-01-01

The anticipated alpha-waste production rates from the Barnwell Nuclear Fuel Reprocessing plant is discussed. The estimated alpha-waste production rate from the 1500 metric ton/year plant is about 85,000 ft 3 /year at the 10 nCi/g limit. Most of this waste is estimated to come from the separation facility, and the major waste sources were cladding, which was 27%, and low-level contact-handled general process trash, which was estimated at 32% of the total. It was estimated that 45% of the waste was combustible and 72% of the waste was compactible. These characteristics could have a significant impact on the final volumes as disposed. Changing the alpha-waste limit from 10 nCi/g to 100 nCi/g was estimated to reduce the amount of alpha waste produced by about 20%. Again, the uncertainty in this value obviously has to be substantial. One has to recognize that these estimates were just that; they were not based on any operating experience. The total plutonium losses to waste, including the high-level waste, was estimated to be 1.5%. The cladding waste was estimated to be contaminated with alpha emitters to the extent of 10 4 to 10 5 nCi/g

Status and prospects for reprocessing

International Nuclear Information System (INIS)

Rossney, G.K.

1977-01-01

Following the formation of United Reprocessors (U.R.G.) in 1976 by British Nuclear Fuels Limited (B.N.F.L.) in the United Kingdom, the Commissariat a l'Energie Atomique (C.E.A.) in France and K.E.W.A. Kernbrennstoff-Wiederaufarbeitungs-Gesellschaft MBH (K.E.W.A.) in Germany, collaboration is now well established for the marketing of their reprocessing services for irradiated oxide fuel from thermal reactors. In addition collaboration in the continued evolution of the technology has progressed and an extensive research and development programme has been established, the results of which are exchanged between the shareholders. During 1976 the U.K. Government has given approval to B.N.F.L. to sign further contracts with foreign customers, subject to certain conditions. In France, the fuel cycle activities of the C.E.A. have been vested in a new company (Compagnie Generale Des Matieres Nucleaires (C.O.G.E.M.A.)) and their La Hague plant has commenced reprocessing operations on irradiated oxide fuel. In Germany, an agreement has been signed between K.E.W.A. and P.W.K. for the pre-project study for the proposed German plant. Against this background this paper reviews the present status of reprocessing by the shareholders of U.R.G. and the prospects for reprocessing

The international reprocessing situation

International Nuclear Information System (INIS)

Sornein, J.

1976-01-01

It is investigated what volume and availability of reprocessing capacity is needed for LWR (and AGR) fuel elements for Western Europe, USA, and Japan during the period from 1980 to 1990. Taking into account the technical, financial, and licensing difficulties, an optimistic and pessimistic assessment is made especially for Western Europe, and from the findings conclusions are drawn for spent fuel element storage and nuclear power plant construction. (HR/LN) [de

Benefit analysis of reprocessing and recycling light water reactor fuel

International Nuclear Information System (INIS)

1976-12-01

The macro-economic impact of reprocessing and recycling fuel for nuclear power reactors is examined, and the impact of reprocessing on the conservation of natural uranium resources is assessed. The LWR fuel recycle is compared with a throwaway cycle, and it is concluded that fuel recycle is favorable on the basis of economics, as well as being highly desirable from the standpoint of utilization of uranium resources

Reprocessing input data validation

International Nuclear Information System (INIS)

Persiani, P.J.; Bucher, R.G.; Pond, R.B.; Cornella, R.J.

1990-01-01

The Isotope Correlation Technique (ICT), in conjunction with the gravimetric (Pu/U ratio) method for mass determination, provides an independent verification of the input accountancy at the dissolver or accountancy stage of the reprocessing plant. The Isotope Correlation Technique has been applied to many classes of domestic and international reactor systems (light-water, heavy-water, graphite, and liquid-metal) operating in a variety of modes (power, research, production, and breeder), and for a variety of reprocessing fuel cycle management strategies. Analysis of reprocessing operations data based on isotopic correlations derived for assemblies in a PWR environment and fuel management scheme, yielded differences between the measurement-derived and ICT-derived plutonium mass determinations of (-0.02 ± 0.23)% for the measured U-235 and (+0.50 ± 0.31)% for the measured Pu-239, for a core campaign. The ICT analyses has been implemented for the plutonium isotopics in a depleted uranium assembly in a heavy-water, enriched uranium system and for the uranium isotopes in the fuel assemblies in light-water, highly-enriched systems. 7 refs., 5 figs., 4 tabs

Access control system for two person rule at Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Yanagisawa, Sawako; Ino, Munekazu; Yamada, Noriyuki; Oota, Hiroto; Iwasaki, Mitsuaki; Kodani, Yoshiki; Iwamoto, Tomonori

2014-01-01

Following the amendment and enforcement of Regulation of Reprocessing Activity on March 29th 2012, two person rule has become compulsory for the specific rooms to counter and prevent the sabotage or theft of nuclear materials by the insiders at reprocessing plant in Japan. The rooms will include those which contains cooling systems for decay heat removal from spent fuels and so on, scavenging systems to prevent the hydrogen accumulation, and those which contains nuclear material. To ensure the two person rule at Rokkasho Reprocessing Plant, JNFL has recently, after comprehensive study, introduced efficient and effective access control system for the rooms mentioned above. The system is composed of bio-attestation devices, surveillance cameras and electronic locks to establish access control system. This report outlines the access control system for two person rule and introduces the operation. (author)

Formation of aqueous complexes of metal ions formed during the reprocessing of nuclear fuels with ortho-phenanthroline and dibutylphosphate

International Nuclear Information System (INIS)

Musikas, C.; Le Marois, G.; Racinoux, J.

1979-01-01

In this work the formation of aqueous complexes of metalions (lanthanides, actinides) was investigated that occurs during reprocessing of nuclear combustibles with ortho-phenanthroline and dibutylphosphate. Complexes with different ligand numbers and solubility are formed. Cationic and anionic forms according to the DBP concentration in the extraction solution. Acid-base titrations, absorption spectra and solubility determinations were used for the characterization. (RB) [de

Energies and media nr 30. Conditions for the nuclear sector. The fuel cycle and wastes. The usefulness of fuel reprocessing. Wastes; Energies et medias no. 30. La conjoncture, pour le nucleaire. Le cycle du combustible et les dechets. L'utilite du retraitement des combustibles. Les dechets

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-10-15

After some comments on recent events in the nuclear sector in different countries (energy policy and projects in the USA, Europe, China, India, Russia), this issue proposes some explanations on the nuclear fuel cycle and on nuclear wastes: involved processes and products from mining to reprocessing and recycling, usefulness of reprocessing (future opportunities of fast neutron reactors, present usefulness of reprocessing with the recycling of separated fissile materials), impact of reprocessing on the environment in La Hague (gas and liquid releases, release standard definition), and the destiny of wastes

Why reprocess

International Nuclear Information System (INIS)

Greenwood, T.

1977-01-01

Prospective costs of reprocessing, waste management, and mixed oxide fuel fabrication have risen so much that the costs of U/P recycle and of spent fuel storage are nearly equal. This paper reviews the current state of the reprocessing industry, with a list of facilities all over the world, and examines the incentives and disincentives other than short-term economics that will affect the decision of states to acquire their own reprocessing facilities. Finally, it examines the possibility of avoiding a widespread commercial reprocessing industry

Reprocessing of spent nuclear fuels. Status and trends

International Nuclear Information System (INIS)

Hultgren, Aa.

1993-01-01

The report gives a short review of the status for industrial reprocessing and recycling of Uranium/Plutonium. The following countries are covered: Belgium, France, Germany, Great Britain, India, Japan, Russia, USA. Different fuel cycle strategies are accounted for, and new developments outlined. 116 refs, 27 figs, 12 tabs

Design of an advanced human-centered supervisory system for a nuclear fuel reprocessing system

International Nuclear Information System (INIS)

Riera, B.; Lambert, M.; Martel, G.

1999-01-01

In the field of highly automated processes, our research concerns supervisory system design adapted to supervisory and default diagnosis by human operators. The interpretation of decisional human behaviour models shows that the tasks of human operators require different information, which has repercussions on the supervisory system design. We propose an advanced human-centred supervisory system (AHCSS) which is more adapted to human-beings, because it integrates new representation of the production system,(such as functional and behavioural aspects) with the use of advanced algorithms of detection and location. Based on an approach using these new concepts, and AHCSS was created for a nuclear fuel reprocessing system. (authors)

Risk assessment for nuclear processes at the Savannah River Site

International Nuclear Information System (INIS)

Durant, W.S.

1992-01-01

The Savannah River Site, one of the US Department of Energy's nuclear materials processing facilities, has for many years conducted risk-based safety analyses for the nuclear processes conducted at the facilities. This approach has allowed comparisons of risks to established criteria for acceptability. When the risk-based program was begun, it was evident that its success would depend upon having a compilation of data that was site specific. The decision was made to create a data bank of undesirable events that had occurred at the site's nuclear fuel reprocessing facilities. From this modest beginning, five data banks have been created for nuclear fuel reprocessing, waste management, nuclear fuel fabrication, tritium operations, and the Savannah River Technology Center. In addition to the primary purpose of providing a sound basis for risk-based safety analyses, these highly versatile data banks are routinely used for equipment breakdown histories, incident investigations, design studies, project justifications, reliability studies, process problem solving, training, and audits

Waste management in reprocessing plants

International Nuclear Information System (INIS)

Mortreuil, M.

1982-01-01

This lecture will give a survey of the French policy for the management of wastes in reprocessing plants. In consideration of their radioactivity, they must be immobilized in matrix in such a manner that they are stored under optimal safety conditions. A general review on the nature, nucleide content and quantity of the various wastes arising from thermal nuclear fuel reprocessing is given in the light of the French plants UP1 at Marcoule and UP2 at La Hague. The procedures of treatment of such wastes and their conditioning into inert packages suitable for temporary or terminal storage are presented, especially concerning the continuous vitrification process carried out for fission product solutions. The requirements of each option are discussed and possible alternative solutions are exposed. (orig./RW)

Reprocessing business in the UK

Energy Technology Data Exchange (ETDEWEB)

Wilkinson, W L

1985-01-01

The development of the process for separating uranium, plutonium and fission products from irradiated fuel began in Britain in late 1940s, and the first separation plant was operated at Sellafield in 1952. This plant was operated very well for more than 12 years with the overall availability over 95%. The second separation plant to meet the needs of the growing nuclear power program became operational in 1964. This plant has been extremely successful, but the significant improvement was made to extend the operating life of the key items. In mid 1970s, by the introduction of uranium oxide fuel reactors, significant reprocessing capacity became to be required. Therefore, it was decided to embark upon the development of a thermal oxide reprocessing plant (THORP) to complement the existing facilities at Sellafield. The THORP is a very large complex of plants. The first duty for the THORP is to reprocess 6,000 t U of oxide fuel in 10 years. But the plant is designed for the life of 25 years. The plant has the capacity of 1200 tes/year. The scope covered by the THORP, the plant processes and the wastes produced from the THORP are described. (Kako, I.).

Remote maintenance lessons learned on prototypical reprocessing equipment

International Nuclear Information System (INIS)

Kring, C.T.; Schrock, S.L.

1990-01-01

A major objective of the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory is to develop and demonstrate the technology required to reprocess spent nuclear fuel. The Fuel Recycle Division, over the past 16 years, has undertaken this objective by designing and testing prototypical hardware representing essentially every major equipment item currently included in most fuel reprocessing plant conceptual designs. These designs are based on total remote maintenance to increase plant availability and reduce radiation exposure to plant operators. The designs include modular equipment to facilitate maintainability and the remote manipulation necessary to accomplish maintenance tasks. Prototypic equipment has been installed and tested in a cold mock-up of a reprocessing hot cell, called the remote operations and maintenance demonstration facility. The applied maintenance concept utilizes the dexterity and mobility of bridge-mounted, force-reflecting servomanipulators. Prototypic processing equipment includes a remote disassembly system, a remote shear system, a rotary dissolver, a remote automated sampler system, removable equipment racks to support chemical process equipment items, and the advanced servomanipulators. Each of these systems and a brief description of functions are discussed

R and D status of oxide electro-refining reprocessing technology

International Nuclear Information System (INIS)

Myochin, Munetaka

2005-01-01

The oxide electro-refining pyrochemical reprocessing is excellent in the resistivity against nuclear material diversion and in the suitability for oxide fuel cycle and has an excellent affinity for the technology of fuel production using the vibropac method. The oxide electro-refining pyrochemical reprocessing system has therefore been examined as a part of studies of commercialization of FBR cycle. This report outlines the examination results of fundamental data acquired for the system design. (M.H.)

Role of near-real-time accounting in international safeguards for reprocessing plants

International Nuclear Information System (INIS)

Hakkila, E.A.; Dietz, R.J.; Shipley, J.P.

1979-01-01

The effectiveness of conventional nuclear materials accounting systems, both national and international, is constrained by the fundamental process features of high-throughput nuclear facilities and the economic limits of effective nuclear materials management consistent with production goals. Conventional accounting, complemented by near-real-time accounting, may meet projected IAEA performance goals for detecting diversion in medium- and high-throughput reprocessing facilities projected for the late 1900's. The design of materials accounting systems for international safeguards in reprocessing plants is discussed, paying particular attention to the question of international verification. Specific problems in measurement techniques, data evaluation, and systems structure are identified, and the current status of research and development efforts is reviewed

Electrocoagulation of solvent residues in the reprocessing of spent nuclear fuels

International Nuclear Information System (INIS)

Gidarakos, E.; Gramatte, W.; Koehling, A.; Schmitt, R.E.

1989-03-01

The aim of this project was to find out the potential of the method for the electrocoagulation (EC) of colloidally dispersed particles for an improved fine feed purification in the reprocessing of high burnup nuclear fuels with the help of real fuel solutions on a laboratory scale. In EC, the particles colloidally dispersed in the solution are fed with electric charges at the electrodes; this leads to a coagulation of the particles, with separation taking place at the electrodes. The methods of analysis chosen for the EC were nephelometry for inactive experiments with RuO 2 suspensions, and gamma spectroscopy for experiments with radioactive fuel solutions, with the nuclide pair Ru/Rh-106 acting as a colloidal tracer nuclide. On the whole, the present experimental data permit the conclusion that under the experimental conditions and with the apparatus applied, EC gives rise to the separation of colloidally dispersed noble metal particles in an active fuel solution. (orig./RB) [de

Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

1977-09-01

Safety and cost information were developed for the conceptual decommissioning of a fuel reprocessing plant with characteristics similar to the Barnwell Nuclear Fuel Plant. The main process building, spent fuel receiving and storage station, liquid radioactive waste storage tank system, and a conceptual high-level waste-solidification facility were postulated to be decommissioned. The plant was conceptually decommissioned to three decommissioning states or modes; layaway, protective storage, and dismantlement. Assuming favorable work performance, the elapsed time required to perform the decommissioning work in each mode following plant shutdown was estimated to be 2.4 years for layaway, 2.7 years for protective storage, and 5.2 years for dismantlement. In addition to these times, approximately 2 years of planning and preparation are required before plant shutdown. Costs, in constant 1975 dollars, for decommissioning were estimated to be $18 million for layaway, $19 million for protective storage and $58 million for dismantlement. Maintenance and surveillance costs were estimated to be $680,000 per year after layaway and $140,000 per year after protective storage. The combination mode of protective storage followed by dismantlement deferred for 10, 30, and 100 years was estimated to cost $64 million, $67 million and $77 million, respectively, in nondiscounted total 1975 dollars. Present values of these costs give reduced costs as dismantlement is deferred. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year radiation dose commitment to the members of the public from airborne releases from normal decommissioning activities were estimated to be less than 11 man-rem

Technology, safety, and costs of decommissioning a reference nuclear fuel reprocessing plant

Energy Technology Data Exchange (ETDEWEB)

Schneider, K.J.; Jenkins, C.E.; Rhoads, R.E.

1977-09-01

Safety and cost information were developed for the conceptual decommissioning of a fuel reprocessing plant with characteristics similar to the Barnwell Nuclear Fuel Plant. The main process building, spent fuel receiving and storage station, liquid radioactive waste storage tank system, and a conceptual high-level waste-solidification facility were postulated to be decommissioned. The plant was conceptually decommissioned to three decommissioning states or modes; layaway, protective storage, and dismantlement. Assuming favorable work performance, the elapsed time required to perform the decommissioning work in each mode following plant shutdown was estimated to be 2.4 years for layaway, 2.7 years for protective storage, and 5.2 years for dismantlement. In addition to these times, approximately 2 years of planning and preparation are required before plant shutdown. Costs, in constant 1975 dollars, for decommissioning were estimated to be $18 million for layaway, $19 million for protective storage and $58 million for dismantlement. Maintenance and surveillance costs were estimated to be $680,000 per year after layaway and $140,000 per year after protective storage. The combination mode of protective storage followed by dismantlement deferred for 10, 30, and 100 years was estimated to cost $64 million, $67 million and $77 million, respectively, in nondiscounted total 1975 dollars. Present values of these costs give reduced costs as dismantlement is deferred. Safety analyses indicate that radiological and nonradiological safety impacts from decommissioning activities should be small. The 50-year radiation dose commitment to the members of the public from airborne releases from normal decommissioning activities were estimated to be less than 11 man-rem.

Remote maintenance ''lessons learned'' on prototypical reprocessing equipment

International Nuclear Information System (INIS)

Kring, C.T.; Schrock, S.L.

1990-01-01

Hardware representative of essentially every major equipment item necessary for reprocessing breeder reactor nuclear fuel has been installed and tested for remote maintainability. This testing took place in a cold mock-up of a remotely maintained hot cell operated by the Consolidated Fuel Reprocessing Program (CFRP) within the Fuel Recycle Division at Oak Ridge National Laboratory (ORNL). The reprocessing equipment tested included a Disassembly System, a Shear System, a Dissolver System, an Automated Sampler System, removable Equipment Racks on which various chemical process equipment items were mounted, and an advanced servomanipulator (ASM). These equipment items were disassembled and reassembled remotely by using the remote handling systems that are available within the cold mock-up area. This paper summarizes the ''lessons learned'' as a result of the numerous maintenance activities associated with each of these equipment items. 4 refs., 3 figs., 1 tab

Simulation of atmospheric krypton-85 transport to assess the detectability of clandestine nuclear reprocessing

Energy Technology Data Exchange (ETDEWEB)

Ross, Jens Ole

2010-02-02

The radioactive noble gas krypton-85 is released into the atmosphere during reprocessing of spent nuclear fuel or irradiated breeding targets. This is a necessary step for plutonium separation. Therefore the {sup 85}Kr signature of reprocessing could possibly be used for the detection of undeclared nuclear facilities producing nuclear weaponusable material. The {sup 85}Kr content of the atmosphere has grown over the last decades as the emissions from military and civilian nuclear industry could not be compensated by the decay with a half-life of 10.76 years. In this study, the global {sup 85}Kr background distribution due to emissions of known reprocessing facilities for the period from 1971 until 2006 was simulated using the atmospheric general circulation model ECHAM5 applying the newest available annual emission data. The convective tracer transport scheme and the operator splitting for the physical calculations in the model were modified in order to guarantee physically correct results for tracer point sources, in particular non negative concentrations. An on-line routine controlling the {sup 85}Kr -budget in the model enforced exact mass conservation. The results of the simulation were evaluated by extensive comparison with measurements performed by the German Federal Office for Radiation Protection with very good agreement at most observation sites except those in the direct vicinity of {sup 85}Kr sources. Of particular interest for the {sup 85}Kr detection potential was the variability of {sup 85}Kr background concentrations which was evaluated for the first time in a global model. In addition, the interhemispheric transport as simulated by ECHAM5 was analyzed using a two-box model providing a mean exchange time of τ {sub ex} = 10.5 months. The analysis of τ{sub ex} over simulated 35 years indicates that in years with strong South Asian or African Monsoon the interhemispheric transport is faster during the monsoon season. A correlation analysis of

The ban on reprocessing as seen from the perspective of European law

International Nuclear Information System (INIS)

Hanenburg, E.; Warg, G.

1999-01-01

The plan of the German federal government to opt out of the peaceful uses of nuclear power for electricity generation initially was to incorporate also a ban on reprocessing spent fuel elements. On February 22, 1999, Federal Minister for the Environment Trittin finally announced that his revised draft for the time being would contain no ban on reprocessing. That ban, as originally planned, raises a number of issues of European law which are analyzed in the article by Hanenburg and Warg, especially the question whether the ban on reprocessing constitutes a violation of the principles and objectives of the Common Market. The legal principles underlying the Common Market, especially the Euratom Treaty among the member countries, constitute the basis of the analysis in which, inter alia, aspects such as cross-border reprocessing and secondary European law or the legal consequences of the Euratom Treaty for the opting-out policy of the German federal government are dealt with. The analysis arrives at the finding that a final opt-out as planned by the German federal government in the amendments to the Atomic Energy Act, and the complete substitution of nuclear electricity by other sources of energy, violate the purpose of the Euratom Treaty at least to keep open the structural possibility of generating electricity by nuclear power. (orig.) [de

Long-term effects of a shortsighted us political decision banning commercial waste reprocessing

International Nuclear Information System (INIS)

Winterle, B.T.

2003-01-01

In 1977, US President Jimmy Carter ordered a drastic change in United States nuclear policy, banning all commercial reprocessing activities, and cancelling plans and funding for fast-breeding reactors. It was a political decision, influenced by immediate world events, and intended to be temporary. Contemporary documents and speeches given by Carter are examined in depth to determine the reasoning behind this dramatic change in US nuclear policy and the response by other countries. President Ronald Reagan rescinded these bans, but general mistrust by the US nuclear industry of further changes in political policy prevented further commercial reprocessing activities and construction of fast-breeding reactors in the US. The increase in the number of operating US fission reactors along with the lack of reprocessing activities caused concern among both Reagan and members of Congress. The resulting legislation set the stage for the proposed High-Level-Waste Repository at Yucca Mountain, Nevada. construction of the proposed repository had faced many serious setbacks due to several factors. The uncertainty regarding the project's timely completion has drastic repercussions for the involved parties. The conclusion of the author is that further evaluation into commercial reprocessing activities should be undertaken before final approval of the proposed repository is granted. (author)

Interim guidance for the safe transport of reprocessed uranium

International Nuclear Information System (INIS)

1994-06-01

Increasingly reprocessed uranium is being used for the fabrication of nuclear fuel elements. Different intermediate reprocessing steps are carried out at different locations. Therefore, transportation of uranium material is necessary. Due to the difference in isotope composition of reprocessed uranium then unirradiated uranium a doubt is casted on the presumption that packages used for the transport of unirradiated uranium are automatically suitable for reprocessed uranium compounds. The Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) recommended that the issue be reviewed by consultants and that a document be developed that would give guidance to users of the Regulations. This TECDOC is the result of the endeavors of the experts convened at two Consultants Services meetings. It contains guidance on the provisions in the current Regulations as well as proposals for changes to the new Revised Edition whose publication is planned for 1996. This document demonstrates that under the present Transport Regulations it is possible in most cases to ship reprocessed uranium compounds in the same packages as unirradiated uranium compounds. In few cases a more stringent package type is required. 8 refs, 22 figs, 19 tabs

Application of probabilistic risk assessment to nuclear fuel reprocessing at the Savannah River Plant

International Nuclear Information System (INIS)

Durant, W.S.

