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Sample records for cogema reprocessing plants

  1. Computerized Analytical Data Management System and Automated Analytical Sample Transfer System at the COGEMA Reprocessing Plants in La Hague

    International Nuclear Information System (INIS)

    Flament, T.; Goasmat, F.; Poilane, F.

    2002-01-01

    Managing the operation of large commercial spent nuclear fuel reprocessing plants, such as UP3 and UP2-800 in La Hague, France, requires an extensive analytical program and the shortest possible analysis response times. COGEMA, together with its engineering subsidiary SGN, decided to build high-performance laboratories to support operations in its plants. These laboratories feature automated equipment, safe environments for operators, and short response times, all in centralized installations. Implementation of a computerized analytical data management system and a fully automated pneumatic system for the transfer of radioactive samples was a key factor contributing to the successful operation of the laboratories and plants

  2. 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

  3. Vitrification of HLW produced by uranium/molybdenum fuel reprocessing in cogema's cold crucible melter

    International Nuclear Information System (INIS)

    Quang, R. Do; Petitjean, V.; Hollebeque, F.; Pinet, O.; Flament, T.; Prodhomme, A.; Dalcorso, J. P.

    2003-01-01

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

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  5. Transport of oxide spent fuel. Industrial experience of COGEMA

    International Nuclear Information System (INIS)

    Lenail, B.

    1985-01-01

    COGEMA, the world leading Company in the reprocessing industry who is also involved in the transport activity, is ruling all transports of spent fuel to La Hague reprocessing plant. The paper summarizes some aspects of the experience gained in this field (road, rail and sea transports) and describes the standards defined by COGEMA as regards transport casks. These standards are as follows: - casks of dry type, - casks of the maximum size compatible with rail transports, - capability to be unloaded with standardized equipment and following standard procedures. Considering: 1) the extremely large experience of COGEMA for all transport modes and, 2) the fact that all these transports are performed in full compliance with the IAEA recommendations, COGEMA is convinced that its experience could serve to help countries or utilities willing to undertake to establish a transport system within their own country COGEMA is prepared to contribute to this task on terms to be agreed [fr

  6. The Cogema group in Japan

    International Nuclear Information System (INIS)

    1998-12-01

    The partnership between the Cogema group and Japan in the domain of fuel cycle started about 20 years ago and the 10 Japanese nuclear operators are all clients of the Cogema group. The 1997 turnover realized with Japan reached 3.6 billions of francs (11% of the total turnover of the group). This short paper presents briefly the nuclear program of Japan (nuclear park, spent fuels reprocessing-recycling strategy) and the contracts between Cogema and the Japanese nuclear operators (natural uranium, uranium conversion and enrichment, spent fuel reprocessing, plutonium recycle and MOX fuel production markets). (J.S.)

  7. Transport of oxide spent fuel. Industrial experience of COGEMA

    International Nuclear Information System (INIS)

    Lenail, B.

    1983-01-01

    COGEMA is ruling all transports of spent fuel to La Hague reprocessing plant. The paper summarizes some aspects of the experience gained in this field (road, rail and sea transports) and describes the standards defined by COGEMA as regards transport casks. These standards are as follows: - casks of dry type, - casks of the maximum size compatible with rail transports, - capability to be unloaded with standardized equipment and following standard procedures

  8. Reprocessing RTR fuel in the La Hague plants

    International Nuclear Information System (INIS)

    Thomasson, J.; Drain, F.; David, A.

    2001-01-01

    Starting in 2006, research reactors operators will be fully responsible for the back-end management of their spent fuel. It appears that the only solution for this management is treatment-conditioning, which could be done at the La Hague reprocessing complex in France. The fissile material can be separated in the reprocessing plants and the final waste can be encapsulated in a matrix adapted to its potential hazards. RTR reprocessing at La Hague would require some modifications, since the plant had been primarily designed to reprocess fuel from light water reactors. Many provisions have been taken at the plant design stage, however, and the modifications would be feasible even during active operations, as was done from 1993 to 1995 when a new liquid waste management was implemented, and when one of the two vitrification facilities was improved. To achieve RTR back-end management, COGEMA and its partners are also conducting R and D to define a new generation of LEU fuel with performance characteristics approximating those of HEU fuel. This new-generation fuel would be easier to reprocess. (author)

  9. Reprocessing RTR fuel in the La Hague plants

    Energy Technology Data Exchange (ETDEWEB)

    Thomasson, J. [Cogema, F-78140 Velizy (France); Drain, F.; David, A. [SGN, F-78182 Saint Quentin en Yvelines (France)

    2001-07-01

    Starting in 2006, research reactors operators will be fully responsible for the back-end management of their spent fuel. It appears that the only solution for this management is treatment-conditioning, which could be done at the La Hague reprocessing complex in France. The fissile material can be separated in the reprocessing plants and the final waste can be encapsulated in a matrix adapted to its potential hazards. RTR reprocessing at La Hague would require some modifications, since the plant had been primarily designed to reprocess fuel from light water reactors. Many provisions have been taken at the plant design stage, however, and the modifications would be feasible even during active operations, as was done from 1993 to 1995 when a new liquid waste management was implemented, and when one of the two vitrification facilities was improved. To achieve RTR back-end management, COGEMA and its partners are also conducting R and D to define a new generation of LEU fuel with performance characteristics approximating those of HEU fuel. This new-generation fuel would be easier to reprocess. (author)