1980-01-01

The Savannah River Laboratory has developed an integrated risk assessment methodology that has been applied to systems in the nuclear fuel reprocessing facilities at the Savannah River Plant. The methodology can be applied to several types of design and operational problems. Basically, the analysis is subdivided into individual modules that can be either utilized separately or integrated into an overall risk analysis. Computer codes and computer data banks are utilized extensively to minimize the manual effort. The flow of information begins with a definition of the system to be analyzed followed by an evaluation of sources of fault information, storage of this information in data banks, design analysis and data treatment, risk calculations, and end product options

Fuel salt reprocessing influence on the MSFR behavior and on its associated reprocessing unit

International Nuclear Information System (INIS)

Doligez, X.

2010-10-01

In order to face with the growing of the energy demand, the nuclear industry has to reach the fourth generation technology. Among those concept, molten salt reactor, and especially the fast neutron spectrum configuration, seems very promising: indeed breeding is achievable while the feedback coefficient are still negative. However, the reprocessing salt scheme is not totally set down yet. A lot of uncertainties remain on chemical properties of the salt. Thanks to numerical simulation we studied the behavior of the molten Salt Fast Reactor coupled to a nominal reprocessing unit. We are now able to determine heat transfer and radiation in each elementary step of the unit and, by this way determine those that need special study for radioprotection. We also studied which elements are fundamental to extract for the reactor operation. Finally, we present a sensibility analysis of the chemical uncertainties to few relevant properties of the reactor behavior. (author)

International nuclear commerce: structure, trends and proliferation potentials

International Nuclear Information System (INIS)

Lodgaard, S.

1977-01-01

In recent years a surge has taken place in international nuclear commerce and this paper analyses the new patterns that have emerged. Despite uncertainties in nuclear energy forecasting the market is huge. Projections for the industry for the period 1971-1985 estimate a worldwide investment of 250 billion dollars. Following an initial decade of cooperation, 1955-1965, the superpower monopoly has become eroded. The export market for power reactors is analysed and the growth and spread of reprocessing facilities is discussed. It is pointed out that while commercial scale reprocessing requires vast and complex chemical plant, reprocessing small amounts for bomb production may be done relatively simply. Enrichment capabilities are also becoming more generally available. The market is not only expanding, but becoming multipolar and diversified, and the entire fuel cycle is now involved. The cooperation network France - W. Germany - South Africa- Iran is discussed at some length. The role of international safeguards is also treated fairly extensively, leading to a discussion of the motives and paths in the acquisition of nuclear weapons. It is concluded that little is to be gained from the London talks on safeguard measures and commercial restraint and that the root causes of proliferation should be tackled by comprehensive disarmament schemes. (JIW)

Fuel reprocessing and waste management in the UK

International Nuclear Information System (INIS)

Heafield, W.; Griffin, N.L.

1994-01-01

The currently preferred route for the management of irradiated fuel in the UK is reprocessing. This paper, therefore, concentrates on outlining the policies, practices and achievement of British Nuclear Fuels plc (BNFL) associated with the management of its irradiated fuel facilities at Sellafield. The paper covers reprocessing and how the safe management of each of the major waste categories is achieved. BNFL's overall waste management policy is to develop, in close consultation with the regulatory authorities, a strategy to minimize effluent discharges and provide a safe, cost effective method of treating and preparing for disposal all wastes arising on the site

Safety-related concrete structure design and construction of Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Morishita, Hideki; Munakata, Yoshinari; Togashi, Akihito

2003-01-01

The Rokkasho Reprocessing Plant of the Japan Nuclear Fuel Co. Ltd., is a facility to reprocess remained uranium without firing and newly formed plutonium contained in spent fuels used at the nuclear power stations, to produce fuels to be repeatedly used. Constructions in this facility has some characteristics shown as follows: 1) radiation shielding and seismic isolated functions like those at the nuclear power plants, 2) reduction of wall thickness based on partially using heavy concrete at walls required for radiation shielding, 3) protective design against fly-coming matters such as aircrafts, 4) construction period reduction based on winter construction and large scale block engineering. Here were described characteristics of designs on radiation shielding, seismic isolated and fly-coming matters protection construction engineering and quality control on concrete. (G.K.)

Experience in the construction of a spent nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Yamashita, Hiroshi

1976-01-01

The construction and operation of a reprocessing plant was first published in 1956. The Reprocessing Expert Committee of AEC was established in 1959, and the preliminary design was finished in 1964 by NCP of Britain. The detailed design was completed in 1969 by SGN of France, and the training of operators was carried out in parallel with this in France. The results of the safety investigation was approved in Jan. 1970, and the construction was started in June 1971. The site of the reprocessing plant is the eastern part of the Tokai Establishment of PNC. The process adopted is the wet Purex process having been established in large practical plants. The treating capacity is 0.7 t/day. The main processes are acceptance and storage, mechanical treatment, and chemical treatment. The reprocessing facilities comprise the main shop, the analysis station, the main exhaust stack, the decontamination station, the solid waste store, the sea discharge pipe, and other incidental facilities. The construction works were about 7 months behind the schedule when the water flow test was finished. The chemical test was finished in March, 1975, and the uranium test is in progress since Sept., 1975. The problems for future are the developments of effective waste treatment and storing techniques, and the researches have been carried out by PNC. The construction project of the second plant is urgently required, since it takes 10 years from planning to operation. (Kako, I.)

Hybrid KED/XRF measurement of minor actinides in reprocessing plants

International Nuclear Information System (INIS)

Hsue, S.T.; Collins, M.L.

1996-01-01

Minor actinides have received considerable attention recently in the nuclear power industry. Because of their potential value as recycle fuels in thermal and breeder reactors, reprocessing plants may have an economic incentive to extract Np, Am, and Cm from their waste streams. This report discusses the technique of hybrid densitometry and its potential to measure Np and Am in reprocessing plants. Precision estimates are made for the hybrid analysis of Np and Am in two types of dissolver solutions

Assessment of proliferation resistances of aqueous reprocessing techniques using the TOPS methodology

International Nuclear Information System (INIS)

Åberg Lindell, M.; Grape, S.; Håkansson, A.; Jacobsson Svärd, S.

2013-01-01

Highlights: • Proliferation resistances of three possible LFR fuel cycles are assessed. • The TOPS methodology has been chosen for the PR assessment. • Reactor operation, reprocessing and fuel fabrication are examined. • Purex, Ganex, and a combination of Purex, Diamex and Sanex, are compared. • The safeguards analysis speaks in favor of Ganex as opposed to the Purex process. - Abstract: The aim of this study is to assess and compare the proliferation resistances (PR) of three possible Generation IV lead-cooled fast reactor fuel cycles, involving the reprocessing techniques Purex, Ganex and a combination of Purex, Diamex and Sanex, respectively. The examined fuel cycle stages are reactor operation, reprocessing and fuel fabrication. The TOPS methodology has been chosen for the PR assessment, and the only threat studied is the case where a technically advanced state diverts nuclear material covertly. According to the TOPS methodology, the facilities have been divided into segments, here roughly representing the different forms of nuclear material occurring in each examined fuel cycle stage. For each segment, various proliferation barriers have been assessed. The results make it possible to pinpoint where the facilities can be improved. The results show that the proliferation resistance of a fuel cycle involving recycling of minor actinides is higher than for the traditional Purex reprocessing cycle. Furthermore, for the purpose of nuclear safeguards, group actinide extraction should be preferred over reprocessing options where pure plutonium streams occur. This is due to the fact that a solution containing minor actinides is less attractive to a proliferator than a pure Pu solution. Thus, the safeguards analysis speaks in favor of Ganex as opposed to the Purex process

A survey of methods for separating and immobilizing krypton-85 arising from a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Taylor, P.

1990-12-01

This report reviews the literature on methods to separate and immobilize krypton-85 arising from dissolution or prior treatment of nuclear fuel in a reprocessing plant. It was prepared as part of a broader review of fuel reprocessing waste management methods that might find future applications in Canada. Cryogenic distillation is the most fully demonstrated method of separation of krypton from off-gases, but it is complex. In particular, it requires pretreatment of the gas stream to eliminate several other components before the final distillation. The most highly developed alternative process is fluorocarbon adsorption, while several other processes have been investigated on a bench scale. The simplest method of storing radioactive krypton is in compressed-gas cylinders, but the risks of accidental release are increased by the corrosive nature of the decay product, rubidium. Encapsulation in either a metal matrix or a hydrothermally vitrified zeolite appears to offer the most secure immobilization of krypton. Processes for both types of material have been demonstrated inactively on a scale approaching that required for treatment of off-gases from a commercial-scale fuel reprocessing plant. Low-operating temperatures and pressures of the metal encapsulation process, compared with encapsulation in zeolites, represent a definite advantage, but electrical power requirements for the former process are relatively high. It appears that suitable technology is available for separation and immobilization of radioactive krypton, should the need arise in Canada in the future

Status of radioiodine control for nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

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

1983-07-01

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

Microchemical chip technology and nuclear energy. To develop new analytical system for process control in reprocessing plant

International Nuclear Information System (INIS)

Tokeshi, Manabu; Ikeda, Yasuhisa; Kitamori, Takehiko

2006-01-01

A feasibility study for two years has been done to apply micro-chemical chip technology to nuclear fuel reprocessing plant. Desktop-sized thermal lens microscope (DT-TLM) combined with integrated glass ship was examined in order to find a rapid and sensitive analytical method. A laser-beam is split into two beams, one as the reference while the other to be absorbed in a small quantity of sample solution in a cell with short optical-path length. The solution, on absorbing laser photons, increases in temperature accompanied with change in refractive index, which can be detected by using thermal lens microscope. After examinations of Co-complexes in the presence of 10 -6 M Cu ions by using micro chip-extraction behavior from aqueous phase to chloroform organic phase, and of U(VI) solutions in 3M nitric acid with added 8-quinolinol and others to develop optical density at absorbing wavelength, the author concluded that the system may be applicable for the practical analysis of U(VI) and H + in the spent fuel reprocessing plant. (S. Ohno)

Fast and Simultaneous Determination of Pu(Ⅳ) and Nitric Acid in Spent Nuclear Fuel Reprocessing Sample by Near Infrared Spectroscopy

Institute of Scientific and Technical Information of China (English)

LI; Ding-ming; ZHANG; Li-hua; WANG; Ling; GONG; Yan-ping; FAN; De-jun; YI; Bao-shan; CHEN; Qiang; JI; Yong-chao; WU; Ji-zong

2013-01-01

Determination of Pu(Ⅳ)and nitric acid plays significant role in nuclear fuel reprocessing plant to control process accurately and timely.Coupling C-T fixed-type grating with InGaAs detector,a new novel analytical system for simultaneous measurement of nitric acid and Pu(Ⅳ)was developed by our working group.After obtaining near infrared absorptive spectra by the spectroscopic instrument,the spectra data

Environmental survey of the reprocessing and waste management portions of the LWR fuel cycle: a task force report

Energy Technology Data Exchange (ETDEWEB)

Bishop, W.P.; Miraglia, F.J. Jr. (eds.)

1976-10-01

This Supplement deals with the reprocessing and waste management portions of the nuclear fuel cycle for uranium-fueled reactors. The scope of the report is limited to the illumination of fuel reprocessing and waste management activities, and examination of the environmental impacts caused by these activities on a per-reactor basis. The approach is to select one realistic reprocessing and waste management system and to treat it in enough depth to illuminate the issues involved, the technology available, and the relationships of these to the nuclear fuel cycle in general and its environmental impacts.

Environmental survey of the reprocessing and waste management portions of the LWR fuel cycle: a task force report

International Nuclear Information System (INIS)

Bishop, W.P.; Miraglia, F.J. Jr.

1976-10-01

This Supplement deals with the reprocessing and waste management portions of the nuclear fuel cycle for uranium-fueled reactors. The scope of the report is limited to the illumination of fuel reprocessing and waste management activities, and examination of the environmental impacts caused by these activities on a per-reactor basis. The approach is to select one realistic reprocessing and waste management system and to treat it in enough depth to illuminate the issues involved, the technology available, and the relationships of these to the nuclear fuel cycle in general and its environmental impacts

Simulation of solvent extraction in reprocessing

Energy Technology Data Exchange (ETDEWEB)

Kumar, Shekhar; Koganti, S B [Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

1994-06-01

A SIMulation Program for Solvent EXtraction (SIMPSEX) has been developed for simulation of PUREX process used in nuclear fuel reprocessing. This computer program is written in double precision structured FORTRAN77 and at present it is used in DOS environment on a PC386. There is a plan to port it to ND supermini computers in future. (author). 5 refs., 3 figs.

Alloy 33: A new material for the handling of HNO3/HF media in reprocessing of nuclear fuel

International Nuclear Information System (INIS)

Koehler, M.; Heubner, U.; Eichenhofer, K.W.; Renner, M.

1997-01-01

Alloy 33, an austenitic 33Cr-32Fe-31Ni-1.6Mo-0.6Cu-0.4N material shows excellent resistance to corrosion when exposed to highly oxidizing media as e.g. HNO 3 and HNO 3 /HF mixtures which are encountered in reprocessing of nuclear fuel. According to the test results available so far, resistance to corrosion in boiling azeotropic (67%) HNO 3 is about 6 and 2 times superior to AISI 304 L and 310 L. In higher concentrated nitric acid it can be considered corrosion resistant up to 95% HNO 3 at 25 C, up to 90% HNO 3 at 50 C and up to somewhat less than 85% HNO 3 at 75 C. In 20% HNO 3 /7% HF at 50 C its resistance to corrosion is superior to AISI 316 Ti and Alloy 28 by factors of about 200 and 2.4. Other media tested with different results include 12% HNO 3 with up to 3.5% HF and 0.4% HF with 32 to 67.5% HNO 3 at 90 C. Alloy 33 is easily fabricated into all product forms required for chemical plants (e.g. plate, sheet, strip, wire, tube and flanges). Components such as dished ends and tube to tube sheet weldments have been successfully fabricated facilitating the use of Alloy 33 for reprocessing of nuclear fuel

Aerial deposition of plutonium in mixed forest stands from nuclear fuel reprocessing

International Nuclear Information System (INIS)

Adriano, D.C.; Pinder, J.E. III

1977-01-01

Concentrations of 238 Pu and 239 , 240 Pu were determined in bark, organic matter, and soil samples collected in the summer of 1975 from pine (Pinus taeda) and hardwood (Quercus falcata; Carya tormentosa) stands near a nuclear fuel reprocessing plant at the U.S. Energy Res. and Dev. Admin.'s Savannah River Plant near Aiken, S.C. The results indicated that tree crowns intercepted fallout Pu (Pu-bearing particles) and produced higher Pu concentrations in the organic matter and soil under tree crowns. Higher 239 , 240 Pu concentrations were found under pines than under hardwoods. Plutonium concentrations in the O1 (litter, A 00 ) and O2 (organic matter, A 0 ) layers were higher than those in mineral soil, but most of the Pu was contained in the mineral soil. Higher contents of 239 , 240 Pu were observed near the tree stems than in locations outside of the tree crowns. In pines these values were 163 and 80 nCi 239 , 240 Pu/m 2 , and in hardwoods, 122 and 80 nCi 239 , 240 Pu/m 2 , for the respective locations, from the litter to the 15-cm depth. The proportion of 238 Pu contained in foliage, litter, and organic matter was greater than for 239 , 240 Pu. However, the latter radionuclides had a greater proportion contained in the mineral soil. This observation is consistent with the more recent releases containing a higher percentage of 238 Pu from reprocessing operation. Plutonium concentrations in the 5 to 15 cm depth indicated limited Pu mobility in soil, but 238 , 240 Pu concentrations at this depth were higher near tree stems, suggesting greater mobility perhaps as a result of stem flow

New long-term plan of nuclear development and perspectives of nuclear fuel cycle policy

International Nuclear Information System (INIS)

Uchiyama, Yohji

2005-01-01

Japan's nuclear fuel cycle policy, recently issued as an interim report of the Council to Formulate the New Long-Term Nuclear Program of the Atomic Energy Commission, is summarized and briefly explained together with the concluding remarks from the sub-committee for discussing technical and economical problems on the spent nuclear fuels with the present state of the Rokkasho reprocessing plant in mind. As for the nuclear fuel treatment, the panel considered four scenarios: (1) total reprocessing (the reprocessing for spent fuel after an appropriate period of storage); (2) partial reprocessing (spent fuel is reprocessed, with direct disposal of any spent fuel in excess of reprocessing capacity); (3) total direct disposal (direct disposal of all spent fuel); and (4) temporary storage (spent fuel is temporarily stored, and in about 2060 a choice will be made about whether to reprocess it or directly dispose of it). These four scenarios were studied from various perspectives, namely: (1) ensuring safety; (2) energy security; (3) environmental compatibility; (4) economic efficiency; (5) nuclear nonproliferation; (6) technical feasibility; (7) social acceptance; (8) securing choices; (9) issues concerning change in policy; and (10) overseas trends. Regarding economic efficiency, the council in particular conducted detailed studies and reassessment of nuclear fuel cycle costs. Scenario 1 (total reprocessing) is about 0.5-0.7 yen/kWh higher than scenario 3 (total direct disposal). However, looking at the situation from the perspectives of energy security, that is the stable supply and moderate use of resources, and environmental compatibility, scenario 1 (total reprocessing) can be evaluated as superior to the other scenarios. And more importantly, if the fast-breeder reactor cycle is commercialized, this superiority increases considerably. (S. Ohno)

Italian experience with pilot reprocessing plants

International Nuclear Information System (INIS)

Cao, S.; Dworschak, H.; Rolandi, G.; Simonetta, R.

1977-01-01

Problems and difficulties recently experienced in the reprocessing technology of high burnup power reactor fuel elements have shown the importance of pilot plant experiments to optimize the separation processes and to test advanced equipment on a representative scale. The CNEN Eurex plant, in Saluggia (Vercelli), with a 50 kg/d thruput, in operation since '71, has completed several reprocessing campaigns on MTR type fuel elements. Two different chemical flowsheets based respectively on TBP and tertiary amines were thoroughly tested and compared: a concise comparative evaluation of the results obtained with the two schemes is given. Extensive modifications have then been introduced (namely a new headend cell equipped with a shear) to make the plant suitable to reprocess power reactor fuels. The experimental program of the plant includes a joint CNEN-AECL reprocessing experiment on CANDU (Pickering) type fuel elements to demonstrate a two cycle, amine based recovery of the plutonium. Later, a stock of high burnup fuel elements from the PWR Trino power station will be reprocessed to recover Pu and U with a Purex type flowsheet. ITREC, the second CNEN experimental reprocessing plant located at Trisaia Nuclear Center (Matera), started active operation two years ago. In the first campaign Th-U mixed oxide fuel elements irradiated in the Elk River reactor were processed. Results of this experiment are reported. ITREC special design features confer a high degree of versability to the plant allowing for substantial equipment modification under remote control conditions. For this reason the plant will be principally devoted in the near future to advanced equipment testing. Along this line high speed centrifugal contactor of a new type developed in Poland will be tested in the plant in the frame of a joint experiment between CNEN and the Polish AEC. Later on the plant program will include experimental campaign on fast reactor fuels; a detailed study on this program is in

Geohydrologic conditions at the Nuclear Fuel Reprocessing Plant and Waste-Management Facilities at the western New York Nuclear Service Center, Cattaraugus County, New York

International Nuclear Information System (INIS)

Bergeron, M.P.; Kappel, W.M.; Yager, R.M.

1987-01-01

A nuclear-fuel reprocessing plant, a high-level radioactive liquid-waste tank complex, and related waste facilities occupy 100 hectares (ha) within the Western New York Nuclear Service Center near West Valley, NY. The facilities are underlain by glacial and postglacial deposits that fill an ancestral bedrock valley. The main plant facilities are on an elevated plateau referred to as the north plateau. Groundwater on the north plateau moves laterally within a surficial sand and gravel from the main plant building to areas northeast, east, and southeast of the facilities. The sand and gravel ranges from 1 to 10 m thick and has a hydraulic conductivity ranging from 0.1 to 7.9 m/day. Two separate burial grounds, a 4-ha area for low-level radioactive waste disposal and a 2.9-ha area for disposal of higher-level waste are excavated into a clay-rich till that ranges from 22 to 28 m thick. Migration of an organic solvent from the area of higher level waste at shallow depth in the till suggests that a shallow, fractured, oxidized, and weathered till is a significant pathway for lateral movement of groundwater. Below this zone, groundwater moves vertically downward through the till to recharge a lacustrine silt and fine sand. Within the saturated parts of the lacustrine unit, groundwater moves laterally to the northeast toward Buttermilk Creek. Hydraulic conductivity of the till, based on field and laboratory analyses, ranges from 0.000018 to 0.000086 m/day

Reprocessed uranium recycling: the ideal and the facts

International Nuclear Information System (INIS)

Comte, D.

1998-01-01

Commercial reprocessing of Light Water Reactor (LWR) spent fuel provides Reprocessed Uranium (RepU) and plutonium, both products containing a large amount of energy. As the gap, already quite large, between uranium consumption and production threatens to grow, these materials show today a strong strategic benefit, constituting a substantial and reliable source of supply for nuclear fuel manufacturing. RepU, which represents about 96% of recycled materials, can be used in all major types of nuclear power reactor currently in operation. This paper focuses on RepU recycling in LWRs, the feasibility of which is technically well established world-wide, and industrially demonstrated through experience gained within the COGEMA Group. Contrary to a commonly accepted assumption, which probably derives from natural uranium prices remaining for more than a decade at a low level which cannot be sustained into the future, recycling RepU can also bring strong economic benefits to the utilities. It generates savings on uranium procurement that exceed expenditures associated with storing and processing RepU. Thus, the use of this product is an attractive option. The strategic and economic benefits of recycling RepU will become compelling in the near future. Anticipating these needs, the COGEMA Group has developed capabilities to offer utilities the services covering all steps from reprocessing of spent fuel to fuel fabrication using RepU. (author)

Noble gas atmospheric monitoring at reprocessing facilities

International Nuclear Information System (INIS)

Nakhleh, C.W.; Perry, R.T. Jr.; Poths, J.; Stanbro, W.D.; Wilson, W.B.; Fearey, B.L.

1997-01-01

The discovery in Iraq after the Gulf War of the existence of a large clandestine nuclear-weapon program has led to an across-the-board international effort, dubbed Programme 93+2, to improve the effectiveness and efficiency of International Atomic Energy Agency (IAEA) safeguards. One particularly significant potential change is the introduction of environmental monitoring (EM) techniques as an adjunct to traditional safeguards methods. Monitoring of stable noble gas (Kr, Xe) isotopic abundances at reprocessing plant stacks appears to be able to yield information on the burnup and type of the fuel being processed. To estimate the size of these signals, model calculations of the production of stable Kr, Xe nuclides in reactor fuel and the subsequent dilution of these nuclides in the plant stack are carried out for two case studies: reprocessing of PWR fuel with a burnup of 35 GWd/tU, and reprocessing of CAND fuel with a burnup of 1 GWd/tU. For each case, a maximum-likelihood analysis is used to determine the fuel burnup and type from the isotopic data

Spent fuel reprocessing system security engineering capability maturity model

International Nuclear Information System (INIS)

Liu Yachun; Zou Shuliang; Yang Xiaohua; Ouyang Zigen; Dai Jianyong

2011-01-01

In the field of nuclear safety, traditional work places extra emphasis on risk assessment related to technical skills, production operations, accident consequences through deterministic or probabilistic analysis, and on the basis of which risk management and control are implemented. However, high quality of product does not necessarily mean good safety quality, which implies a predictable degree of uniformity and dependability suited to the specific security needs. In this paper, we make use of the system security engineering - capability maturity model (SSE-CMM) in the field of spent fuel reprocessing, establish a spent fuel reprocessing systems security engineering capability maturity model (SFR-SSE-CMM). The base practices in the model are collected from the materials of the practice of the nuclear safety engineering, which represent the best security implementation activities, reflect the regular and basic work of the implementation of the security engineering in the spent fuel reprocessing plant, the general practices reveal the management, measurement and institutional characteristics of all process activities. The basic principles that should be followed in the course of implementation of safety engineering activities are indicated from 'what' and 'how' aspects. The model provides a standardized framework and evaluation system for the safety engineering of the spent fuel reprocessing system. As a supplement to traditional methods, this new assessment technique with property of repeatability and predictability with respect to cost, procedure and quality control, can make or improve the activities of security engineering to become a serial of mature, measurable and standard activities. (author)

Structural damage and chemical contaminants on reprocessed arthroscopic shaver blades.

Science.gov (United States)

Kobayashi, Masahiko; Nakagawa, Yasuaki; Okamoto, Yukihiro; Nakamura, Shinichiro; Nakamura, Takashi

2009-02-01

In response to socioeconomic pressure to cut budgets in medicine, single-use surgical instruments are often reprocessed despite potential biological hazard. To evaluate the quality and contaminants of reprocessed shaver blades. Reprocessed shaver blades have mechanical damage and chemical contamination. Controlled laboratory study. Seven blades and 3 abraders were reprocessed 1 time or 3 times and then were assessed. In the first part of the study, structural damage on the blades after 3 reprocessings was compared to that after 1 reprocessing using optical microscopy. In the second part, surface damage was observed using optical microscopy and scanning electron microscopy; elemental and chemical analyses of contaminants found by the microscopy were performed using scanning electron microscopy/energy dispersive x-ray spectroscopy, scanning Auger microscopy, and Fourier transform infrared spectroscopy. Optical microscopic examination revealed abrasion on the surface of the inner blade and cracks on the inner tube after 1 reprocessing. These changes were more evident after 3 reprocessings. Scanning electron microscopy/energy dispersive x-ray spectroscopy of the inner cutter of the blade reprocessed once showed contaminants containing calcium, carbon, oxygen, and silicon, and Fourier transform infrared spectroscopy demonstrated biological protein consisting mainly of collagen, some type of salts, and polycarbonate used in plastic molding. Scanning electron microscopy/energy dispersive x-ray spectroscopy of the inner cutter of the reprocessed abrader revealed contaminants containing carbon, calcium, phosphorous, and oxygen, and Fourier transform infrared spectroscopy showed H2O, hydroxyapatite, and hydroxyl proteins. Scanning Auger microscopy showed that the tin-nickel plating on the moving blade and abrader was missing in some locations. This is the first study to evaluate both mechanical damage and chemical contaminants containing collagen, hydroxyapatite, and salts

How can Korea secure uranium enrichment and spent fuel reprocessing rights?

International Nuclear Information System (INIS)

Roh, Seungkook; Kim, Wonjoon

2014-01-01

South Korea is heavily dependent on energy resources from other countries and nuclear energy accounts for 31% of Korea's electric power generation as a major energy. However, Korea has many limitations in uranium enrichment and spent fuel reprocessing under the current Korea-U.S. nuclear agreement, although they are economically and politically important to Korea due to a significant problems in nuclear fuel storages. Therefore, in this paper, we first examine those example countries – Japan, Vietnam, and Iran – that have made nuclear agreements with the U.S. or have changed their agreements to allow the enrichment of uranium and the reprocessing of spent fuel. Then, we analyze those countries' nuclear energy policies and review their strategic repositioning in the relationship with the U.S. We find that a strong political stance for peaceful usage of nuclear energy including the legislation of nuclear laws as was the case of Japan. In addition, it is important for Korea to acquire advanced technological capability such as sodium-cooled fast reactor (SFR) because SFR technologies require plutonium to be used as fuel rather than uranium-235. In addition, Korea needs to leverage its position in nuclear agreement between China and the U.S. as was the case of Vietnam

Reprocessing: A reasonable way of waste disposal

International Nuclear Information System (INIS)

Merz, E.

1986-01-01

Reprocessing is the only way to recover the valuable substances contained in the burnt fuel elements and to make them utilizable for energy generation again. It is easier to adapt a national solution to the special domestic needs than a waste management plant which is operated on an international basis and is therefore simpler to be implemented. It guarantees independence, stands for the meeting of requirements resulting from the Non-Proliferation Treaty and creates safe jobs. Furthermore, it offers more liberty in applying optimized recycling strategies. A national reprocessing industry leads to an improved competitive position in the nuclear business, due to technological development and demonstration. A country like the Federal Republic of Germany, which depends on exports, does need top-level technologies. (HSCH) [de

Safety culture aspects of managing for safety. Experience of a large nuclear reprocessing site

International Nuclear Information System (INIS)

Rycraft, H.S.

1996-01-01

The Nuclear Industry is going through turbulent times both in terms of public acceptance and business issues. Safety is one area which impacts on whether the business is allowed to continue, and how an organisation organizes itself. The need to cut costs to make nuclear power a viable energy resource, has forced the nuclear utilities to review manning policies, and management style, and in particular how to maintain safety standards during a period of change, and ultimately support continuing improvement of standards. The shrinking workforce requires a new style of management, one that depends more on the people of the organisation taking responsibility for safety at all levels of the organisation. Not only personal safety but the safety of their colleagues, general public and the environment. The safety culture of an organisation is indivisible from the company culture, each aspect of a culture influences the whole and so the balance between business, safety and quality, has to be managed. BNFL provides a full fuel cycle service to nuclear power plants, and associated services to many national and international organisations. The following notes are taken from the work carried out in the company, and mostly at the Nuclear Reprocessing and Waste storage Site at Sellafield, based in the North West of England. Following the recent re-organisation, the site now employs 6200 people and has a further 1500 contractors working on construction activities on the site. Activities on the site range from remote handling to hands on tasks, involving highly active materials to low level waste. (author)

TIGA Tide Gauge Data Reprocessing at GFZ

Science.gov (United States)

Deng, Zhiguo; Schöne, Tilo; Gendt, Gerd

2014-05-01

To analyse the tide gauge measurements for the purpose of global long-term sea level change research a well-defined absolute reference frame is required by oceanographic community. To create such frame the data from a global GNSS network located at or near tide gauges are processed. For analyzing the GNSS data on a preferably continuous basis the International GNSS Service (IGS) Tide Gauge Benchmark Monitoring Working Group (TIGA-WG) is responsible. As one of the TIGA Analysis Centers the German Research Centre for Geosciences (GFZ) is contributing to the IGS TIGA Reprocessing Campaign. The solutions of the TIGA Reprocessing Campaign will also contribute to 2nd IGS Data Reprocessing Campaign with GFZ IGS reprocessing solution. After the first IGS reprocessing finished in 2010 some improvements were implemented into the latest GFZ software version EPOS.P8: reference frame IGb08 based on ITRF2008, antenna calibration igs08.atx, geopotential model (EGM2008), higher-order ionospheric effects, new a priori meteorological model (GPT2), VMF mapping function, and other minor improvements. GPS data of the globally distributed tracking network of 794 stations for the time span from 1994 until end of 2012 are used for the TIGA reprocessing. To handle such large network a new processing strategy is developed and described in detail. In the TIGA reprocessing the GPS@TIGA data are processed in precise point positioning (PPP) mode to clean data using the IGS reprocessing orbit and clock products. To validate the quality of the PPP coordinate results the rates of 80 GPS@TIGA station vertical movement are estimated from the PPP results using Maximum Likelihood Estimation (MLE) method. The rates are compared with the solution of University of LaRochelle Consortium (ULR) (named ULR5). 56 of the 80 stations have a difference of the vertical velocities below 1 mm/yr. The error bars of PPP rates are significant larger than those of ULR5, which indicates large time correlated noise in

HTGR fuel reprocessing technology

International Nuclear Information System (INIS)

Brooks, L.H.; Heath, C.A.; Shefcik, J.J.

1976-01-01

The following aspects of HTGR reprocessing technology are discussed: characteristics of HTGR fuels, criteria for a fuel reprocessing flowsheet; selection of a reference reprocessing flowsheet, and waste treatment

Materials management in an internationally safeguarded fuels reprocessing plant

International Nuclear Information System (INIS)

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

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

Assembly of laboratory line for nuclear fuel reprocessing

International Nuclear Information System (INIS)

Fidler, J.; Chotivka, V.

1979-01-01

The dismantling of a laboratory line for spent fuel reprocessing after the termination of the research programme and the procedures for hot and semi-hot cell decontamination are described. The equipment was mostly disassembled in smaller parts which were then decontaminated by wiping them with cotton wool soaked in detergent and citric acid, varnished with two-component epoxi varnish, wrapped into multiple polyethylene foils, sealed in PVC bags and thus ready for transport. (B.S.)

Applications of liquid phase chromatographies for the analysis of streams arising at the back end of nuclear fuel cycle

International Nuclear Information System (INIS)

Deshingkar, D.S.; Yalmali, Vrunda S.; Wattal, P.K.

2000-06-01

India has opted for a closed fuel cycle comprising of reprocessing and recycling technology. The back end of such nuclear fuel cycle involves the reprocessing of spent nuclear fuels for recovery of plutonium and depleted uranium by Purex technology. Wastes arising from the reprocessing plant are classified as high, intermediate and low level wastes (HLW, ILW, LLW). HLW is mixture of over 50 elements present in different chemical forms. The accurate analyses of dissolver solution and HLW are the most challenging but essential tasks for reprocessing plant operations and also for further development of treatment methods. Inductively coupled plasma - atomic emission spectroscopy and atomic absorption spectroscopy techniques are suitable for analysis of metallic anions. Ion chromatography has proven capability to analyse number of cations or anions at ppm or even ppb level in single run. The report reviews the literature regarding the title subject. To assess the technical feasibility of ion chromatography for waste analysis, a simulated PHWR-HLW analogue was prepared. The PHWR-HLW analogue and ground water samples were analysed on DIONEX-DX 500 and Metrohm IC. Results obtained clearly demonstrated the usefulness of ion chromatography as vital analytical tool. HLW and other process or waste streams arising at the back end of nuclear fuel cycle can be analysed for alkali, alkaline earth, rare earth and transition metal cations and important anions. Use of fraction collector along with ion chromatography can enhance it's sensitivity to few Bq/ml for radioactive samples. (author)

Reprocessing and Waste Treatment Project. Status report 1975, 17 November 1975

International Nuclear Information System (INIS)

Issel, W.

This paper reviews the development and position of industrial reprocessing of nuclear fuels in the German Federal Republic. The KEWA concept is mentioned in particular. Cost estimation and risk are considered

The today nuclear park

International Nuclear Information System (INIS)

Girard, Ph.; Marignac, Y.; Tassart, J.

2000-03-01

This economic analysis of the nuclear industry, takes stock on the french nuclear park, the nuclear materials flux, the operating and in construction from 1970 to 1998 reactors, the storage and the wastes reprocessing. The second part proposes many scenario in function of the reactors lifetime and the industrial policy of fuel reprocessing. This analysis shows the interest of extending the power plants lifetime and evaluates the consequences of a reprocessing-recycling policy facing the stop of such a policy in 2010. (A.L.B.)

Reprocessing of spent nuclear fuel; Prerada isluzenog nuklearnog goriva

Energy Technology Data Exchange (ETDEWEB)

Gal, I [Institute of Nuclear Sciences Boris Kidric, Laboratorija za visoku aktivnost, Vinca, Beograd (Serbia and Montenegro)

1963-12-15

This report covers: chemical-technology investigation of modified purex process for reprocessing of spent fuel; implementation of the procedure for obtaining plutonium peroxide and oxalate; research in the field of uranium, plutonium, and fission products separation by inorganic ion exchangers and extraction by organic solutions; study of the fission products in the heavy water RA reactor.

The main methods of solving the problem of radioactive waste management from nuclear power stations and spent fuel reprocessing plants in the USSR

International Nuclear Information System (INIS)

1978-09-01

The main directions of solving the problem of radioactive waste management from nuclear power stations and radiochemical plants, the aspects of gaseous waste management, liquid HLW storage in vessels and the problems of heat removal during storage of vitrified HLW in surface storages are considered. The main problems arising during fine decontamination of gaseous discharges from nuclear power stations and reprocessing plants are discussed. The migration of fission products in the environment and technical aspects of their capture from gaseous discharges are also considered

Fast reactor fuel reprocessing development in the United States: an overview

International Nuclear Information System (INIS)

Groenier, W.S.; Burch, W.D.

1979-01-01

As a result of the reduced nuclear power demand and the growing concerns over the potential proliferation of sensitive nuclear materials, there has not been a necessity to make immediate decisions regarding near-term reprocessing and breeder reactor commercialization. Programs which formed the basic thrust of nuclear development in the early 1970's have already been adjusted: increased emphasis on problems of radioactive waste management; increased attention to nonproliferation objectives and subsequent reorientation of the overall fuel cycle and breeder programs; increased emphasis on a once-through light-water reactor technology; increased concern for a more detailed knowledge of the uranium resource base; reorientation of the uranium enrichment programs; and exploration of alternative fuel cycles (such as thorium) to minimize the use of plutonium. Nevertheless, major strategic decisions still loom over breeder commercialization, the breeder's requisite demand for reprocessing, and the future role of more proliferation-resistant nuclear technologies. The current program in the United States is organized to provide the necessary technology for the reprocessing of breeder fuels on a timetable that is consistent with the reactor development and demonstration program. Also addressed in this paper are the present day concerns of environmental protection, safety, nuclear material safeguards, and proliferation resistance. It is structured on the well-known Purex processing method but includes new efforts aimed at advanced and alternative fuels. At the present time, the program consists mainly of a generic effort that is planned to progress through an integrated equipment engineering demonstration to an eventual pilot-plant operation. Each of these facilities is viewed as a test bed for advanced and alternative processing steps to address the many significant technical and political issues. 16 figures

The reprocessing-recycling of spent nuclear fuel. Actinides separation - Application to wastes management; Le traitement-recyclage du combustible nucleaire use. La separation des actinides - Application a la gestion des dechets

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

After its use in the reactor, the spent fuel still contains lot of recoverable material for an energetic use (uranium, plutonium), but also fission products and minor actinides which represent the residues of nuclear reactions. The reprocessing-recycling of the spent fuel, as it is performed in France, implies the chemical separation of these materials. The development and the industrial implementation of this separation process represent a major contribution of the French science and technology. The reprocessing-recycling allows a good management of nuclear wastes and a significant saving of fissile materials. With the recent spectacular rise of uranium prices, this process will become indispensable with the development of the next generation of fast neutron reactors. This book takes stock of the present and future variants of the chemical process used for the reprocessing of spent fuels. It describes the researches in progress and presents the stakes and recent results obtained by the CEA. content: the separation of actinides, a key factor for a sustainable nuclear energy; the actinides, a discovery of the 20. century; the radionuclides in nuclear fuels; the aquo ions of actinides; some redox properties of actinides; some complexing properties of actinide cations; general considerations about treatment processes; some characteristics of nuclear fuels in relation with their reprocessing; technical goals and specific constraints of the PUREX process; front-end operations of the PUREX process; separation and purification operations of the PUREX process; elaboration of finite products in the framework of the PUREX process; management and treatment of liquid effluents; solid wastes of the PUREX process; towards a joint management of uranium and plutonium: the COEX{sup TM} process; technical options of treatment and recycling techniques; the fuels of generation IV reactors; front-end treatment processes of advanced fuels; hydrometallurgical processes for future fuel

Plant for retention of 14C in reprocessing plants for LWR fuel elements

International Nuclear Information System (INIS)

Braun, H.; Gutowski, H.; Bonka, H.; Gruendler, D.

1983-01-01

The 14 C produced from nuclear power plants is actually totally emitted from nuclear power plants and reprocessing plants. Using the radiation protection principles proposed in ICRP 26, 14 C should be retained at heavy water moderated reactors and reprocessing plants due to a cost-benefit analysis. In the frame of a research work to cost-benefit analysis, which was sponsored by the Federal Minister of the Interior, an industrial plant for 14 C retention at reprocessing plants for LWR fuel elements has been planned according to the double alkali process. The double alkali process has been chosen because of the sufficient operation experience in the conventional chemical technique. In order to verify some operational parameters and to gain experiences, a cold test plant was constructed. The experiment results showed that the double alkali process is a technically suitable method with high operation security. Solidifying CaCO 3 with cement gives a product fit for final disposal

Radiation and environmental safety of spent nuclear fuel management options based on direct disposal or reprocessing and disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Vuori, S.

1996-05-01

The report considers the various stages of two nuclear fuel cycle options: direct disposal and reprocessing followed by disposal of vitrified high-level waste. The comparative review is based on the results of previous international studies and concentrates on the radiation and environmental safety aspects of technical solutions based on today's technology. (23 refs., 7 figs., 4 tabs.)

Papers presented at the 7th status report of the Reprocessing and Waste Treatment Project

International Nuclear Information System (INIS)

1988-10-01

The report contains all lectures on the present state of the R+D work which were delivered on the occasion of the 7th seminar on the present state of the Reprocessing and Waste Treatment Project in the Karlsruhe Nuclear Research Centre on 15/16 March 1988. The project is aimed at improving methods for nuclear waste disposal with regard to the German reprocessing plant for light-water reactor fuels currently under construction in Wackersdorf. The individual contributions were separately adapted for the INIS and EDB data banks. (RB) [de

Description of solid waste expected from a large commercial reprocessing plant

International Nuclear Information System (INIS)

Keely, R.B.

1979-01-01

Both low-level and high-level solid wastes generated during reprocessing of spent nuclear fuel are characterized in this paper with respect to source, quantity, content, radioactivity, potential volume reduction, and transuranic content

Technology development of fast reactor fuel reprocessing technology in India

International Nuclear Information System (INIS)

Natarajan, R.; Raj, Baldev

2009-01-01

India is committed to the large scale induction of fast breeder reactors beginning with the construction of 500 MWe Prototype Fast Breeder Reactor, PFBR. Closed fuel cycle is a prerequisite for the success of the fast reactors to reduce the external dependence of the fuel. In the Indian context, spent fuel reprocessing, with as low as possible out of pile fissile inventory, is another important requirement for increasing the share in power generation through nuclear route as early as possible. The development of this complex technology is being carried out in four phases, the first phase being the developmental phase, in which major R and D issues are addressed, while the second phase is the design, construction and operation of a pilot plant, called CORAL (COmpact Reprocessing facility for Advanced fuels in Lead shielded cell. The third phase is the construction and operation of Demonstration of Fast Reactor Fuel Reprocessing Plant (DFRP) which will provide experience in fast reactor fuel reprocessing with high availability factors and plant throughput. The design, construction and operation of the commercial plant (FRP) for reprocessing of PFBR fuel is the fourth phase, which will provide the requisite confidence for the large scale induction of fast reactors

Dissolution studies of spent nuclear fuels

International Nuclear Information System (INIS)

1991-02-01

To obtain quantitative data on the dissolution of high burnup spent nuclear fuel, dissolution study have been carried out at the Department of Chemistry, JAERI, from 1984 under the contract with STA entitled 'Reprocessing Test Study of High Burnup Fuel'. In this study PWR spent fuels of 8,400 to 36,100 MWd/t in averaged burnup were dissolved and the chemical composition and distribution of radioactive nuclides were measured for insoluble residue, cladding material (hull), off-gas and dissolved solution. With these analyses basic data concerning the dissolution and clarification process in the reprocessing plant were accumulated. (author)

Radioactive effluents from nuclear power stations and nuclear fuel reprocessing plants in the European Community

International Nuclear Information System (INIS)

Luykx, F.; Fraser, G.

1983-01-01

The report covers operational nuclear power stations of capacity greater than 5C MWe and nucler fuel reprocessing plants in the European Community. Radioactive gaseous and liquid effluent discharges from these installations are given for the period 1976 to 1980, expressed both in absolute terms and normalized to net electricity production from the fuel. An assesssment is then made of exposure of members of the public consequent to the 1980 discharges. Where environmental contamination levels were detectable the results have been taken into account in the dose assessment; however, environmental contamination was in general below the limit of detection. In these circumstances the dose estimates rely entirely on theoretical models which frequently incorporate conservative assumptions; hence these estimates are likely to be greater than the doses actually received. The estimated exposures have then been compared with the dose limits set out in the Euratom Directive of 15th July, 1980. It is concluded that the exposure of members of the public always left an appreciable safety margin relative to the limits and indeed lay within the variations in exposure which result from natural background

Hydrothermal synthesis for fabrication and reprocessing of MOX nuclear fuel

International Nuclear Information System (INIS)

Ohta, Suguru; Yamamura, Tomoo; Shirasaki, Kenji; Satoh, Isamu; Shikama, Tatsuo

2011-01-01

To improve the nuclear proliferation resistance and to minimize use of chemicals, a new reprocessing and fabrication process of 'mixed oxide' (MOX) fuel was proposed and studied by using simulated spent fuel solutions. The process is consisting of the two steps, i.e. the removal of fission product (FP) from dissolved spent fuel by using carbonate solutions (Step-1), and hydrothermal synthesis of uranium dioxides (Step-2). In Step-1, rare earth (the precipitation ratio: 90%) and alkaline earth (10-50% for Sr) as FP were removed based on their low solubility of hydroxides and carbonate salts, with uranium kept dissolved for the certain carbonate solutions of weak base (Type 2) or mixtures of relatively strong base and weak base (Type 3). In Step-2, the features of uranium dioxides UO 2+x particles, i.e. stoichiometry (x=0.05-0.2), size (0.2-3 μm) and shape (cubic, spherical, rectangular parallelpiped, etc.), were controlled, and the cesium was removed down to 40 ppm by an addition of organic additives. The decontamination factors (DF) for cesium exceeds 10 5 , whereas the total DF of all the simulated FP were as low as the order of 10 which requires future studies for removal of alkaline earth, Re and Tc etc. (author)

Status and trends in spent fuel reprocessing. Proceedings of an advisory group meeting

International Nuclear Information System (INIS)

1999-08-01

Spent fuel management has always been an important part of the nuclear fuel cycle and is still one of the most important activities in all countries exploiting the peaceful use of nuclear energy. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and to coordinate and encourage closer co-operation among Member States in certain research and developing activities that are of common interest. As part of spent fuel management, reprocessing activities have been reviewed from time to time on a low profile level under the terminology 'spent fuel treatment'. However, spent fuel treatment covers, in broad terms, spent fuel storage (short, interim and long term), fuel rod consolidation, reprocessing and, in case the once-through cycle is selected, conditioning of the spent fuel for disposal. Hence the reprocessing activities under the heading 'spent fuel treatment' were somewhat misleading. Several meetings on spent fuel treatment have been organized during the fast decade: an Advisory Group meeting (AGM) in 1992, a Technical Committee meeting in 1995 and recently an Advisory Group meeting from 7 to 10 September 1998. The objectives of the meetings were to review the status and trends of spent fuel reprocessing, to discuss the environmental impact and safety aspects of reprocessing facilities and to define the most important issues in this field. Notwithstanding the fact that the Summary of the report does not include aspects of military reprocessing, some of the national presentations do refer to some relevant aspects (e.g. experience, fissile stockpiles)

Outline of human machine interface at Rokkasho reprocessing plant

International Nuclear Information System (INIS)

Niioka, T.; Miyazaki, T.; Fujita, D.; Esashika, A.; Yoshida, Y.; Nakamura, W.; Tochigi, T.; Yoshimoto, A.; Yokoi, M.

2006-01-01

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)

EdF speaks about economic advantages of fuel reprocessing as compared with interim storage

International Nuclear Information System (INIS)

Anon.

1997-01-01

The French company Electricite de France (EdF) will prefer nuclear fuel reprocessing and plutonium recycling to spent fuel storage also in the years after 2000. This option is economically advantageous if the proportional cost of reprocessing does not exceed 1900 FRF/kg heavy metal. Economic analysis shows that this is feasible. EdF will soon have to reprocess annually about 1000 Mt spent fuel to supply enough plutonium for MOX fuel fabrication to feed as many as 28 PWR units and the Superphenix reactor. Spent fuel reprocessing is seen as promising as long as the efficiency of the MOX fuel approaches that of natural uranium based fuel. The French national industrial, political and legal context of EdF operations is also considered. (P.A.)

Processes for the control of 14CO2 during reprocessing

International Nuclear Information System (INIS)

Notz, K.J.; Holladay, D.W.; Forsberg, C.W.; Haag, G.L.

1980-01-01

The fixation of 14 CO 2 may be required at some future time because of the significant fractional contribution of 14 C, via the ingestion pathway, to the total population dose from the nuclear fuel cycle, even though the actual quantity of this dose is very small when compared to natural background. The work described here was done in support of fuel reprocessing development, of both graphite fuel (HTGRs) and metal-clad fuel (LWRs and LMFBRs), and was directed to the control of 14 CO 2 released during reprocessing operations. However, portions of this work are also applicable to the control of 14 CO 2 released during reactor operation. The work described falls in three major areas: (1) The application of liquid-slurry fixation with Ca(OH) 2 , which converts the CO 2 to CaCO 3 , carried out after treatment of the CO 2 -containing stream to remove other gaseous radioactive components, mainly 85 Kr. This approach is primarily for application to HTGR fuel reprocessing. (2) The above process for CO 2 fixation, but used ahead of Kr removal, and followed by a molecular sieve process to take out the 85 Kr. This approach was developed for use with HTGR reprocessing, but certain aspects also have application to metal-clad fuel reprocessing and to reactor operation. (3) The use of solid Ba(OH) 2 hydrate reacting directly with the gaseous phase. This process is generally applicable to both reprocessing and to reactor operation

Policy in France regarding the back-end of the fuel cycle reprocessing/recycling route

International Nuclear Information System (INIS)

Gloaguen, A.; Lenail, B.

1991-01-01

The decision taken in early 1970s to base the French power policy on the use of pressurized water reactors also included the strategy for the back end of the nuclear fuel cycle based on reprocessing, waste conditioning for the final disposal in the most suitable form in terms of safety and plutonium recycling to fast breeder reactors. Twenty years have elapsed, and substantial development and investment have been made. New evidences have emerged especially regarding breeder development, and the initial choice has been proved to be sound. EDF and COGEMA, the French utility and fuel cycle companies, respectively, are working together in order to take the best advantage of past efforts. The good behavior of MOX fuel in EDF reactors and the excellent start of the UP3 reprocessing plant of La Hague, which was completed and commissioned in August, 1990, made EDF and COGEMA extremely confident for future decision. The French choice made in favor of fuel reprocessing the history of fuel reprocessing in France, the policy concerning the back end of nuclear fuel cycle of EDF, and the present consideration and circumstances on this matter are reported. (K.I.)

Enhancement of safety for reprocessing facilities

International Nuclear Information System (INIS)

2012-06-01

The adequacy of the safety measures for utility loss accidents in nuclear fuel reprocessing facilities which have been formulated by the nuclear enterprises is investigated in JNES which organizes an advanced committee to specifically study this problem. The results are reviewed in the present report including the case of such severe accidents as in Fukushima Daiichi Nuclear Power Plant. The report also represents a tentative proposal for examination standards of such unimaginable severe accidents as 'station blackout,' urgent safety measures necessary for reoperation of nuclear power plants and requested by nuclear and industrial safety agency, and pointing out and clarification of the potential weakness from the safety point of view, and collective and composite evaluation of safety of the relevant facilities. Furthermore, the definition of accident management is given as of controlled condition and the authorized way of thinking for the cases of plural events happening at the same time and the cases when risks exist radioactivity emits with explosion. (S. Ohno)

Nuclear links

International Nuclear Information System (INIS)

1981-01-01

The subject is dealt with in sections: introduction; energy and the third world; world energy consumption 1978; oil -the energy dilemma; nuclear chains - introduction; uranium; Namibia; enrichment and reprocessing; countries with enrichment and reprocessing facilities; waste; conclusion; why take the nuclear option; third world countries with nuclear reactors; the arms connection; government spending and human resources 1977 (by countries); nuclear power - the final solution; the fascists; world bank; campaigns; community action in Plogoff; Australian labour movement; NUM against nuclear power; Scottish campaign; students against nuclear energy; anti-nuclear campaign; partizans; 3W1 disarmament and development; campaign ATOM; CANUC; 3W1; SANE. (U.K.)

Economic analyses of LWR fuel cycles

International Nuclear Information System (INIS)

Field, F.R.

1977-05-01

An economic comparison was made of three options for handling irradiated light-water reactor (LWR) fuel. These options are reprocessing of spent reactor fuel and subsequent recycle of both uranium and plutonium, reprocessing and recycle of uranium only, and direct terminal storage of spent fuel not reprocessed. The comparison was based on a peak-installed nuclear capacity of 507 GWe by CY 2000 and retirement of reactors after 30 years of service. Results of the study indicate that: Through the year 2000, recycle of uranium and plutonium in LWRs saves about $12 billion (FY 1977 dollars) compared with the throwaway cycle, but this amounts to only about 1.3% of the total cost of generating electricity by nuclear power. If deferred costs are included for fuel that has been discharged from reactors but not reprocessed, the economic advantage increases to $17.7 billion. Recycle of uranium only (storage of plutonium) is approximately $7 billion more expensive than the throwaway fuel cycle and is, therefore, not considered an economically viable option. The throwaway fuel cycle ultimately requires >40% more uranium resources (U 3 O 8 ) than does reprocessing spent fuel where both uranium and plutonium are recycled

Risk analyses of nuclear power plants

International Nuclear Information System (INIS)

Jehee, J.N.T.; Seebregts, A.J.

1991-02-01

Probabilistic risk analyses of nuclear power plants are carried out by systematically analyzing the possible consequences of a broad spectrum of causes of accidents. The risk can be expressed in the probabilities for melt down, radioactive releases, or harmful effects for the environment. Following risk policies for chemical installations as expressed in the mandatory nature of External Safety Reports (EVRs) or, e.g., the publication ''How to deal with risks'', probabilistic risk analyses are required for nuclear power plants

Guide to the selection, training, and licensing or certification of reprocessing plant operators. Volume I

International Nuclear Information System (INIS)

1976-06-01

The Code of Federal Regulations, Title 10, Part 55, establishes procedures and criteria for the licensing of operators, including senior operators, in ''Production and Utilization Facilities'', which includes plants for reprocessing irradiated fuel. A training guide is presented which will facilitate the licensing of operators for nuclear reprocessing plants by offering generalized descriptions of the basic principles (theory) and the unit operations (mechanics) employed in reprocessing spent fuels. In the present volume, details about the portions of a training program that are of major interest to management are presented

Guide to the selection, training, and licensing or certification of reprocessing plant operators. Volume I

Energy Technology Data Exchange (ETDEWEB)

None

1976-06-01

The Code of Federal Regulations, Title 10, Part 55, establishes procedures and criteria for the licensing of operators, including senior operators, in ''Production and Utilization Facilities'', which includes plants for reprocessing irradiated fuel. A training guide is presented which will facilitate the licensing of operators for nuclear reprocessing plants by offering generalized descriptions of the basic principles (theory) and the unit operations (mechanics) employed in reprocessing spent fuels. In the present volume, details about the portions of a training program that are of major interest to management are presented. (JSR)

Replacement of the glove box panel in nuclear fuel reprocessing facility

International Nuclear Information System (INIS)

Yamamoto, Masahiko; Shirouzu, Hidetomo; Mori, Eito; Surugaya, Naoki

2016-05-01

The panels for visual confirmation of glove box installed at Operation Testing Laboratory in Tokai Reprocessing Plant have been deteriorated and transparencies have been decreased due to the long-term use. Therefore, the glove box panels have been replaced from the view point of preventive maintenance. In the new regulation formulated since the accident at Tokyo Electric Power Company's Fukushima Daiichi Nuclear Power Station, it is demanded that the glove box consists of incombustible or noncombustible materials. In this replacement, the new panels have been manufactured with the polycarbonate which satisfied the UL94 V-0 incombustible class. The glove box has been in service for 40 years and its inside is contaminated with radioactive materials. Thus, the contaminations have been investigated and decontaminated before the replacement work. Then, operator's exposure and radiation protection equipment have been estimated. Also, it is necessary to replace the panels with maintaining the glove box's enclosure function. The replacement has been conducted in closed space covering the opening parts with vinyl sheets. The enclosure function has been verified by the inspection of the new panels and glove box. (author)

Radioactive wastes management in fiscal year 1983 in the fuel reprocessing plant

International Nuclear Information System (INIS)

1985-01-01

In the nuclear fuel reprocessing plant of Power Reactor and Nuclear Fuel Development Corporation, the releases of radioactive gaseous and liquid wastes are so managed not to exceed the respective objective release levels. Of the radioactive liquid wastes, the high level concentrated wastes are stored in tanks and the low level wastes are stored in tanks or asphalt solidified. For radioactive solid wastes, high level solid wastes are stored in casks, low level solid wastes and asphalt solids in drums etc. The releases of radioactive gaseous and liquid wastes in the fiscal year 1983 were below the objective release levels. The radioactive wastes management in the fuel reprocessing plant in fiscal year 1983 is given in tables, the released quantities, the stored quantities, etc. (Mori, K.)

Design and fabrication of stainless steel components for long life of spent fuel reprocessing plants

International Nuclear Information System (INIS)

Natarajan, R.; Ramkumar, P.; Sundararaman, V.; Kamachi Mudali, U.; Baldev Raj; Shanmugam, K.

2010-01-01

Reprocessing of spent nuclear fuels based on the PUREX process is the proven process with many commercial plants operating satisfactorily worldwide. The process medium being nitric acid, austenitic stainless steel is the material of construction as it is the best commercially available material for meeting the conditions in the reprocessing plants. Because of the high radiation fields, contact maintenance of equipment and systems of these plants are very time consuming and costly unlike other chemical process plants. Though the plants constructed in the early years required extensive shut downs for replacement of equipment and systems within the first fifteen years of operation itself, development in the field of stainless steel metallurgy and fabrication techniques have made it possible to design the present day plants for an operating life period of forty years. A review of the operational experience of the PUREX process based aqueous reprocessing plants has been made in this paper and reveals that life limiting failures of equipment and systems are mainly due to corrosion while a few are due to stresses. Presently there are no standards for design specification of materials and fabrication of reprocessing plants like the nuclear power plants, where well laid down ASTM and ASME codes and standards are available which are based on the large scale operational feedbacks on pressure vessels for conventional and nuclear industries. (author)

Chemical engineering in fuel reprocessing. The French experience

International Nuclear Information System (INIS)

Viala, M.; Sombret, C.; Bernard, C.; Miquel, P.; Moulin, J.P.

1992-01-01

Reprocessing is the back-end of the nuclear fuel cycle, designed to recover valuable fissile materials, especially plutonium, and to condition safely all the wastes ready for disposal. For its new commercial reprocessing plants (UP 3 and UP 2 800) COGEMA decided to include many engineering innovations as well as new processes and key-components developed by CEA. UP 3 is a complete new plant with a capacity of 800 t/y which was put in operation in August 1990. UP 2 800 is an extension of the existing UP 2 facility, designed to achieve the same annual capacity of 800 t/y, to be put in operation at the end of 1993 by the commissioning of a new head-end and highly active chemical process facilities

Nuclear fuel reprocessing

International Nuclear Information System (INIS)

White, D.

1981-01-01

A simple friction device for cutting nuclear fuel wrappers comprising a thin metal disc clamped between two large diameter clamping plates. A stream of gas ejected from a nozzle is used as coolant. The device may be maintained remotely. (author)

Reprocessing process simulation network; PRONET

International Nuclear Information System (INIS)

Mitsui, T.; Takada, H.; Kamishima, N.; Tsukamoto, T.; Harada, N.; Fujita, N.; Gonda, K.

1991-01-01

The effectiveness of simulation technology and its wide application to nuclear fuel reprocessing plants has been recognized recently. The principal aim of applying simulation is to predict the process behavior accurately based on the quantitative relations among substances in physical and chemical phenomena. Mitsubishi Heavy Industries Ltd. has engaged positively in the development and the application study of this technology. All the software products of its recent activities were summarized in the integrated form named 'PRONET'. The PRONET is classified into two independent software groups from the viewpoint of computer system. One is off-line Process Simulation Group, and the other is Dynamic Real-time Simulator Group. The former is called 'PRONET System', and the latter is called 'PRONET Simulator'. These have several subsystems with the prefix 'MR' meaning Mitsubishi Reprocessing Plant. Each MR subsystem is explained in this report. The technical background, the objective of the PRONET, the system and the function of the PRONET, and the future application to an on-line real-time simulator and the development of MR EXPERT are described. (K.I.)

Spent nuclear fuel storage

International Nuclear Information System (INIS)

Romanato, Luiz Sergio

2005-01-01

When a country becomes self-sufficient in part of the nuclear cycle, as production of fuel that will be used in nuclear power plants for energy generation, it is necessary to pay attention for the best method of storing the spent fuel. Temporary storage of spent nuclear fuel is a necessary practice and is applied nowadays all over the world, so much in countries that have not been defined their plan for a definitive repository, as well for those that already put in practice such storage form. There are two main aspects that involve the spent fuels: one regarding the spent nuclear fuel storage intended to reprocessing and the other in which the spent fuel will be sent for final deposition when the definitive place is defined, correctly located, appropriately characterized as to several technical aspects, and licentiate. This last aspect can involve decades of studies because of the technical and normative definitions at a given country. In Brazil, the interest is linked with the storage of spent fuels that will not be reprocessed. This work analyses possible types of storage, the international panorama and a proposal for future construction of a spent nuclear fuel temporary storage place in the country. (author)

Summary of plutonium terrestrial research studies in the vicinity of a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Corey, J.C.; Boni, A.L.; Andriano, D.C.; Pinder, J.F.; McLeod, K.W.

1978-01-01

This paper reports plutonium concentrations of wheat, soybeans, and corn grown (a) on a field adjacent to one of the nuclear reprocessing facilities at the Savannah River Plant (SRP), (b) in a glasshouse, and (c) offsite. The crops on SRP were grown on a field that has been receiving both fallout plutonium and plutonium emitted at low chronic levels from an air exhaust stack since 1955. The crops grown in the glasshouse were raised on soil from the onsite agricultural field. The offsite field has received only fallout plutonium. The crop data indicate that the dose to an individual from ingesting grain grown on the field, although higher than from ingesting grain grown offsite, is still small (the 70-year dose-to-bone from eating 2 X 10 5 g (440 lb) of wheat in a year would be less than one mrem). Crop data from the field and the glasshouse experiment indicate that less than 10% of the total contamination of field-grown crops adjacent to a reprocessing facility was contributed by root uptake, the remainder by deposition on the plant surfaces. The plutonium content of the grain was generally 10 to 100 times less than that of the vegetation, again suggesting that deposition from stack emissions vegetation, again suggesting that deposition from stack emissions on the vegetation increased the plutonium content; whereas the grain, particularly corn and soybeans, was protected by thehusk or pod and contained principally plutonium from the root uptake pathway

Social awareness on nuclear fuel cycle

International Nuclear Information System (INIS)

Tanigaki, Toshihiko

2006-01-01

In the present we surveyed public opinion regarding the nuclear fuel cycle to find out about the social awareness about nuclear fuel cycle and nuclear facilities. The study revealed that people's image of nuclear power is more familiar than the image of the nuclear fuel cycle. People tend to display more recognition and concern towards nuclear power and reprocessing plants than towards other facilities. Comparatively speaking, they tend to perceive radioactive waste disposal facilities and nuclear power plants as being highly more dangerous than reprocessing plants. It is found also that with the exception of nuclear power plants don't know very much whether nuclear fuel cycle facilities are in operation in Japan or not. The results suggests that 1) the relatively mild image of the nuclear fuel cycle is the result of the interactive effect of the highly dangerous image of nuclear power plants and the less dangerous image of reprocessing plants; and 2) that the image of a given plant (nuclear power plant, reprocessing plant, radioactive waste disposal facility) is influenced by the fact of whether the name of the plant suggests the presence of danger or not. (author)

West Valley Reprocessing Plant. Safety analysis plant, supplement 18

International Nuclear Information System (INIS)

1975-01-01

Supplement 18 contains the following additions to Appendix II--5.0 Geology and Seismology: Section 12 ''Seismic Investigations for Spent Fuel Reprocessing Facility at West Valley, New York,'' October 20, 1975, and Section 13 ''Earthquake Return Period Analysis at West Valley, New York, for Nuclear Fuel Services, Inc.'' November 5, 1975

Management of spent solvents of reprocessing origin

International Nuclear Information System (INIS)

Manohar, S.; Srinivas, C.; Vincent, T.; Wattal, P.K.

2001-01-01

Spent solvents of reprocessing origin constitute a major portion of radioactive liquid organic wastes arising from nuclear activity. An in-depth study of this waste stream has led to the evolution of a complete management option, which addresses not only the concern of radioactivity but also its organic nature. This is based on alkaline hydrolysis of Tri-n-butyl phosphate (TBP), which converts it into aqueous soluble products, viz. sodium salt of dibutyl phosphoric acid and butanol. During the process of alkaline hydrolysis almost all the activity associated with the waste gets transferred into the aqueous phase. The recovered diluent virtually free of activity and TBP can be recycled, and in case of it not meeting reprocessing standards, can be incinerated. The process generated aqueous waste is found compatible with cement and can be immobilized in cement matrix. (author)

Handling of spent nuclear fuel and final storage of vitrified high level reprocessing waste

International Nuclear Information System (INIS)

1978-01-01

A summary of the planning of transportation and plant design in the Swedish KBS project on management and disposal reprocessed radioactive waste. It describes a transportation system, a central storage facility for used fuel elements, a plant for intermediate storage and encapsulation and a final repository for the vitrified waste. Accounts are given for the reprocessing and vitrification. The safety of the entire system is discussed

The refurbishment of the D1206 fuel reprocessing plant

International Nuclear Information System (INIS)

Bailey, G.

1988-01-01

The term decommissioning can be applied not only to reactors but to any nuclear plant, laboratory, building or part of a building that may have been associated with radioactive material and needs to be restored to clean conditions. In this case the decommissioning and reconstruction of the Dounreay Fast Reactor fuel reprocessing plant, so that plutonium oxide could be reprocessed as well as enriched uranium fuel, is described. The work included improving containment and shielding, building a new head-end treatment cave for the more complex and larger fuel elements, improving the ventilation and constructing a new dissolver. In this paper the breakdown cave and dissolver cell are described and compared and the work done explained. (U.K.)

Reprocessing and fuel fabrication systems

International Nuclear Information System (INIS)

Field, F.R.; Tooper, F.E.

1978-01-01

The study of alternative fuel cycles was initiated to identify a fuel cycle with inherent technical resistance to proliferation; however, other key features such as resource use, cost, and development status are major elements in a sound fuel cycle strategy if there is no significant difference in proliferation resistance. Special fuel reprocessing techniques such as coprocessing or spiking provide limited resistance to diversion. The nuclear fuel cycle system that will be most effective may be more dependent on the institutional agreements that can be implemented to supplement the technical controls of fuel cycle materials

Reprocessing-recycling, or the application of the selective sorting and recycling policy to nuclear activities

International Nuclear Information System (INIS)

1998-12-01

In France, the reprocessing of spent fuels is the solution that has been retained for the management of the end-of-cycle. The sorting of the different components of spent fuels allows the recycling of uranium and plutonium for the further production of enriched uranium and mixed oxide fuels. This paper presents Cogema's advances in this domain (facilities and plants), the transfer of Cogema's reprocessing and recycling technologies in other countries (Japan, USA, Russia), the economical and environmental advantages of the recycling of spent fuels, the economical resources provided by this activity, and the cooperation with foreign countries for the reprocessing of their spent fuels at Cogema-La Hague. (J.S.)

Request from nuclear fuel cycle and criticality safety design

International Nuclear Information System (INIS)

Hamasaki, Manabu; Sakashita, Kiichiro; Natsume, Toshihiro

2005-01-01

The quality and reliability of criticality safety design of nuclear fuel cycle systems such as fuel fabrication facilities, fuel reprocessing facilities, storage systems of various forms of nuclear materials or transportation casks have been largely dependent on the quality of criticality safety analyses using qualified criticality calculation code systems and reliable nuclear data sets. In this report, we summarize the characteristics of the nuclear fuel cycle systems and the perspective of the requirements for the nuclear data, with brief comments on the recent issue about spent fuel disposal. (author)

Study of the chemical behaviour of technetium during irradiated fuels reprocessing

International Nuclear Information System (INIS)

Zelverte, A.

1988-04-01

This paper deals with the preparation of the lower oxidation states +III +IV and +V of technetium in nitric acid and its behaviour during the reprocessing of nuclear fuels (PUREX process). The first part of this work is a bibliographical study of this element in solution without any strong ligand. By chemical and electrochemical technics, pentavalent, tetravalent and trivalent technetium species, were prepared in nitric acid. The following chemical reactions are studied: - trivalent and tetravalent technetium oxidation by nitrate ion. - hydrazine and tetravalent uranium oxidation catalysed by technetium: in those reactions, we point out unequivocally the prominent part of trivalent and tetravalent technetium, - technetium behaviour towards hydroxylamine. Technetium should not cause any disturbance in the steps where hydroxylamine is employed to destroy nitrous acid and hydrazine replacement by hydroxylamine in uranium-plutonium partition could contribute to a best reprocessing of nuclear fuels [fr

Seismic investigation of the Nuclear Fuel Services, Inc., Reprocessing Plant at West Valley, New York

International Nuclear Information System (INIS)

Endebrock, E.G.; Bartholomew, R.J.; Bennett, J.G.; Brasier, R.I.; Corcoran, W.F.

1978-03-01

An investigation was undertaken to determine the earthquake level at which the Nuclear Fuel Service, Inc., Reprocessing Plant at West Valley, New York, could first experience a predefined structural failure. The effort was divided into tasks of evaluating soil-structure interaction, determining overall facility motion, and analyzing the substructures. The analysis included using two- and three-dimensional finite element computer codes. Shear wall failure, cell flexural failure (beam action), and foundation (pile) failure were identified as possible structural failure types. The cells that contain radioactive materials and that are required to confine such materials during an earthquake should remain intact up to 0.20 g's. At the same loading, the piles supporting the confinement cells could undergo displacements sufficient to cause fracture of piping between nonmonolithically connected cells

Remote systems and remote maintenance of a reprocessing plant in Japan

International Nuclear Information System (INIS)

Funaya, T.

1977-01-01

The design concept and overall maintenance philosophy applied in the Power Reactor and Nuclear Fuel Development Corporation Reprocessing Plant at Tokai-mura, Japan, are briefly introduced. Details on remote systems and remote maintenance in mechanical processing areas are described

Standard model for the safety analysis report of nuclear fuel reprocessing plants; Modelo padrao para relatorio de analise de seguranca de usinas de reprocessamento de combustiveis nucleares

Energy Technology Data Exchange (ETDEWEB)

NONE

1980-02-15

This norm establishes the Standard Model for the Safety Analysis Report of Nuclear Fuel Reprocessing Plants, comprehending the presentation format, the detailing level of the minimum information required by the CNEN for evaluation the requests of Construction License or Operation Authorization, in accordance with the legislation in force. This regulation applies to the following basic reports: Preliminary Safety Analysis Report - PSAR, integrating part of the requirement of Construction License; and Final Safety Analysis Report (FSAR) which is the integrating part of the requirement for Operation Authorization.

Plutonium, proliferation, and the price of reprocessing

International Nuclear Information System (INIS)

Gilinsky, V.

1978-01-01

France and Britain disagree with the US on whether deferring fuel reprocessing that provides plutonium for export can help contain proliferation. The US has veto power over reprocessing of US-supplied fuels for non-EURATOM countries, but exceptions will be made for movement within the EURATOM community. Political issues will be influenced by the magnitude of the financial investments, however, and commercial considerations have until recently dominated and complicated international safeguards. The author notes that US policy was reversed by the gradual acknowledgment that the same international inspection of plutonium stockpiles would not work as it had for low-enriched fuel and that economic interests must have a lower priority to avoiding proliferation. He cites the combination of sudden policy shifts, failure to prove that present reactors are best, and long-term distrust of US economic motives as failing to persuade either the French or British, who feel the best safeguard is provided by their high-security reprocessing facilities. Still to be resolved are the conditions under which plutonium must be returned to its owners, a problem that must determine safe international transport and storage and international management. Technical fixes, such as the CIVEX process, cannot contribute to the solution for several decades, while reprocessing is no longer considered a first step in waste disposal and would be more expensive and complicated than present waste disposal procedures. The author concedes merit in President Carter's requirement of separating ''the legitimate and necessary use of uranium'' and nuclear fuels that are also explosives

Radioactive effluents from nuclear power stations and reprocessing plants in the European Community

International Nuclear Information System (INIS)

1978-04-01

The report presents the available data on radioactive gaseous and liquid effluents discharged by nuclear power stations and nuclear fuel reprocessing plants in the European Community from 1972 to 1976. Discharges are expressed both in absolute terms and relative to the net production of electricity from the fuel. On the basis of the discharges recorded for 1976 the resulting maximum exposure of members of the population is quantified and compared with the dose limits prescribed by Euratom radiological protection standards and with the exposure resulting from natural radioactivity. It is concluded that there is no case in which a discharge could have given rise to an exposure exceeding the relevant prescribed limit. Not only did the possible maximum exposures incurred by individuals leave an appreciable safety margin relative to that limit but, for the vast majority of installations, they were comparable with or were considerably lower than the geographical and temporal variations in exposures resulting from natural radioactivity. Where environmental levels have been detectable the measured results have of course been used but, with few exceptions, the levels have remained less than the very low limits of detection currently possible. In general, where theoretical models are used to evaluate exposure, they are designed to give conservative results and hence it is likely that the true exposures are even less than those calculated

Experience in constructing a spent nuclear fuel reprocessing plant in Japan

International Nuclear Information System (INIS)

Hashimoto, K.; Sakuma, A.; Inoue, K.

1977-01-01

Towards the end of 1970, Japan Gasoline Co. Ltd. (JGC) and Saint-Gobain Techniques Nouvelles of France received an order for the construction of a reprocessing plant from Power Reactor and Nuclear Fuel Development Corporation, as a joint prime contractor. The work executed by JGC in this project is reported and consisted of: (1) Procurement, inspection and schedule control of equipment and materials other than those imported from Europe; (2) Conclusion of contracts with various subcontractors relating to the building construction, piping and other work; and (3) Supervision of field work. The field work began in June 1971 and was completed in about 40 months. The overall field labour mobilized during that time totalled about 410,000 man-days, and 900,000 man-hours were spent by the JGC engineers. With the object of constructing a high-quality plant, JGC since 1969 has started to investigate subcontractors in Japan as well as undertaking the selection, education and training of prospective subcontractors. For the welding work in particular, techniques were imported from France and domestic techniques were developed at the same time. Completion of the blank tests was estimated to require 33 months, but the schedule was delayed about seven months for various reasons. Obviously there is room for many improvements when constructing future nuclear chemical plants. However, careful consideration should also be given from the basic design stage onward, to the methods and sequence of construction so that a simplified plan can be obtained from which the work could be easily executed without resorting to special technology. This would lead to reduction in construction time, and a safer and more reliable plant at lower cost. (author)

Aerosols released in accidents in reprocessing plants

International Nuclear Information System (INIS)

Ballinger, M.Y.; Owczarski, P.C.; Hashimoto, K.; Nishio, G.; Jordan, S.; Lindner, W.

1987-01-01

For analyzing the thermodynamic and radiological consequences of solvent fire accidents in reprocessing plants, intensive investigations on burning contaminated condensible liquids were performed at Kernforschungszentrum Karlsruhe (KfK), Pacific Northwest Laboratory (PNL), and Japan Atomic Energy Research Institute (JAERI). In small- and large-scale tests, KfK studied the behavior of kerosene, tributyl phosphate, HNO 3 mixture fires in open air and closed containments. The particle release from uranium-contaminated pool fires was investigated. Different filter devices were tested. For analyzing fires, PNL has developed the FIRIN computer code and has generated small-scale fire data in support of that code. The results of the experiments in which contaminated combustible liquids were burned demonstrate the use of the FIRIN code in simulating a solvent fire in a nuclear reprocessing plant. To demonstrate the safety evaluation of a postulated solvent fire in an extraction process of a reprocessing pant, JAERI conducted large-scale fire tests. Behavior of solvent fires in a cell and the integrity of high-efficiency particulate air (HEPA) filters due to smoke plugging were investigated. To evaluate confinement of radioactive materials released from the solvent fire, the ventilation systems with HEPA filters were tested under postulated fire conditions

Technetium-99 and strontium-90: Abundance determination at ultratrace sensitivity by AMS as signatures of undeclared nuclear reprocessing activity

International Nuclear Information System (INIS)

McAninch, J.E.; Proctor, I.D.

1995-03-01

The purpose of this White Paper is to examine the use of the ultratrace technique Accelerator Mass Spectrometry (AMS) to lower detection limits for 99 Tc and 90 Sr, and to examine the utility of these isotopes as signatures of a convert reprocessing facility. The International Atomic Energy Agency (IAEA) has committed to improving the effectiveness of the IAEA Safeguards System. This is in some degree a result of the discovery in 1991 of an undeclared Iraqi EMIS program. Recommendations from the March 1993 Consultants Group Meeting have resulted in several studies and follow on field trials to identify environmental signatures from covert nuclear fuel reprocessing activity. In particular, the April, 1993 reports of the Standing Advisory Group on Safeguards Implementation (SAGSI) identified the long-lived radioisotopes Technetium-99 and strontium-90 as two reliable signatures of fuel reprocessing activity. This report also suggested pathways in the chemical processing of irradiated fuel where these elements would be volatilized and potentially released in amounts detectable with ultratrace sensitivity techniques. Based on measured 99 Tc background levels compiled from a variety of sources, it is estimated that AMS can provide 10% measurements of environmental levels of 99 Tc in a few minutes using modestly sized samples: a few grams for soils, plants, or animal tissues; one to several liters for rain or seawater samples; and tens to hundreds of cubic meters for air sampling. Small sample sizes and high sample throughput result in significant increases in feasibility, cost effectiveness, and quality of data for a regional monitoring program. Similar results are expected for 90 Sr

Safety aspects of LWR fuel reprocessing and mixed oxide fuel fabrication plants

International Nuclear Information System (INIS)

Fischer, M.; Leichsenring, C.H.; Herrmann, G.W.; Schueller, W.; Hagenberg, W.; Stoll, W.

1977-01-01

The paper is focused on the safety and the control of the consequences of credible accidents in LWR fuel reprocessing plants and in mixed oxide fuel fabrication plants. Each of these plants serve for many power reactor (about 50.000 Mwel) thus the contribution to the overall risk of nuclear energy is correspondingly low. Because of basic functional differences between reprocessing plants, fuel fabrication plants and nuclear power reactors, the structure and safety systems of these plants are different in many respects. The most important differences that influence safety systems are: (1) Both fuel reprocessing and fabrication plants do not have the high system pressure that is associated with power reactors. (2) A considerable amount of the radioactivity of the fuel, which is in the form of short-lived radionuclides has decayed. Therefore, fuel reprocessing plants and mixed oxide fuel fabrication plants are designed with multiple confinement barriers for control of radioactive materials, but do not require the high-pressure containment systems that are used in LWR plants. The consequences of accidents which may lead to the dispersion of radioactive materials such as chemical explosions, nuclear excursions, fires and failure of cooling systems are considered. A reasonable high reliability of the multiple confinement approach can be assured by design. In fuel reprocessing plants, forced cooling is necessary only in systems where fission products are accumulated. However, the control of radioactive materials can be maintained during normal operation and during the above mentioned accidents, if the dissolver off-gas and vessel off-gas treatment systems provide for effective removal of radioactive iodine, radioactive particulates, nitrogen oxides, tritium and krypton 85. In addition, the following incidents in the dissolver off-gas system itself must be controlled: failures of iodine filters, hydrogen explosion in O 2 - and NOsub(x)-reduction component, decomposition of

Mechanical and Instrumental Experiences from the Erection, Commissioning, and Operation of a Small Pilot Plant for Development Work on Aqueous Reprocessing of Nuclear Fuels

International Nuclear Information System (INIS)

Joensson, K.

1965-05-01

A radio chemical pilot plant for the reprocessing of irradiated nuclear fuels has been built by AB Atomenergi at Kjeller in Norway. In the report a short description of the main equipment is given as well as of the procedure during the erection of the plant. Finally the results and experiences from the cold tests, tracer tests and active runs are indicated

Mechanical and Instrumental Experiences from the Erection, Commissioning, and Operation of a Small Pilot Plant for Development Work on Aqueous Reprocessing of Nuclear Fuels

Energy Technology Data Exchange (ETDEWEB)

Joensson, K

1965-05-15

A radio chemical pilot plant for the reprocessing of irradiated nuclear fuels has been built by AB Atomenergi at Kjeller in Norway. In the report a short description of the main equipment is given as well as of the procedure during the erection of the plant. Finally the results and experiences from the cold tests, tracer tests and active runs are indicated.

Handling of spent nuclear fuel and final storage of vitrified high level reprocessing waste

International Nuclear Information System (INIS)

1978-01-01

The report gives a general summary of the Swedish KBS-project on management and disposal of vitrified reprocessed waste. Its final aim is to demostrate that the means of processing and managing power reactor waste in an absolutely safe way, as stipulated in the Swedish so called Conditions Act, already exist. Chapters on Storage facility for spent fuel, Intermidiate storage of reprocessed waste, Geology, Final repository, Transportation, Protection, and Siting. (L.E.)

Implications of ICPR 60 for nuclear fuel reprocessing in france

International Nuclear Information System (INIS)

Mathieu, P.

1992-01-01

The ICRP 60 publication intends to guide the regulatory agencies on the main rules and principle of protection. The text contains recommendations for practices and for emergencies. The following report intends to develop the possible consequences of the publication for the reprocessing of spent fuel as managed by COGEMA in the plants of La Hague and Marcoule. (author)

The Nuclear Fuel Cycle

International Nuclear Information System (INIS)

2011-08-01

This brochure describes the nuclear fuel cycle, which is an industrial process involving various activities to produce electricity from uranium in nuclear power reactors. The cycle starts with the mining of uranium and ends with the disposal of nuclear waste. The raw material for today's nuclear fuel is uranium. It must be processed through a series of steps to produce an efficient fuel for generating electricity. Used fuel also needs to be taken care of for reuse and disposal. The nuclear fuel cycle includes the 'front end', i.e. preparation of the fuel, the 'service period' in which fuel is used during reactor operation to generate electricity, and the 'back end', i.e. the safe management of spent nuclear fuel including reprocessing and reuse and disposal. If spent fuel is not reprocessed, the fuel cycle is referred to as an 'open' or 'once-through' fuel cycle; if spent fuel is reprocessed, and partly reused, it is referred to as a 'closed' nuclear fuel cycle.

Spent fuel management in France: Reprocessing, conditioning, recycling

International Nuclear Information System (INIS)

Giraud, J.P.; Montalembert, J.A. de

1994-01-01

The French energy policy has been based for 20 years on the development of nuclear power. The some 75% share of nuclear in the total electricity generation, representing an annual production of 317 TWh requires full fuel cycle control from the head-end to the waste management. This paper presents the RCR concept (Reprocessing, Conditioning, Recycling) with its industrial implementation. The long lasting experience acquired in reprocessing and MOX fuel fabrication leads to a comprehensive industrial organization with minimized impact on the environment and waste generation. Each 900 MWe PWR loaded with MOX fuel avoids piling up 2,500 m 3 per year of mine tailings. By the year 2000, less than 500 m 3 of high-level and long-lived waste will be annually produced at La Hague for the French program. The fuel cycle facilities and the associated MOX loading programs are ramping-up according to schedule. Thus, the RCR concept is a reality as well as a policy adopted in several countries. Last but not least, RCR represents a strong commitment to non-proliferation as it is the way to fully control and master the plutonium inventory

Spectrophotometric determination of zirconium with Chrome Azurol s in aqueous streams of nuclear fuel reprocessing

International Nuclear Information System (INIS)

Ganesh, S.; Velavendan, P.; Pandey, N.K.; Kamachi Mudali, U.; Natarajan, R.

2014-01-01

A sensitive and reproducible spectrophotometric method for the determination of zirconium is developed. The method is based on the formation of stable bluish violet colour complex with Chrome Azurol S (CAS) with maximum absorption at 598 nm. The complex formed obeys Beer's law in the range of 1-7 μg/mL. Under optimum conditions, the sensitivity of the proposed method, (i.e. the detection limit), molar absorptivity and Sandell's sensitivity values are 2.42 μg/mL, 3.93 x10 3 L.Mol -1 .cm -1 and 2.54 x 10 -4 μg/cm 2 respectively. Relative standard deviation is less than 2% and correlation coefficient is 0.997. The present method is highly sensitive, selective, rapid and simple. It can be applied for the direct determination of zirconium in environmental, industrial, water and nuclear reprocessing samples. (author)

Determination of free acidity in nuclear fuel reprocessing streams by fiber optic aided spectrophotometric technique

International Nuclear Information System (INIS)

Ganesh, S.; Velavendan, P.; Pandey, N.K.; Kamachi Mudali, U.; Natarajan, R.

2014-01-01

A fiber optic aided spectrophotometric technique has been developed for the determination of free acidity in nuclear fuel reprocessing streams. The developed method is simple, accurate and applicable to all ranges of nitric acid and heavy metal concentrations relevant to the purex process. The method is based on the formation of yellow colour with an acid-sensitive indicator such as chrome azurol s, the intensity of yellow colour is proportional to the acid concentration. The system obeys Lambert-Beer's law at 455 nm in the range of acidity 1-10 M of nitric acid. The results obtained are reproducible with standard deviation 2% and relative error is less than 3%. The results obtained by the developed technique are in good agreement with those obtained by the standard procedure. This method is adaptable for remote operation and on-line monitoring. (author)

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

International Nuclear Information System (INIS)

Jacobson, Victor Levon

2002-01-01

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 sodium-bearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements

Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing

Energy Technology Data Exchange (ETDEWEB)

Riley, Brian J.; Kroll, Jared O.; Peterson, Jacob A.; Pierce, David A.; Ebert, William L.; Williams, Benjamin D.; Snyder, Michelle M. V.; Frank, Steven M.; George, Jaime L.; Kruska, Karen

2017-11-01

This paper provides an overview of research evaluating the use of lead tellurite glass as a waste form for salt wastes from electrochemical reprocessing of used nuclear fuel. The efficacy of using lead tellurite glass to immobilize three different salt compositions was evaluated: a LiCl-Li2O oxide reduction salt containing fission products from oxide fuel, a LiCl-KCl eutectic salt containing fission products from metallic fuel, and SrCl2. Physical and chemical properties of glasses made with these salts were characterized with X-ray diffraction, bulk density measurements, differential thermal analysis, chemical durability tests, scanning and transmission electron microscopies, and energy-dispersive X-ray spectroscopy. These glasses were found to accommodate high salt concentrations and have high densities, but further development is needed to improve chemical durability. (C) 2017 Published by Elsevier B.V.

Method for increasing the lifetime of an extraction medium used for reprocessing spent nuclear fuel and/or breeder materials

International Nuclear Information System (INIS)

Schmieder, H.; Stieglitz, L.

1977-01-01

A method is provided for increasing the lifetime of an extraction medium containing an organophosphorus acid ester and a hydrocarbon and being used for reprocessing spent nuclear fuel and/or breeder materials. Impurities resulting from chemical and/or radiolytic decomposition and interfering compounds of such impurities with radionuclides are removed from the extraction medium by bringing the extraction medium, after use, into intimate contact with an aqueous hydrazine hydrate solution having a concentration of between 0.1 and 1.0 molar at a temperature between 20 to 75 0 C. The aqueous hydrazine hydrate solution is then separated from the extraction medium

Nickel based alloys for molten salt applications in pyrochemical reprocessing applications

International Nuclear Information System (INIS)

Ningshen, S.; Ravi Shankar, A.; Rao, Ch. Jagadeeswara; Mallika, C.; Kamachi Mudali, U.

2016-01-01

Pyrochemical reprocessing route is one of the best option for reprocessing of spent metallic nuclear fuel from future fast breeder in many countries, especially in the US (Integral fast reactor, IFR), Russia (Research Institute of Atomic Reactors, RIAR), Japan, Korea and India. This technology with intrinsic nuclear proliferation resistance is regarded as one of the most promising nuclear fuel cycle technologies of the next-generation. However, the selection of materials of construction for pyrochemical reprocessing plants is challenging because of the extreme environments, i.e., high radiation, corrosive molten salt (LiCl-KCl, LiCl-KCl-CsCl, KCl-NaCl-MgCl 2 , etc.), reactive molten metals, and high temperature. Efforts have been made to develop compatible materials for various unit operations like salt preparation, electrorefining, cathode processing and alloy casting in pyrochemical reprocessing. Nickel and its alloy are the candidate materials for salt purification exposed to molten LiCl-KCl under Cl 2 bubbling, in air or ultra high purity argon environment. In the present study, the corrosion behavior of candidate materials like Inconel 600, Inconel 625, Inconel 690 exposed to molten LiCl-KCl eutectic salt environment at 500 to 600 °C have been carried out. The surface morphology of the exposed samples and scales were examined by SEM/EDX and XRD. The weight loss results indicated that Inconel 600 and Inconel 690 offer better corrosion resistance compared to Inconel 625 in air and chlorine environment. Higher corrosion of Inconel 625 is attributed to development of Mo rich salt layers. However, Ni base alloys exhibited a decreasing trend of weight loss with increasing time of exposure and weight gain was observed under UHP Ar environment. The mechanism of corrosion of Ni base alloys appeared to be due to formation of Cr rich and Ni rich layers of Cr 2 O 3 , NiO and spinel oxides at the surface and subsequent spallation. Based on the present studies, Inconel 690

Prospect of spent fuel reprocessing and back-end cycling in China in 1990's

International Nuclear Information System (INIS)

Ke Youzhi; Wang Rengtao

1987-01-01

According to the CHinese Program of nuclear energy in 1990's, the amount of spent fuel by the year 2000 is estimated in this paper. Reprocessing is considered as an important link in the back-end fuel cycle. A pilot plant is scheduled for hot start up in 1996. The main goal of the study is LWR spent fuel reprocessing. We will use the experience gained from reprocessing of production reactor fuel and last research results. The advanced foreign technigue and experience will be introduced. The study emphasizes on the test of technology, equipments, instrumentation and automation, development of remote maintenance and decontamination. China will start to demonstrate the way for fuel cycle. (author)

Application of a room temperature ionic liquid for nuclear spent fuel reprocessing: speciation of trivalent europium and solvatation effects

International Nuclear Information System (INIS)

Moutiers, G.; Mekki, S.; Billard, I.

2007-01-01

One of the solutions proposed for the optimization of the long term storage and conditioning of spent nuclear fuel is to separate actinide and lanthanide both from each other and from other less radioactive metallic species. The industrial proposed processes, based on liquid liquid extraction steps, involve solvents with non negligible vapour pressure and may generate contaminated liquid wastes that will have to be reprocessed. During the last decade, some room-temperature ionic liquids have been studied and integrated into industrial processes. The interest on this class of solvent came out from their 'green' properties (non volatile, non flammable, recyclable, etc...), but also from the variability of their physico-chemical properties (stability, hydrophobicity, viscosity) as a function of the RTIL chemical composition. Indeed, it has been shown that classical chemical industrial processes could be transferred into those media, even more improved, while a certain number of difficulties arising from using traditional solvent can be avoided. In this respect, it could be promising to investigate the ability to use room temperature ionic liquid into the spent nuclear fuel reprocessing field. The aim of this this study is to test the ability of the specific ionic liquid bumimTf 2 N to allow trivalent europium extraction. The choice of this metal is based on the chemical analogy with trivalent minor actinides Curium and Americium which are contributing the greatest part of the long-lived high level radioactive wastes. Handling these elements needs to be very cautious for the safety and radioprotection aspect. Moreover, europium is a very sensitive luminescent probe to its environment even at the microscopic scale. The report is structured with four parts. In a first chapter, we present the main physico-chemical properties of an imidazolium-based ionic liquid family, and then we choose the ionic liquid bumimTf 2 N for the whole thesis and start with the electrochemical

Applying Bayesian decision theory to assess reprocessing economic and social cost-benefits

International Nuclear Information System (INIS)

Heising, C.D.

1978-01-01

Bayesian decision theory, combined with conventional systems analysis techniques into the discipline called decision analysis, has been applied in this work to assess economic and social cost-benefits associated with reprocessing nuclear fuel. Particular attention in this paper is given to the models which have been developed to place numerical estimates in dollar terms on the three categories of social risks that have been identified with reprocessing. These categories include: (1) health, environment, and safety, (2) diversion of fissile material, including sabotage, terrorist acts, and subnational diversion, and (3) nuclear proliferation, defined to be a diversion at the national level to obtain weapons capability. The emphasis is placed on the third category, as proliferation risk has not been treated elsewhere in a quantitative fashion; most arguments have in the main been qualitative conjectures put forth by political scientists

Environmental evaluation of reprocessing

International Nuclear Information System (INIS)

1979-01-01

This paper addresses two specific points. (a) The means by which it is established that reprocessing is carried out within the basic standards for radiological protection set by the ICRP. (b) A summary of the products, wastes and effluents of reprocessing together with the energy and water resources required. It is concluded that reprocessing of spent thermal reactor fuel can be undertaken whilst conforming to the basic standards set by ICRP. For domestic reasons of public acceptability some countries adopt very strict limits. Any attempt at comparisons between limits set by individual countries could lead to misunderstandings if account is not taken of these additional factors which may in turn influence the cost of reprocessing

State-of-the-art report on accident analysis and risk analysis of reprocessing plants in European countries

International Nuclear Information System (INIS)

Nomura, Yasushi

1985-12-01

This report summarizes informations obtained from America, England, France and FRG concerning methodology, computer code, fundamental data and calculational model on accident/risk analyses of spent fuel reprocessing plants. As a result, the followings are revealed. (1) The system analysis codes developed for reactor plants can be used for reprocessing plants with some code modification. (2) Calculational models and programs have been developed for accidental phenomenological analyses in FRG, but with insufficient data to prove them. (3) The release tree analysis codes developed in FRG are available to estimate radioactivity release amount/probability via off-gas/exhaustair lines in the case of accidents. (4) The computer codes developed in America for reactor-plant environmental transport/safety analyses of released radioactivity can be applied to reprocessing facilities. (author)

The determination of Pu-241 by liquid scintillation counting in gaseous effluents of an incineration facility, FERAB, and the Karlsruhe Nuclear Reprocessing Plant, WAK

International Nuclear Information System (INIS)

Godoy, J.M.; Schuettelkopf, H.

1983-03-01

Although the concentration of Pu-241 in nuclear fuel to be reprocessed is high, there are only few results published about the emission of Pu-241 with gaseous and liquid effluents. Nearly no information is available, too, about the environmental contamination of nuclear installations by Pu-241. Therefore a procedure was developed to measure Pu-241 by liquid scintillation counting. Sample preparation was performed by electroplating of plutonium on stainless steel planchets. To correct the selfabsorption the linear dependence of counting efficiency in the liquid scintillation counter and the resolution in the α-spectrometer was used. (orig./HP) [de

Mono- and di-n-butyl phosphates of some metals in spent nuclear fuel reprocessing

Energy Technology Data Exchange (ETDEWEB)

Solovkin, A.S.

1982-01-01

Results of investigations which have been carried out in the Soviet Union for the last 10 years on the determination of the composition, structure, conditions of the formation and solubility of mono- and di-n-butyl phosphates of metals (U/sup 6 +/, Pu/sup 4 +/, Pu/sup 3 +/, Th, Zr, Fe/sup 3 +/, Am, Al, rare-earth elements), which are important for the processes of irradiated nuclear fuel reprocessing, are presented. A conclusion is made that zirconium mono- and di-n-butyl phosphates are the least soluble in aqueous and organic solvents of all investigated compounds. FeA/sub 3/ and AmA/sub 3/ are weakly soluble in aqueous solutions. The other compounds are sufficiently soluble in moderately acidic aqueous solutions or in DBP and TBP with dilutents. The obtained results indicate at the similarity of zirconium and plutonium (4) chemical properties; thorium, in this respect, is not an analogue of plutonium (4). Possible structural formulas of the investigated compounds are considered.

Filter safety tests under solvent fire in a cell of nuclear-fuel reprocessing plant

International Nuclear Information System (INIS)

Nishio, Gunji

1988-01-01

In a nuclear-fuel reprocessing plant, a solvent fire in an extraction process is postulated. Since 1983, large scale solvent fire tests were carried out by Fire/Filter Facility to demonstrate solvent burning behavior in the cell, HEPA filter integrity by the fire and radioactive confinement by air-ventilation of the plant under postulated fire conditions. From results of 30 % TBP-70 % n-dodecane fire, burning rate of solvent in the cell, smoke generation rate and smoke deposition onto duct surface were obtained by a relation between air-ventilation rate into the cell and burning surface area of the solvent. The endurance of HEPA filter due to smoke plugging was measured by a pressure drop across the filter during the fire. The confinement of radioactive materials from the burning solvent was determined by the measurement of airborne concentrations in the cell for stable nuclei simulated fission products, radioactive tracers and uranium nitrate. (author)

Reprocessing: experience and future outlooks

International Nuclear Information System (INIS)

Rapin, M.

1981-01-01

It is shown that reprocessing is the best way to cope with irradiated fuels since it provides an optimized waste conditioning for long term storage, the possibility to recycle fissile material and the reduction of Pu diversion risk. The reprocessing constraints are discussed from political, technical, safety, public acceptance, and economical points of view. The French reprocessing programme (thermal reactor fuel fast breeder fuels) is presented together with a short review of the reprocessing experience and outlooks out of France [fr

Model of iodine transport and reaction kinetics in a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Davis, W. Jr.

1977-05-01

A model is presented to describe the time-dependent flow and retention of stable iodine isotopes and the decay of 131 I in a nuclear fuel reprocessing plant. The plant consists of 16 units of equipment such as a voloxidizer or graphite burner, fuel dissolver, solvent extractors, storage tanks, vaporizers, primary iodine sorbers, and silver zeolite. The rate of accumulation of bulk and radioactive iodine in these units and in the environment is described using 19 differential equations. Reasonable time-dependence of iodine retention factors (RFs) by the plant were calculated. RFs for a new plant in excess of 10 6 for stable iodine and 129 I decrease to the range of 10 3 to 10 2 as plant operating times exceed 50 to 100 days. The RFs for 131 I also decrease initially, for a period of approximately 10 days, but then increase by several orders of magnitude due to radioactive decay and isotopic exchange. Generally, the RFs for 131 I exceed those for stable iodine by factors of 10 4 or more. 19 references, 13 figures, 2 tables

Power Reactor Thoria Reprocessing Facility (PRTRF), Trombay

International Nuclear Information System (INIS)

Dhami, P.S; Yadav, J.S; Agarwal, K.

2017-01-01

Exploitation of the abundant thorium resources to meet sustained energy demand forms the basis of the Indian nuclear energy programme. To gain reprocessing experience in thorium fuel cycle, thoria was irradiated in research reactor CIRUS in early sixties. Later in eighties, thoria bundles were used for initial flux flattening in some of the pressurized heavy water reactors (PHWRs). The research reactor irradiated thoria contained small content (∼ 2-3ppm) of "2"3"2U in "2"3"3U product, which did not pose any significant radiological problems during processing in Uranium Thorium Separation Facility (UTSF), Trombay. Thoria irradiated in PHWRs on discharge contained (∼ 0.5-1.5% "2"3"3U with significant "2"3"2U content (100-500 ppm) requiring special radiological attention. Based on the experience from UTSF, a new facility viz. Power Reactor Thoria Reprocessing Facility (PRTRF), Trombay was built which was hot commissioned in the year 2015

Nuclear Analyses of Indian LLCB Test Blanket System in ITER

Science.gov (United States)

Swami, H. L.; Shaw, A. K.; Danani, C.; Chaudhuri, Paritosh

2017-04-01

Heading towards the Nuclear Fusion Reactor Program, India is developing Lead Lithium Ceramic Breeder (LLCB) tritium breeding blanket for its future fusion Reactor. A mock-up of the LLCB blanket is proposed to be tested in ITER equatorial port no.2, to ensure the overall performance of blanket in reactor relevant nuclear fusion environment. Nuclear analyses play an important role in LLCB Test Blanket System design & development. It is required for tritium breeding estimation, thermal-hydraulic design, coolants process design, radioactive waste management, equipment maintenance & replacement strategies and nuclear safety. The nuclear behaviour of LLCB test blanket module in ITER is predicated in terms of nuclear responses such as tritium production, nuclear heating, neutron fluxes and radiation damages. Radiation shielding capability of LLCB TBS inside and outside bio-shield was also assessed to fulfill ITER shielding requirements. In order to supports the rad-waste and safety assessment, nuclear activation analyses were carried out and radioactivity data were generated for LLCB TBS components. Nuclear analyses of LLCB TBS are performed using ITER recommended nuclear analyses codes (i.e. MCNP, EASY), nuclear cross section data libraries (i.e. FENDL 2.1, EAF) and neutronic model (ITER C-lite v.l). The paper describes a comprehensive nuclear performance of LLCB TBS in ITER.

Progress and experiences from the decommissioning of the eurochemic reprocessing plant

International Nuclear Information System (INIS)

Gillis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R.

2008-01-01

The Eurochemic reprocessing facility at Dessel in Belgium, was constructed from 1960 to 1966. After shutdown, the plant was decontaminated from 1975 to 1979 to keep safe standby conditions at reasonable cost. When it was decided in 1986 not to resume reprocessing in Belgium, the main Belgoprocess activities changed to processing and storage of radioactive waste and to decontamination and decommissioning of obsolete nuclear facilities. The industrial decommissioning was started in 1990. This document presents the project: overview of decommissioning activities and equipment used, automation in decontamination, ensuring health and safety during the operations, release of decontaminated materials, current situation of the decommissioning activities and quality assurance program. (A.L.B.)

Transport of nuclear materials: a major stake for the reprocessing-conditioning-recycling strategy

International Nuclear Information System (INIS)

Gautrot, J.J.

1998-01-01

As the international reference in terms of fuel cycle services, the COGEMA Group has developed a wide range of industrialized products answering to its clients needs. But, as deregulation and competition are now expanding, utilities has to be perfectly aware of the cost level of their strategic choices, and to keep these costs down. This point is especially valid in the back-end of the fuel cycle. Several leading nuclear countries around the world have chosen the reprocessing-recycling option because it ensures a economically mastered vision. In that respect, transportation reliability is consequently a basic requirement. It ensures a balanced and continuous flows of materials. Transportation system must be reliable in terms of schedule, safety or industrial aspects (i.e. dedicated packaging for road, rail, sea or air transports, maintenance aspects...). Any serious flaw in one of these three points could lead to delays, thus lessening the economic advantage for utilities. But, one must not loose sight that transportation of nuclear materials is tied to extra-technical issues, such as environmental or regulatory factors, which are fundamental for a consistent understanding of this business. The COGEMA Group, through its subsidiary Transnucleaire, possesses a dedicated transport system, widely praised for its constant commitment in terms of safety, quality and operating. This papers presents the overall back-end transportation framework and details the transport organisations as well as the main achievements of Transnucleaire when it comes to sea, road or rail back-end transports. (authors)

Reprocessing of nonoptimally exposed holograms

International Nuclear Information System (INIS)

Phipps, G.S.; Robertson, C.E.; Tamashiro, F.M.

1980-01-01

Two reprocessing techniques have been investigated that are capable of correcting the effects of nonoptimum optical density of photographic amplitude holograms recorded on Agfa-Gevaert type 10E75 plates. In some cases a reprocessed hologram will exhibit a diffraction efficiency even higher than that obtainable from a hologram exposed and processed to the optimum density. The SNR of the reprocessed holograms is much higher than that of the same holograms belached with cupric bromide. In some cases the SNR approaches the optimum value for a properly exposed amplitude hologram. Subjective image quality and resolution of reprocessed hologram reconstructins appear to be no different than for normal single-development holograms. Repeated reprocessing is feasible and in some cases desirable as a means of increasing diffraction efficiency

Safety assessment of UP3-A reprocessing plant

International Nuclear Information System (INIS)

Mercier, J.P.; Guezenec, J.Y.; Poirier, M.C.

1992-02-01

This presentation describes how the safety assessment was made of UP3-A plant of the La Hague establishment for the building permit and operating license within the context of French nuclear regulations and the national debate on the need for reprocessing. Other factors discussed are how the public was involved, how the regulations were improved in the process and what the different stages of commissioning consisted of. (author)

Decontamination and decommissioning of the West Valley Reprocessing Plant

International Nuclear Information System (INIS)

Daugherty, H.F.; Keel, R.

1986-11-01

This report presents the decontamination and decommissioning (D and D) activities at the West Valley Nuclear Fuel Reprocessing Plant through September 1, 1986. The topics addressed are: D and D of areas for reuse by the Liquid Waste Treatment System (LWTS); D and D of areas for reuse as High Level Waste (HLW) canister storage; and technologies developed in D and D work

Advanced fuel cycle on the basis of pyroelectrochemical process for irradiated fuel reprocessing and vibropacking technology

International Nuclear Information System (INIS)

Mayorshin, A.A.; Skiba, O.V.; Tsykanov, V.A.; Golovanov, V.N.; Bychkov, A.V.; Kisly, V.A.; Bobrov, D.A.

2000-01-01

For advanced nuclear fuel cycle in SSC RIAR there is developed the pyroelectrochemical process to reprocess irradiated fuel and produce granulated oxide fuel UO 2 , PuO 2 or (U,Pu)O 2 from chloride melts. The basic technological stage is the extraction of oxides as a crystal product with the methods either of the electrolysis (UO 2 and UO 2 -PuO 2 ) or of the precipitating crystalIization (PuO 2 ). After treating the granulated fuel is ready for direct use to manufacture vibropacking fuel pins. Electrochemical model for (U,Pu)O 2 coprecipitation is described. There are new processes being developed: electroprecipitation of mixed oxides - (U,Np)O 2 , (U,Pu,Np)O 2 , (U,Am)O 2 and (U,Pu,Am)O 2 . Pyroelectrochemical production of mixed actinide oxides is used both for reprocessing spent fuel and for producing actinide fuel. Both the efficiency of pyroelectrochemical methods application for reprocessing nuclear fuel and of vibropac technology for plutonium recovery are estimated. (author)

A novel waste form for disposal of spent-nuclear-fuel reprocessing waste: A vitrifiable cement

International Nuclear Information System (INIS)

Gougar, M.L.D.; Scheetz, B.E.; Siemer, D.D.

1999-01-01

A cement capable of being hot isostatically pressed into a glass ceramic has been proposed as the waste form for spent-nuclear-fuel reprocessing wastes at the Idaho National Engineering and Environmental Laboratory (INEEL). This intermediate cement, with a composition based on that of common glasses, has been designed and tested. The cement formulations included mixed INEEL wastes, blast furnace slag, reactive silica, and INEEL soil or vermiculite, which were activated with potassium or sodium hydroxide. Following autoclave processing, the cements were characterized. X-ray diffraction analysis revealed three notable crystalline phases: quartz, calcite, and fluorite. Results of compressive strength testing ranged from 1452 and 4163 psi, exceeding the US Nuclear Regulatory Commission (NRC)-suggested standard of >500 psi. From American National Standards Institute/American Nuclear Society 16.1-1986 leach testing, effective diffusivities for Cs were determined to be on the order of 10 -11 to 10 -10 cm 2 /s and for Sr were 10 -12 cm 2 /s, which are four orders of magnitude less than diffusivities in some other radwaste materials. Average leach indices (LI) were 9.6 and 11.9 for Cs and Sr, respectively, meeting the NRC Standard of LI > 6. The 28-day Materials Characterization Center-1 leach testing resulted in normalized elemental mass losses between 0.63 and 28 g/(m 2 ·day) for Cs and between 0.34 and 0.70 g/(m 2 ·day) industry-accepted standard while Cs losses indicate a process sensitive parameter

Stock management optimization. Example of the management of a reprocessed plutonium stock

International Nuclear Information System (INIS)

Herault, L.; Privault, C.

1997-01-01

This paper describes a method developed by the CEA for the management of a stock of nuclear materials of Electricite de France and which combines meta-heuristics with mathematical programing results for a better efficiency. The industrial problem to solve concerns the reprocessing of spent fuels and the reuse of their plutonium content for the manufacturing of mixed oxide (MOX) fuels. In this problem, the plutonium stock is shared into subsets which must supply fuel fabrication plants at a given date and with precise energetic, chemical and quality criteria in order to minimize the reprocessing costs. (J.S.)

Krypton separation from waste gas of a reprocessing plant by low temperature rectification

International Nuclear Information System (INIS)

1987-01-01

6 lectures at this seminar describe and evaluate the results of the research and development work on low temperature krypton separation from the waste gas of the reprocessing of nuclear fuels. They are used for making decisions for the process to be used in the future on a large scale at the Wackersdorf reprocessing plant. 2 further lectures deal with alternatives to this process, which were also developed: the freon washing and low temperature adsorption of krypton. All the lectures were included separately in the INIS and ENERGY databases. (RB) [de

Off-line NDA measurement of actinides in reprocessing solution using hybrid K-edge/K-XRF densitometer

International Nuclear Information System (INIS)

Bootharajan, M.; Swaminathan, K.; Venkata Subramani, C.R.; Kumar, R.

2015-01-01

A versatile, nondestructive assay (NDA) system of a hybrid K-edge/K-XRF facility adapted to a glove box facility has been developed at RCL, IGCAR for the analysis of U and Pu in process solutions obtained from the reprocessing of spent nuclear fuels. This paper describes i) The development of a hybrid K-edge/K-XRF facility adapted to a glove box system ii) The results obtained using conditioner solution of burn up 155 GWd/t with a dose of 20 R/h and iii) Comparison of the results with the parallel analyses of the same by Isotope dilution mass spectrometry. The hybrid K-edge cum K-XRF densitometer is ideally suited for dissolver solutions as well as U and Pu product solutions from reprocessing plant. This method can be useful in the analysis of mixed solution of Special Nuclear Materials (SNM) without chemical separation. To assay solutions with high radiation background, the hybrid K-edge/K-XRF system is designed and fabricated inside a glove box with adequate shielding from both source X-rays and the sample radiation. The theory and preliminary experiments are described elsewhere. Around 5 mL of the conditioner solution (burn up of 155 GWd/t with a dose of 20 R/h) was taken in a poly propylene vial placed concentrically in to another poly propylene vial. The concentration was estimated by K-edge densitometry with X-ray tube operated with 150 kV and 1 mA and counting period of 3000s. Background correction was obtained with the X-ray tube in OFF condition. The solution was analysed parallelly using isotopic dilution mass spectrometry

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-09-01

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.

Electrochemical Methods for Reprocessing Defective Fuel Elements and for Decontaminating Equipment

International Nuclear Information System (INIS)

Mikheykin, S. V.; Rybakov, K. A.; Simonov, V. P.

2002-01-01

Reprocessing of fuel elements receives much consideration in nuclear engineering. Chemical and electrochemical methods are used for the purpose. For difficultly soluble materials based on zirconium alloys chemical methods are not suitable. Chemical reprocessing of defective or irradiated fuel elements requires special methods for their decladding because the dissolution of the clad material in nitric acid is either impossible (stainless steel, Zr alloys) or quite slow (aluminium). Fuel elements are cut in air-tight glove-boxes equipped with a dust collector and a feeder for crushed material. Chemical treatment is not free from limitations. For this reason we started a study of the feasibility of electrochemical methods for reprocessing defective and irradiated fuel elements. A simplified electrochemical technology developed makes it possible to recover expensive materials which were earlier wasted or required multi-step treatment. The method and an electrochemical cell are suitable for essentially complete dissolution of any fuel elements, specifically those made of materials which are difficultly soluble by chemical methods

Status of development on simulation technology for pyrochemical reprocessing

International Nuclear Information System (INIS)

Arie, Kazuo; Mizuguchi, Koji; Fujita, Reiko

2004-01-01

Simulation techniques for the elemental behaviors in the pyrochemical reprocessing process of spent nuclear fuels are important for fuel reprocessing and future power station development. The authors developed a simulation code SPR1.0 which can analyze co-occurring electrochemical and chemical reactions simultaneously and which is applicable to know the behavior of any element in the system. The present report describes the status of the code development, the database for fundamental electrochemical reactions, and verification of the code. The code employs TRIAS code for electrochemical reactions and SOLGASMIX-PV for chemical reactions. Electrolytic process for MOX (mixed oxide) fuels with different Pu redox ratios were simulated using the present code and the effect of introducing iron ions was studied. The prospect of future development is also described. (S. Ohno)

The need to study of bounding accident in reprocessing plant

International Nuclear Information System (INIS)

Segawa, Satoshi; Fujita, Kunio

2013-01-01

There is a clear consensus that the severe accident corresponds to the core damage accident for power reactors. On the other hand, for FCFs, there is no clear consensus on what is the accident to assess the safety in the region of beyond design basis, or what is the accident which has very low probability but large consequence. The need to examine a bounding consequence of each type of accident is explained to advance the rationality of safety management and regulation and, as a result, to reinforce the safety of a reprocessing plant. The likelihood of occurrence of an accident causing a bounding consequence should correspond to that of a severe accident at a nuclear power plant. The bounding consequence will be derived using the deterministic method and sound engineering judgment supplemented by the probabilistic method. Once an agreement on such a concept is reached among regulators, operators and related experts it will help to provide a solid basis to ensure the safety of a reprocessing plant independent of that of a nuclear power plant. In this paper, we show a preliminary risk profile of RRP calculated by QSA (Quantitative Safety Assessment) which JNFL developed. The profile shows that bounding consequences of various accidents in a range of occurrence frequency corresponding to a severe accident at a nuclear power plant. And we find that the bounding consequence of high-level liquid waste boiling is the largest among all in this range. Therefore, the risk of this event is shown in this paper as an example. To build a common consensus about bounding accidents among concerned parties will encourage regulatory body to introduce such an idea for more effective regulation with scientific rationality. Additionally the study of bounding accidents can contribute to substantial development for accident management strategy as reprocessing operators. (authors)

Reprocessing in Europe

Energy Technology Data Exchange (ETDEWEB)

Rossney, G [United Reprocessors G.m.b.H., Karlsruhe (F.R. Germany)

1976-04-01

The status of reprocessing activities within the member organizations of United Reprocessors is reviewed. The U.K. government has approved overseas deals by BNFL which will help to pay for their planned plant of 1000 te U p.a. at Windscale. In Germany KEWA has selected a site at Aschenburg as a fuel cycle centre where they plan to build a utility financed reprocessing plant of 1500 te U p.a. France has formed a new fuel cycle corporation, Cogema, which hopes to participate in the large volume of Japanese business negotiated by BNFL. United Reprocessors have agreed to pool their technology which may be available to organisations wishing to construct reprocessing plants in their own countries.

Development of COMPAS, computer aided process flowsheet design and analysis system of nuclear fuel reprocessing

International Nuclear Information System (INIS)

Homma, Shunji; Sakamoto, Susumu; Takanashi, Mitsuhiro; Nammo, Akihiko; Satoh, Yoshihiro; Soejima, Takayuki; Koga, Jiro; Matsumoto, Shiro

1995-01-01

A computer aided process flowsheet design and analysis system, COMPAS has been developed in order to carry out the flowsheet calculation on the process flow diagram of nuclear fuel reprocessing. All of equipments, such as dissolver, mixer-settler, and so on, in the process flowsheet diagram are graphically visualized as icon on a bitmap display of UNIX workstation. Drawing of a flowsheet can be carried out easily by the mouse operation. Not only a published numerical simulation code but also a user's original one can be used on the COMPAS. Specifications of the equipment and the concentration of components in the stream displayed as tables can be edited by a computer user. Results of calculation can be also displayed graphically. Two examples show that the COMPAS is applicable to decide operating conditions of Purex process and to analyze extraction behavior in a mixer-settler extractor. (author)

Cleaning and extraction apparatus in a nuclear fuel reprocessing

International Nuclear Information System (INIS)

Nakamura, Yoshiaki.

1983-01-01

Purpose : To eliminate the requirement for the decomposition and cleaning of a centrifugal extractor upon re-processing of FBR type reactor fuels, by preventing solid fission products from depositing on a rotary body of the centrifugal extractor. Constitution : A cleaning and extraction apparatus comprising a combination of a centrifugal cleaner and a centrifugal extractor is used for shortening the contact time between the process liquid and the extraction solvent in FBR type reactor fuel re-processing, and variable parameters are adjusted so that the following equation can be satisfied for avoiding the deposition of solids onto the rotary body of the centrifugal extractor: lsub(e). (rsub(le) 2 + rsub(2r) 2 ) . Nsub(e) . Qsub(c)/ lsub(c) (rsub(lc) 2 + rsub(2c) 2 ) . Nsub(c) . Qsub(e) < 0.8 where Qsub(c) : flow rate to be processed in a centrifugal cleaner, lsub(c) : length of the rotary body, rsub(2c) : radius of a rotary body, rsub(le) : distance from the center to the liquid-extracting hole of the rotary body center to the liquid-extraction hole, Nsub(c) : number of revolution of the rotary body, Qsub(e) : amount of flowrate to be treated in the centrifugal extractor, lsub(e) : length of the rotary body, rsub(2e) : radius for the rotary body, rsub(le) : distance from the center of the rotary body to the liquid discharging aperture and Nsub(e) : number of rotation of the rotary body. (Ikeda, J.)

Features in the aspect of materials in reprocessing plants

International Nuclear Information System (INIS)

Tanaka, Toshikazu; Suzuki, Kazuhiro

1992-01-01

The process of the reprocessing plant installed in Rokkasho, Aomori Prefecture, by Japan Nuclear Fuel Service Co., Ltd. is the Purex wet process experienced in Japan and abroad, and which can obtain the uranium and plutonium products of high purity at high recovery rate. This process is to melt spent fuel with nitric acid, and extract and separate uranium, plutonium and fission products from the obtained solution by utilizing the difference in chemical properties. The yearly amount of treatment of the reprocessing plant of this company is 800 t uranium. In order to ensure the safety in the reprocessing plant that handles the solution with high radioactivity, the function of confining radioactive substances in definite areas is demanded. For the purpose, the machinery, equipment and piping containing radioactive substances are made of the materials having the corrosion resistance against nitric acid, and welded structure is adopted to prevent leakage. Negative pressure is maintained in waste gas treatment facilities in relation to cells, and in the cells in relation to the building. The outline of the facilities, the materials of the main machinery and equipment, and the applied technologies are reported. (K.I.)

Reprocessing in breeder fuel cycles

International Nuclear Information System (INIS)

Burch, W.D.; Groenier, W.S.

1982-01-01

Over the past decade, the United States has developed plans and carried out programs directed toward the demonstration of breeder fuel reprocessing in connection with the first breeder demonstration reactor. A renewed commitment to moving forward with the construction of the Clinch River Breeder Reactor (CRBR) has been made, with startup anticipated near the end of this decade. While plans for the CRBR and its associated fuel cycle are still being firmed up, the basic research and development programs required to carry out the demonstrations have continued. This paper updates the status of the reprocessing plans and programs. Policies call for breeder recycle to begin in the early to mid-1990's. Contents of this paper are: (1) evolving plans for breeder reprocessing (demonstration reprocessing plant, reprocessing head-end colocated at an existing facility); (2) relationship to LWR reprocessing; (3) integrated equipment test (IET) facility and related hardware development activities (mechanical considerations in shearing and dissolving, remote operations and maintenance demonstration phase of IET, integrated process demonstration phase of IET, separate component development activities); and (4) supporting process R and D

Outline of center for research and development in Rokkasho reprocessing plant site

International Nuclear Information System (INIS)

Araya, S.; Kanatsugu, K.; Shakutsui, M.

1998-01-01

Japan Nuclear Fuel Ltd.(JNFL) is now constructing a commercial nuclear fuel reprocessing plant at Rokkasho Mura, introducing French Technology on the main processes of it. In October 1995 prior to the reprocessing plant operation, JNFL established the CENTER FOR RESEARCH and DEVELOPMENT (Center for R and D) inside the plant site to perform various tests which are intended to improve the safety, availability and reliability of the reprocessing plant. The test facility of the center was constructed from 1991 to 1995, and now many tests have been being performed in the center. A full-scale mock-up of the Head end process components based on French Technology, which consist of a tilting crane, shearing machine, dissolver, hull rinser, end piece rinser and maintenance equipment, was moved into a new building from the Head End Demonstration Test facility in Kobe (reported in RECOD '91). Functional tests and system performance tests are carried out under cold conditions (non radioactive). As equipment and piping layout in the cell and working area layout outside of the cell are simulated to the reprocessing plant design, it is possible to test remote maintainability and repairability under the same condition as the reprocessing plant except radioactive condition. A full-scale mock-up of the Centrifugal clarifier based on French Technology, which can clarify the dissolution solution is operated to confirm clarification performance under various cold conditions and is tested for the maintainability and the repairability. A sampling bench imported from France is the same one planed to be operated in the reprocessing plant which samples for various analysis from each process. The sampling bench is tested to confirm operability, maintainability and reliability. Also the sampling piping and pneumatic piping are going to be install to the sampling bench for a system test of sampling system. Two types of MERC (Mobile Equipment Replacement Cask), which replace worn parts remotely

Coordinated safeguards for materials management in a fuel reprocessing plant. Volume I

International Nuclear Information System (INIS)

Hakkila, E.A.; Cobb, D.D.; Dayem, H.A.; Dietz, R.J.; Kern, E.A.; Schelonka, E.P.; Shipley, J.P.; Smith, D.B.; Augustson, R.H.; Barnes, J.W.

1977-09-01

A materials management system is described for safeguarding special nuclear materials in a fuel-reprocessing plant. Recently developed nondestructive-analysis techniques and process-monitoring devices are combined with conventional chemical analyses and process-control instrumentation for improved materials accounting data. Unit-process accounting based on dynamic material balances permits localization of diversion in time and space, and the application of advanced statistical methods supported by decision-analysis theory ensures optimum use of accounting information for detecting diversion. This coordinated safeguards system provides maximum effectiveness consistent with modest cost and minimum process interference. Modeling and simulation techniques are used to evaluate the sensitivity of the system to single and multiple thefts and to compare various safeguards options. The study identifies design criteria that would improve the safeguardability of future plants

Release of radioactive materials in simulation test of a postulated solvent fire in a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Nishio, G.; Hashimoto, K.

1989-01-01

This paper reports on small- and large-scale fire tests performed to examine the adequacy of a safety evaluation method for a solvent fire in the extraction process of a nuclear fuel reprocessing plant. The test objectives were to obtain information on the confinement of radioactive materials during a 30% tri-n-butyl phosphate-n-dodecane fire while air ventilation is operating in the cell. The rates of release of cesium, strontium, cerium, ruthenium, and uranium from a burning solvent were determined. The quantities of species released were obtained from the solvent burning rate, smoke generation rate, partition coefficients of species between solvent and water, and coefficients of species entrainment to atmosphere in cell

Remote repair and inspection technics in Tokai reprocessing plant

International Nuclear Information System (INIS)

Koyama, Kenji; Ishibashi, Yuzo; Otani, Yosikuni

1986-01-01

Tokai reprocessing plant of Power Reactor and Nuclear Fuel Development Corp. is the only factory in Japan which treats 0.7 t/day of the spent fuel from LWR power stations and recovers remaining uranium and newly produced plutonium. Since the reprocessing plant started the hot test in September, 1977, about eight years have elapsed, and 233 t of spent fuel was treated as of August, 1985. During this period, the development of various remote working techniques have been carried out to cope with the failure of equipment and to strengthen the preventive maintenance of equipment. In this report, the development of the techniques for the remote repair of leaking dissolving tanks and the development of the remote inspection system for confirming the soundness of equipment in cells are described. In nuclear facilities, from the viewpoint of the reduction of radiation exposure accompanying the works under high radiation, labor saving, the increase of capacity factor by shortening the period of repair works, the improvement of safety and reliability of the facilities by perfecting checkup and inspection and so on, it is strongly desired to put robots in practical use for maintenance and inspection. (Kako, I.)

Use of reprocessed uranium. Proceedings of a technical committee meeting held in Vienna, August 2007

International Nuclear Information System (INIS)

2009-11-01

Reprocessed uranium (RepU), the uranium recovered from nuclear processing, is produced by several Member States in their facilities or through commercial contracts. From a sustainable development perspective, recycling of this uranium has become an attractive option for improving the efficiency of natural resource management and reducing radioactive waste accumulation. This publication demonstrates that reprocessing of spent fuel could form a key part of advanced fuel methodologies and describes various reuse options of RepU. In particular, it includes detailed review papers on management, storage, packaging and transport of RepU, reprocessing, utility experience and potential use of RepU. The importance of market aspects, economics and long term perspectives is also addressed

CAD system applications to the nuclear fuel reprocessing facilities

International Nuclear Information System (INIS)

Morita, Eiji; Matsumoto, Tadakuni; Shikakura, Sakae; Furuya, Kousei; Sakurai, Shin-ichi.

1994-01-01

Effective supporting techniques of design, operation, and maintenance of the reprocessing facility have been developed using the Intergraph CAD system. Two and three dimensional views of the process cells were utilized to rationalize the equipment layout and material handling flows, and to check the piping interference. Interferences of the remote maintenance equipment with the process equipments were also evaluated by the pictures on the CAD display. The newest virtual reality technology will help our future development of the more natural simulation for the remote maintenance operator training. (author)

Corrosion resistance of Ultra-Low-Carbon 19% Cr-11% Ni stainless steel for nuclear fuel reprocessing plants in nitric acid

International Nuclear Information System (INIS)

Ariga, Tamako; Takagi, Yoshio; Inazumi, Toru; Masamura, Katsumi; Sukekawa, M.

1995-01-01

An Ultra-Low-Carbon 19% Cr-11% Ni Stainless Steels used in nuclear fuel reprocessing plants where highly corrosion resistance in nitric acid is required has been developed. This steel has optimized the chemistry composition to decrease inclusions and deformation-induced martensitic transformation. The formation of deformation-induced martensite has the potential danger of accelerating corrosion in nitric acid. In this paper, effects of cold reduction and martensitic transformation on corrosion resistance of Ultra-Low-Carbon Stainless Steels in nitric acid are discussed. The developed steel showed excellent corrosion resistance during long-term exposure to nitric acid. (author)

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

International Nuclear Information System (INIS)

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

1984-08-01

A health risk assessment was conducted to investigate the impact of implementing regulations from the Environmental Protection Agency's Final Environmental Statement - 40 CFR 190 - Environmental Protection Requirements for Normal Operation of Activities in the Uranium Fuel Cycle. Potential risks involved in the routine release of 85 Kr from nuclear fuel reprocessing operations to the environment were compared to those resulting from the capture and storage of 85 Kr. The average occupationally exposed worker was estimated to receive about 400 to 600 mrem/y from 85 Kr recovery and immobilization activities. This dose is a factor of 20,000 to 30,000 higher than the estimated dose to the maximum offsite individual (0.02 mrem/y), and a factor of 130,000 to 200,000 higher than the dose received by the average member of the 50-mile population (0.003 mrem/y) from routine release of all 85 Kr. Given the uncertainties in the models used to generate lifetime risk numbers (0.02-0.027 radiation induced fatal cancers expected in the occupational workforce and 0.017 fatal cancers in the general population), the differences in total risks cannot be considered meaningful. There is certainly no reason to conclude that risks from 85 Kr routinely released to the environment are greater than those that would result from recovery, immobilization and storage of the noble gas. 22 references, 1 figure, 3 tables

Standard model for safety analysis report of fuel reprocessing plants

International Nuclear Information System (INIS)

1979-12-01

A standard model for a safety analysis report of fuel reprocessing plants is established. This model shows the presentation format, the origin, and the details of the minimal information required by CNEN (Comissao Nacional de Energia Nuclear) aiming to evaluate the requests of construction permits and operation licenses made according to the legislation in force. (E.G.) [pt

R and D of On-line Reprocessing Technology for Molten-Salt Reactor Systems

International Nuclear Information System (INIS)

Uhlir, Jan; Tulackova, Radka; Chuchvalcova Bimova, Karolina

2006-01-01

The Molten Salt Reactor (MSR) represents one of promising future nuclear reactor concept included in the Generation IV reactors family. The reactor can be operated as the thorium breeder or as the actinide transmuter. However, the future deployment of Molten-Salt Reactors will be significantly dependent on the successful mastering of advanced reprocessing technologies dedicated to their fuel cycle. Here the on-line reprocessing technology connected with the fuel circuit of MSR is of special importance because the reactor cannot be operated for a long run without the fuel salt clean-up. Generally, main MSR reprocessing technologies are pyrochemical, majority of them are fluoride technologies. The proposed flow-sheets of MSR on-line reprocessing are based on a combination of molten-salt / liquid metal extraction and electro-separation processes, which can be added to the gas extraction process already verified during the MSRE project in ORNL. The crucial separation method proposed for partitioning of actinides from fission products is based on successive Anodic dissolution and Cathodic deposition processes in molten fluoride media. (authors)

Conceptual design study on advanced aqueous reprocessing system for fast reactor fuel cycle

International Nuclear Information System (INIS)

Takata, Takeshi; Koma, Yoshikazu; Sato, Koji; Kamiya, Masayoshi; Shibata, Atsuhiro; Nomura, Kazunori; Ogino, Hideki; Koyama, Tomozo; Aose, Shin-ichi

2003-01-01

As a feasibility study on commercialized fast reactor cycle system, a conceptual design study is being progressed for the aqueous and pyrochemical processes from the viewpoint of economical competitiveness, efficient utilization of resources, decreasing environmental impact and proliferation resistance in Japan Nuclear Cycle Development Institute (JNC). In order to meet above-mentioned requirements, the survey on a range of reprocessing technologies and the evaluation of conceptual plant designs against targets for the future fast reactor cycle system have been implemented as the fist phase of the feasibility study. For an aqueous reprocessing process, modification of the conventional PUREX process (a solvent extraction process with purification of U/Pu, with nor recovery of minor actinides (MA)) and investigation of alternatives for the PUREX process has been carried out and design study of advanced aqueous reprocessing system and its alternatives has been conducted. The conceptual design of the advanced aqueous reprocessing system has been updated and evaluated by the latest R and D results of the key technologies such as crystallization, single-cycle extraction, centrifugal contactors, recovery of Am/Cm and waste processing. In this paper, the outline of the design study and the current status of development for advanced aqueous reprocessing system, NEXT process, are mentioned. (author)

Pyroelectrochemical process for reprocessing irradiated nuclear fuels

International Nuclear Information System (INIS)

Brambilla, G.; Sartorelli, A.

1982-01-01

A pyroelectrochemical process for reprocessing irradiated fast reactor mixed oxide or carbide fuels is described. The fuel is dissolved in a bath of molten alkali metal sulfates. The Pu(SO 4 ) 2 formed in the bath is thermally decomposed, leaving crystalline PuO 2 on the bottom of the reaction vessel. Electrodes are then introduced into the bath, and UO 2 is deposited on the cathode. Alternatively, both UO 2 and PuO 2 may be electrodeposited. The molten salts, after decontamination by precipitating the fission products dissolved in the bath by introducing basic agents such as oxides, carbonates, or hydroxides, may be recycled. Since it is not possible to remove cesium from the molten salt bath, periodic disposal and partial renewal with fresh salts is necessary. The melted salts that contain the fission products are conditioned for disposal by embedding them in a metallic matrix

The law for the regulations of nuclear source materials, nuclear fuel materials and reactors

International Nuclear Information System (INIS)

1977-01-01

Concerning refining, fabrication and reprocessing operations of such materials as well as the installation and operation of reactors, necessary regulations are carried out. Namely, in case of establishing the business of refining, fabricating and reprocessing nuclear materials as well as installing nuclear reactors, applications for the permission of the Prime Minister and the Minister of International Trade and Industry should be filed. Change of such operations should be permitted after filing applications. These permissions are retractable. As regards the reactors installed aboard foreign ships, it must be reported to enter Japanese waters and the permission by the Prime Minister must be obtained. In case of nuclear fuel fabricators, a chief technician of nuclear fuel materials (qualified) must be appointed per each fabricator. In case of installing nuclear reactors, the design and methods of construction should be permitted by the Prime Minister. The standard for such permission is specified, and a chief engineer for operating reactors (qualified) must be appointed. Successors inherit the positions of ones who have operated nuclear material refining, fabrication and reprocessing businesses or operated nuclear reactors. (Rikitake, Y.)

China's spent nuclear fuel management: Current practices and future strategies

International Nuclear Information System (INIS)

Zhou Yun

2011-01-01

Although China's nuclear power industry is relatively young and the management of its spent nuclear fuel is not yet a concern, China's commitment to nuclear energy and its rapid pace of development require detailed analyses of its future spent fuel management policies. The purpose of this study is to provide an overview of China's fuel cycle program and its reprocessing policy, and to suggest strategies for managing its future fuel cycle program. The study is broken into four sections. The first reviews China's current nuclear fuel cycle program and facilities. The second discusses China's current spent fuel management methods and the storage capability of China's 13 operational nuclear power plants. The third estimates China's total accumulated spent fuel, its required spent fuel storage from present day until 2035, when China expects its first commercialized fast neutron reactors to be operational, and its likely demand for uranium resources. The fourth examines several spent fuel management scenarios for the present period up until 2035; the financial cost and proliferation risk of each scenario is evaluated. The study concludes that China can and should maintain a reprocessing operation to meet its R and D activities before its fast reactor program is further developed. - Highlights: → This study provides an overview of China's fuel cycle program and its reprocessing policy.→ This study suggests strategies for managing its future fuel cycle program.→ China will experience no pressure to lessen the burden of spent fuel storage in the next 30 years.→ China should maintain sufficient reprocessing operations to meet its demands for R and D activities.→ China should actively invest on R and D activities of both fuel cycling and fast reactor programs.

Process Description and Operating History for the CPP-601/-640/-627 Fuel Reprocessing Complex at the Idaho National Engineering and Environmental Laboratory

International Nuclear Information System (INIS)

Wagner, E.P.

1999-01-01

The Fuel Reprocessing Complex (FRC) at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory was used for reprocessing spent nuclear fuel from the early 1950's until 1992. The reprocessing facilities are now scheduled to be deactivated. As part of the deactivation process, three Resource Conservation and Recovery Act (RCRA) interim status units located in the complex must be closed. This document gathers the historical information necessary to provide a rational basis for the preparation of a comprehensive closure plan. Included are descriptions of process operations and the operating history of the FRC. A set of detailed tables record the service history and present status of the process vessels and transfer lines

Radioactive waste management in a fuel reprocessing facility in fiscal 1982

International Nuclear Information System (INIS)

1984-01-01

In the fuel reprocessing facility of the Power Reactor and Nuclear Fuel Development Corporation, radioactive gaseous and liquid waste are released not exceeding the respective permissible levels. Radioactive concentrated solutions are stored at the site. Radioactive solid waste are stored appropriately at the site. In fiscal 1982, the released quantities of radioactive gaseous and liquid waste were both below the permissible levels. The results of radioactive waste management in the fuel reprocessing facility in fiscal 1982 are given in the tables: the released quantities of radioactive gaseous and liquid waste, the produced quantities of radioactive solid waste, and the stored quantities of radioactive concentrated solutions and of radioactive solid waste as of the end of fiscal 1982. (Mori, K.)

Incineration of dry burnable waste from reprocessing plants with the Juelich incineration process

International Nuclear Information System (INIS)

Dietrich, H.; Gomoll, H.; Lins, H.

1987-01-01

The Juelich incineration process is a two stage controlled air incineration process which has been developed for efficient volume reduction of dry burnable waste of various kinds arising at nuclear facilities. It has also been applied to non nuclear industrial and hospital waste incineration and has recently been selected for the new German Fuel Reprocessing Plant under construction in Wackersdorf, Bavaria, in a modified design

Cost Savings of Nuclear Power with Total Fuel Reprocessing

International Nuclear Information System (INIS)

Solbrig, Charles W.; Benedict, Robert W.

2006-01-01

The cost of fast reactor (FR) generated electricity with pyro-processing is estimated in this article. It compares favorably with other forms of energy and is shown to be less than that produced by light water reactors (LWR's). FR's use all the energy in natural uranium whereas LWR's utilize only 0.7% of it. Because of high radioactivity, pyro-processing is not open to weapon material diversion. This technology is ready now. Nuclear power has the same advantage as coal power in that it is not dependent upon a scarce foreign fuel and has the significant additional advantage of not contributing to global warming or air pollution. A jump start on new nuclear plants could rapidly allow electric furnaces to replace home heating oil furnaces and utilize high capacity batteries for hybrid automobiles: both would reduce US reliance on oil. If these were fast reactors fueled by reprocessed fuel, the spent fuel storage problem could also be solved. Costs are derived from assumptions on the LWR's and FR's five cost components: 1) Capital costs: LWR plants cost $106/MWe. FR's cost 25% more. Forty year amortization is used. 2) The annual O and M costs for both plants are 9% of the Capital Costs. 3) LWR fuel costs about 0.0035 $/kWh. Producing FR fuel from spent fuel by pyro-processing must be done in highly shielded hot cells which is costly. However, the five foot thick concrete walls have the advantage of prohibiting diversion. LWR spent fuel must be used as feedstock for the FR initial core load and first two reloads so this FR fuel costs more than LWR fuel. FR fuel costs much less for subsequent core reloads ( 6 /MWe. The annual cost for a 40 year licensed plant would be 2.5 % of this or less if interest is taken into account. All plants will eventually have to replace those components which become radiation damaged. FR's should be designed to replace parts rather than decommission. The LWR costs are estimated to be 2.65 cents/kWh. FR costs are 2.99 cents/kWh for the first

Overview of reductants utilized in nuclear fuel reprocessing/recycling

Energy Technology Data Exchange (ETDEWEB)

Patricia Paviet-Hartmann; Catherine Riddle; Keri Campbell; Edward Mausolf

2013-10-01

promises as a replacement for AHA. FHA undergoes hydrolysis to formic acid which is volatile, thus allowing the recycling of nitric acid. Unfortunately, FHA powder was not stable in the experiments we ran in our laboratory. In addition, AHA and FHA also decompose to hydroxylamine which may undergo an autocatalytic reaction. Other reductants are available and could be extremely useful for actinides separation. The review presents the current plutonium reductants used in used nuclear fuel reprocessing and will introduce innovative and novel reductants that could become reducers for future research on UNF separation.

Advance purex process for the new reprocessing plants in France and in Japan

International Nuclear Information System (INIS)

Viala, M.

1991-01-01

In the early Eighties, Japanese utilities formed the Japan Nuclear Fuel Service Co (JNFS), which is in charge of the construction and the operation of the first commercial reprocessing plant in Japan to be erected in Rokkasho Village, Aomori Prefecture. Following a thorough worldwide examination of available processes and technologies, JNFS selected the French technology developed for UP3 and UP2 800 for the plants' main facilities. For these three new plants, the 40-year old PUREX process which is used worldwide for spent fuel reprocessing, has been significantly improved. This paper describes some of the innovative features of the selected processes

Dose evaluation model for radionuclides released from the spent nuclear fuel reprocessing plant in Rokkasho

International Nuclear Information System (INIS)

Hisamatsu, Shun'ichi; Iyogi, Takashi; Inaba, Jiro; Chiang, Jing-Hsien; Suwa, Hiroji; Koide, Mitsuo

2007-01-01

A dose evaluation model was developed for radionuclides released from the spent nuclear fuel reprocessing plant which is located in Rokkasho, Aomori Prefecture, and now undergoing test operation. The dose evaluation model suitable for medium- and long-term dose assessments for both prolonged and short-term releases of radionuclides to the atmosphere was developed on the PC. The ARAC-2, a particle tracing type dispersion model coupled with 3-D wind field calculation by a mass conservative model, was adopted as the atmospheric dispersion model. The terrestrial transfer model included movement in soil and groundwater as well as an agricultural and livestock farming system. The available site-specific social and environmental characteristics were incorporated in the model. Growing of the crops was also introduced and radionuclides absorbed were calculated from weight increase from the start of deposition to harvest, and transfer factors. Most of the computer code system of the models was completed by 2005, and this paper reports the results of the development. (author)

Economical and industrial impact of nuclear power stations construction in Belgium

International Nuclear Information System (INIS)

Labrique, J.; Klees, P.

1981-01-01

After a brief introduction the paper analyses the employment in the Belgian nuclear sector with regard to construction, the operation, the engineering of nuclear power plants as well as fuel reprocessing. In the economical section a comparison of the kWh cost of different sources is presented as well as the seasibility of this cost to the raw material price. The future installation of nuclear power plants is discussed and the impact of its delay on the Belgian economy by an absence of decision is analyzed. (AF)

Nuclear power generation and nuclear nonproliferation

International Nuclear Information System (INIS)

Walske, C.

1978-01-01

In the future outlook around year 2000 of nuclear power, thought must be given to fuel reprocessing and plutonium utilization. The adverse utilization of plutonium may be prevented by the means balanced with its economical value. As the method of less cost with lower effect of nonproliferation, combination of fuel reprocessing and fuel fabrication facilities and mixed plutonium/uranium processing are possible. As the method of more cost with higher effect of nonproliferation the maintenance of high radioactivity and inaccessibility of plutonium is conceivable. As for the agreeable methods in 2000, seven principles may be mentioned, such as the dependence upon the agreements among major nations and upon nuclear exporting countries. These are still inadequate, however. What is important is to provide with the sufficient safeguards to countries concerned to negate the need for nuclear weapons. Efforts are then necessary for leading nuclear countries to extend aids to other nuclear-oriented countries. (Mori, K.)

Review of NRC Commission Papers on Regulatory Basis for Licensing and Regulating Reprocessing Facilities

Energy Technology Data Exchange (ETDEWEB)

Park, Jae Yeong; Shin, Hyeong Ki [KINS, Daejeon (Korea, Republic of)

2016-05-15

Spent nuclear fuel (SNF) accumulated in nuclear power plant has been a serious issue in most countries with operating nuclear power plants. Direct disposal of SNF could be a solution of the problem but many countries including the Republic of Korea have had a hard time selecting a site for high level waste repository because of low public acceptance. SNF recycling technologies consisting of reprocessing and transmutation have been developed so as to reduce the final volume of the disposed radioactive waste and to diminish the radiotoxicity of the waste. The Republic of Korea is now developing pyroprocessing and sodium-cooled fast reactor (SFR) technology to be used for the recycling of the wastes. KAERI has a plan to construct a pyroprocessing facility with a capacity of 30 tHM/y and a facility manufacturing TRU fuel for SFR by 2025. However, to license these facility and secure the safety, the current regulatory system related to SNF treatment needs to be improved and amended since the system has been developed focusing on facilities to examine irradiated nuclear materials. Status of reprocessing facility regulations developed by U.S.NRC was reviewed based on SECY papers. U.S.NRC has approved the development of a new rule referred to nationally as '10CFR Part 7x'. Existing 10CFR 50 and 70 has been evolved mainly for nuclear power plants and fuel cycle facilities whose radiological hazard is much lower than reprocessing plants respectively. U.S.NRC also derived many regulatory gaps including safety assessment methods, technical specification, general design criteria and waste classification and continue to develop the regulatory framework limited in scope to the resolution of Gap 5.

Stabilization of neptunium valence states in nitric media for spent nuclear fuel reprocessing

International Nuclear Information System (INIS)

Feldhaus, P.

1996-12-01

A possibility of standarizing the extraction-behavior of Neptunium during the reprocessing of spent nuclear fuel corresponding to PUREX-Process was investigated. The aim of the work was a qualitative dirigation of the Transuraniumelement (TRUE) into the raffinat of the first extraction cycle by a complete redoxconversion of the Neptunium valence states to unextractable Np(V). In the beginning the theoretical and experimental research focussed on the redoxchemistry of the actinide during the fuel dissolution and the feed preparation. Thereby the nitrous acid, which is produced by a radiological, photochemical and reductive degradation of the nitric acid, revealed an ambivalent influence on the Neptunium valences. By a short-term increase in HNO 2 -concentration the Np(V)-fraction could be obviously risen. The use of some stabilizing reagents inhibited a later reoxidation to Np(VI) also catalyzed by nitrous acid. The urea used for this purpose also led to a further increase in the obtained conversion rates due to a Np(VI)-reduction. The analysis of the valence distribution was performed by an extraction method. This had been compared to chromatographic separation in some preliminary investigations and had turned out to be comparably reliable and easily manageable. (orig.) [de

Extending Spent Fuel Storage until Transport for Reprocessing or Disposal

Energy Technology Data Exchange (ETDEWEB)

Carlsen, Brett; Chiguer, Mustapha; Grahn, Per; Sampson, Michele; Wolff, Dietmar; Bevilaqua, Arturo; Wasinger, Karl; Saegusa, Toshiari; Seelev, Igor

2016-09-01

Spent fuel (SF) must be stored until an end point such as reprocessing or geologic disposal is imple-mented. Selection and implementation of an end point for SF depends upon future funding, legisla-tion, licensing and other factors that cannot be predicted with certainty. Past presumptions related to the availability of an end point have often been wrong and resulted in missed opportunities for properly informing spent fuel management policies and strategies. For example, dry cask storage systems were originally conceived to free up needed space in reactor spent fuel pools and also to provide SFS of up to 20 years until reprocessing and/or deep geological disposal became available. Hundreds of dry cask storage systems are now employed throughout the world and will be relied upon well beyond the originally envisioned design life. Given present and projected rates for the use of nuclear power coupled with projections for SF repro-cessing and disposal capacities, one concludes that SF storage will be prolonged, potentially for several decades. The US Nuclear Regulatory Commission has recently considered 300 years of storage to be appropriate for the characterization and prediction of ageing effects and ageing management issues associated with extending SF storage and subsequent transport. This paper encourages addressing the uncertainty associated with the duration of SF storage by de-sign – rather than by default. It suggests ways that this uncertainty may be considered in design, li-censing, policy, and strategy decisions and proposes a framework for safely extending spent fuel storage until SF can be transported for reprocessing or disposal – regardless of how long that may be. The paper however is not intended to either encourage or facilitate needlessly extending spent fuel storage durations. Its intent is to ensure a design and safety basis with sufficient margin to accommodate the full range of potential future scenarios. Although the focus is primarily on

Review of Design Data for Safety Assessment of Tokai Reprocessing Plant. Control of hydrogen gas produced by radiolysis of reprocessing solutions at Tokai Reprocessing Plant

International Nuclear Information System (INIS)

Omori, E.; Surugaya, N.; Takaya, A.; Nakamura, H.; Maki, A.; Yamanouchi, T.

1999-10-01

Radioactive materials in aqueous solution at a nuclear fuel reprocessing plant causes radiolytic generation of several gases including hydrogen. Hydrogen accumulating in equipment can be an explosion hazard. In such plants, though the consideration in the design has been fundamentally made in order to remove the ignition source from the equipment, the hydrogen concentration in the equipment should not exceed the explosion threshold. It is, therefore, desired to keep the hydrogen concentration lower than the explosion threshold by dilution with the air introduced into equipment, from the viewpoint which previously prevents the explosion. This report describes the calculation of hydrogen generation, evaluation of hydrogen concentration under abnormal operation and consideration of possible improvement at Tokai Reprocessing Plant. The amount of hydrogen generation was calculated for each equipment from available data on radiolysis induced by radioactive materials. Taking into consideration for abnormal condition that is single failure of air supply and loss of power supply, the investigation was made on the method for controlling so that the hydrogen concentration may not exceed the explosion threshold. Possible means which can control the concentration of hydrogen gas under the explosion threshold have been also investigated. As the result, it was found that hydrogen concentration of most equipment was kept under the explosion threshold. It was also shown that improvement of the facility was necessary on the equipment in which the concentration of the hydrogen may exceed the explosion threshold. Proposals based on the above results are also given in this report. The above content has been described in 'Examination of the hydrogen produced by the radiolysis' which is a part of 'Reviews of Design Data for Safety Assessment of Tokai Reprocessing Plant' (JNC TN8410 99-002) published in February 1999. This report incorporates the detail evaluation so that operation

Reprocessing of MTR fuel at Dounreay

International Nuclear Information System (INIS)

Hough, N.

1997-01-01

UKAEA at Dounreay has been reprocessing MTR fuel for over 30 years. During that time considerable experience has been gained in the reprocessing of traditional HEU alloy fuel and more recently with dispersed fuel. Latterly a reprocessing route for silicide fuel has been demonstrated. Reprocessing of the fuel results in a recycled uranium product of either high or low enrichment and a liquid waste stream which is suitable for conditioning in a stable form for disposal. A plant to provide this conditioning, the Dounreay Cementation Plant is currently undergoing active commissioning. This paper details the plant at Dounreay involved in the reprocessing of MTR fuel and the treatment and conditioning of the liquid stream. (author)

Status of the nuclear measurement stations for the process control of spent fuel reprocessing at AREVA NC/La Hague

Energy Technology Data Exchange (ETDEWEB)

Eleon, Cyrille; Passard, Christian; Hupont, Nicolas; Estre, Nicolas [CEA, DEN, Cadarache, Nuclear Measurement Laboratory, F-13108 St Paul-lez-Durance (France); Battel, Benjamin; Doumerc, Philippe; Dupuy, Thierry; Batifol, Marc [AREVA NC, La Hague plant - Nuclear Measurement Team, F-50444 Beaumont-Hague (France); Grassi, Gabriele [AREVA NC, 1 place Jean-Millier, 92084 Paris-La-Defense cedex (France)

2015-07-01

Nuclear measurements are used at AREVA NC/La Hague for the monitoring of spent fuel reprocessing. The process control is based on gamma-ray spectroscopy, passive neutron counting and active neutron interrogation, and gamma transmission measurements. The main objectives are criticality and safety, online process monitoring, and the determination of the residual fissile mass and activities in the metallic waste remained after fuel shearing and dissolution (empty hulls, grids, end pieces), which are put in radioactive waste drums before compaction. The whole monitoring system is composed of eight measurement stations which will be described in this paper. The main measurement stations no. 1, 3 and 7 are needed for criticality control. Before fuel element shearing for dissolution, station no. 1 allows determining the burn-up of the irradiated fuel by gamma-ray spectroscopy with HP Ge (high purity germanium) detectors. The burn-up is correlated to the {sup 137}Cs and {sup 134}Cs gamma emission rates. The fuel maximal mass which can be loaded in one bucket of the dissolver is estimated from the lowest burn-up fraction of the fuel element. Station no. 3 is dedicated to the control of the correct fuel dissolution, which is performed with a {sup 137}Cs gamma ray measurement with a HP Ge detector. Station no. 7 allows estimating the residual fissile mass in the drums filled with the metallic residues, especially in the hulls, from passive neutron counting (spontaneous fission and alpha-n reactions) and active interrogation (fission prompt neutrons induced by a pulsed neutron generator) with proportional {sup 3}He detectors. The measurement stations have been validated for the reprocessing of Uranium Oxide (UOX) fuels with a burn-up rate up to 60 GWd/t. This paper presents a brief overview of the current status of the nuclear measurement stations. (authors)

Status of the nuclear measurement stations for the process control of spent fuel reprocessing at AREVA NC/La Hague

International Nuclear Information System (INIS)

Eleon, Cyrille; Passard, Christian; Hupont, Nicolas; Estre, Nicolas; Battel, Benjamin; Doumerc, Philippe; Dupuy, Thierry; Batifol, Marc; Grassi, Gabriele

2015-01-01

Nuclear measurements are used at AREVA NC/La Hague for the monitoring of spent fuel reprocessing. The process control is based on gamma-ray spectroscopy, passive neutron counting and active neutron interrogation, and gamma transmission measurements. The main objectives are criticality and safety, online process monitoring, and the determination of the residual fissile mass and activities in the metallic waste remained after fuel shearing and dissolution (empty hulls, grids, end pieces), which are put in radioactive waste drums before compaction. The whole monitoring system is composed of eight measurement stations which will be described in this paper. The main measurement stations no. 1, 3 and 7 are needed for criticality control. Before fuel element shearing for dissolution, station no. 1 allows determining the burn-up of the irradiated fuel by gamma-ray spectroscopy with HP Ge (high purity germanium) detectors. The burn-up is correlated to the 137 Cs and 134 Cs gamma emission rates. The fuel maximal mass which can be loaded in one bucket of the dissolver is estimated from the lowest burn-up fraction of the fuel element. Station no. 3 is dedicated to the control of the correct fuel dissolution, which is performed with a 137 Cs gamma ray measurement with a HP Ge detector. Station no. 7 allows estimating the residual fissile mass in the drums filled with the metallic residues, especially in the hulls, from passive neutron counting (spontaneous fission and alpha-n reactions) and active interrogation (fission prompt neutrons induced by a pulsed neutron generator) with proportional 3 He detectors. The measurement stations have been validated for the reprocessing of Uranium Oxide (UOX) fuels with a burn-up rate up to 60 GWd/t. This paper presents a brief overview of the current status of the nuclear measurement stations. (authors)

The threat of nuclear terrorism: from analysis to caution measures

International Nuclear Information System (INIS)

Schneider, M.

2001-12-01

In this work are analysed the different cases of terrorism attacks, the potential sources of risks, such reprocessing plants, nuclear power plants, every facility where is stored radioactive material. The vulnerability of these facilities is also evoked. Some solutions are recommended but more specially, further thought needs to be given to that kind of problems. (N.C.)

Fuel reprocessing data validation using the isotope correlation technique

International Nuclear Information System (INIS)

Persiani, P.J.; Bucher, R.G.; Pond, R.B.; Cornella, R.J.

1990-01-01

The Isotope Correlation Technique (ICT), in conjunction with the gravimetric (Pu/U ratio) method for mass determination, provides an independent verification of the input accountancy at the dissolver or accountancy stage of the reprocessing plant. The Isotope Correlation Technique has been applied to many classes of domestic and international reactor systems (light-water, heavy-water, and graphite reactors) operating in a variety of modes (power, research, and production reactors), and for a variety of reprocessing fuel cycle management strategies. Analysis of reprocessing operations data based on isotopic correlations derived for assemblies in a PWR environment and fuel management scheme, yielded differences between the measurement-derived and ICT-derived plutonium mass determinations of (- 0.02 ± 0.23)% for the measured U-235 and (+ 0.50 ± 0.31)% for the measured Pu-239, for a core campaign. The ICT analyses has been implemented for the plutonium isotopics in a depleted uranium assembly in a heavy-water, enriched uranium system and for the uranium isotopes in the fuel assemblies in light-water, highly-enriched systems

America's nuclear waste backlog

International Nuclear Information System (INIS)

Benenson, R.

1981-01-01

This report discusses three topics: concern and controversy relating to nuclear waste; high-level waste storage and politics of waste disposal. The most pressing waste disposal problem concerns spent fuel assemblies from commercial nuclear power plants. It was expected that commercial spent fuel would be sent to commercial reprocessing plants. The feasibility of commercial reprocessing in the United States is contingent on the expansion of the nuclear power industry. The current high-level liquid waste inventory is about 77 million gallons. These are stored at Richland, Washington; Aiken, South Carolina; and Idaho Falls, Idaho. The only commercial high-level wastes ever produced are stored at the defunct reprocessing facility at West Valley, New York. A high-level waste repository must be capable of isolating wastes that will remain dangerous for thousands of years. Salt has long been considered the most suitable medium for high-level and transuranic waste disposal. The timetable for opening a deep geological repository is one of the issues that will have to be dealt with by Congress. The 97th Congress appears ready to act on high-level nuclear waste legislation. Even opponents of nuclear expansion admit the necessity of legislation. Even if Congress gets its act together, it does not mean that the nuclear waste issue is gone. There are still unknowns - future of reprocessing, the needs and demands of the military; the health of the nuclear power industry; the objections of residents in potential site areas; the possibility of a state veto, and the unsolved technological problems in geologic site selection

Pilot studies of an extraction process for reprocessing of spent fuel from fast reactors: Hardware and process details of extractor selection

International Nuclear Information System (INIS)

Anisimov, V.I.; Pavlovich, V.B.; Smetanin, E.Ya.; Glazunov, N.V.; Shklyar, L.I.; Dubrovskii, V.G.; Serov, A.V.; Zakharkin, B.S.; Konorchenko, V.D.; Korotkov, I.A.; Neumoev, N.V.; Renard, E.V.

1992-01-01

While acknowledging the bold and persistent efforts of U.S. and Russian specialists to develop the concept of pyrochemical reprocessing of spent nuclear fuel from fast reactors on remote-controlled equipment for removal of actinides from the fission products one should recognize that the tasks of reprocessing such fuel can be handled only by using water-extraction technology, especially since the known Purex process continues to be improved to the point that a single-cycle scheme may be developed. This article presents results of pilot studies conducted in hot cells using multistage extractors in continuous counterflow operation; data on various extractor types used in reprocessing spent mixed oxide nuclear fuel; advantages and disadvantages of centrifugal and pulsed column extractor; comparison of column-type and centrifugal extractors; and extraction process

Optimal sizes and siting of nuclear fuel reprocessing plants; Tailles et localisations optimales des usines de retraitement des combustibles nucleaires

Energy Technology Data Exchange (ETDEWEB)

Thiriet, L; Deledicq, A [Commissariat a l' Energie Atomique, Siege (France). Centre d' Etudes Nucleaires

1967-07-01

The expansion of a nuclear economy entails the development of fuel process and reprocessing plant programmes. The model proposed makes it possible to select the size, the site and the start-up schedule of the plants in such a way as to minimize the total freight and reprocessing costs. As an illustration, we have approached the problem of burnt natural uranium processing plants related to natural uranium-graphite as nuclear power stations. The sites and annual output of the reactors, the possible plant sites and cost functions (freight and reprocessing) are supposed to be known. The method consists in first approaching the process plant problem as a Dynamic Programming problem, increasing programme slices (total reactor output) being explored sequentially. When the quantities of burnt natural uranium to be reprocessed are fixed, the minimization of the transport cost is then also carried out as a dynamic programming problem. The neighbourhood of the optimum process cost is explored in order to find the minimum summation of a suboptimal processing cost and corresponding optimal transport cost. As the reprocessing problem can be represented on a sequential graph, in order to compute the sub-optima, we developed and used a 'reflexion algorithm'. The method can be interpreted as a general mechanism for determining the optimum when to a sequential dynamic problem (for example an equipment programme) is added a complementary problem (transport, for instance). It also makes it possible to estimate the economic losses which result from the choice of a non optimal policy for other than economic reasons. (author) [French] L'expansion de l'economie nucleaire se traduit par un developpement des programmes d'usines d'elaboration et de retraitement des combustibles. Le modele propose permet de choisir la taille, la localisation et la cadence de mise en service des usines de maniere a minimiser le total des frais de transport et de retraitement. A titre d'exemple nous avons

THORP and the economics of reprocessing

International Nuclear Information System (INIS)

Berkhout, F.; Walker, W.

1990-11-01

This Report compares the costs of reprocessing spent fuels at the new THORP reprocessing plant at Sellafield with the alternative of storing them prior to final disposal. It finds that even when the cost of constructing THORP is treated as a sunk cost, reprocessing has no decisive economic advantage over spent fuel storage. Electric utilities in Western Europe and Japan have already largely paid for the construction of the new British and French reprocessing plants. Today, their economic judgements therefore depend on the future costs of operating and eventually decommissioning the plants, and of dealing with the resulting wastes and separated products. The costs attached to reprocessing have risen mainly due to the higher estimated costs of waste management and decommissioning, and to the costs of coping with unwanted plutonium. Most of these costs are passed directly on to utilities and thus electricity consumers under the terms of cost-plus contracts. Using cost estimates favourable to the reprocessing option, the total future undiscounted liabilities arising from the first ten years of THORP reprocessing come to Pound 2.4-3.7 billion at today's prices. This compares with the more predictable although still burdensome fuel storage, conditioning and disposal costs of Pound 3.0-3.8 billion. If disposal is not anticipated, the economic advantage shifts decisively in favour of spent fuel storage: Pound 0.9-1.3 billion against Pound 1.4-2.4 billion for reprocessing. (author)

Case outsourcing medical device reprocessing.