  10. Reprocessing RTR fuel in the La Hague plants

    Energy Technology Data Exchange (ETDEWEB)

    Thomasson, J. [Cogema, 78 - Velizy Villacoublay (France); Drain, F.; David, A. [SGN, 78 - Saint Quentin en Yveline (France)

    2001-07-01

    Starting in 2006, research reactors operators will be fully responsible for their research and testing reactors spent fuel back-end management. It appears that the only solution for this management is treatment-conditioning, which could be done at the La Hague reprocessing complex in France. The fissile material can be separated in the reprocessing plants and the final waste can be encapsulated in a matrix adapted to its potential hazards. RTR reprocessing at La Hague would require some modifications, since the plant had been primarily designed to reprocess fuel from light water reactors. Many provisions have been taken at the plant design stage, however, and the modifications would be feasible even during active operations, as was done from 1993 to 1995 when a new liquid waste management was implemented, and when one of the two vitrification facilities was improved. To achieve RTR back-end management, COGEMA and its partners are also conducting R and D to define a new generation of LEU fuel with performance characteristics approximating those of HEU fuel. This new-generation fuel would be easier to reprocess. (author)

  11. MTR spent fuel back-end - Cogema's long-term commitment

    International Nuclear Information System (INIS)

    Thomasson, J.

    1998-01-01

    MTR spent fuel back end has been subject to many reversal and uncertainties in the past 10 years. Until the end of 1988, US obligated materials were subject to the Off site Fuels Policy (OFP). Under this policy, spent fuels were returned to USA, and were reprocessed there. This OFP took end the 31th of December 1988, and Research Reactor's operators had to implement others solutions: On site storage or Reprocessing in Europe. Meanwhile the RERTR Program was leading to a new LEU fuel to replace HEU aluminide. This new silicide fuel has one main drawback: it cannot be reprocessed in working plants without some process main line modifications. Fortunately, a new Research Reactors spent fuels return policy has been set up by the US in the early 1996. This new policy applies to all reactors converted or that have agreed to convert to LEU, and reactors operating with HEU for which no suitable LEU is available. It covers all the spent fuels discharged until 2006/05/12. But after that period of time, each reactor will be fully responsible for its spent fuels. Since the end of 1996, COGEMA is proposing reprocessing services for Aluminides spent fuels, based on the La Hague capability. This COGEMA answer is for the long term, as the La Hague plant has a good load for the coming years, including the first decade of the next century. Further, this activity benefits from a strong R and D support, that allowed fulfilling the evolutive needs of our customers, and gives us the ability to adapt the plant to the future market. Taking advantage of this flexibility, COGEMA offers Research Reactors' operators a long-term commitment. Already two reactors' operators have chosen to contract with COGEMA for the whole life of their reactors. The contracts execution is under progress and the first transportation will take place soon. Beside today's services, COGEMA is involved in R and D activities to support new fuels development enhancing present LEU performances and having the ability to

  12. Power and openness of 'Cogema'. Management of uranium and plutonium

    International Nuclear Information System (INIS)

    Andronova, L.

    2001-01-01

    In the paper the 'Cogema' group activity in all stages of nuclear industrial cycle is covered. It is noticed, that 'Cogema' have joint ventures in the field of uranium wells development in the different countries of the world. In March of 1996 'Cogema' jointly with the National Atomic Company 'Kazatomprom' (Kazakhstan) the 'Katko' joint venture have implemented. J V 'Katko' posses with two licences on uranium ores mining for a 25 year term. Use of 'Muyunkum' uranium deposit (South Kazakhstan) carrying out by the mean of leaching technology with following ores reprocessing at the pilot plant. Capacity of the plant is 100 t of commercial uranium concentrate production per year. To middle of the summer of 2001 the plant was put into operation

  13. Head-end process technology for the new reprocessing plants in France and Japan

    International Nuclear Information System (INIS)

    Saudray, D.; Hugelmann, D.; Cho, A.

    1991-01-01

    Major technological innovations brought to the new UP3 and UP2-800 reprocessing plants of COGEMA LA HAGUE and also to the JNFS ROKKASHO plant concern the head-end process. The continuous process designed allows for high throughputs whilst meeting stringent safety requirements. The head-end of each plant includes two lines for each operation in order to guarantee availability. This paper presents the T1 head-end facility of the UP3 plant as well as the few adaptations implemented in the ROKKASHO Reprocessing Plant to fulfill the particular design requirements in Japan

  14. 10 years of transport of vitrified High Level Waste (HLW) from COGEMA La Hague

    International Nuclear Information System (INIS)

    Lancelot, J.; Martinotti, B.; Tourneux, F.

    2004-01-01

    COGEMA has been using, for decades, its large experience of Reprocessing in both Gas Cooled reactors (GCR) and LWR fuels with the following facilities: Marcoule UP1 plant started up in late 50's: La Hague UP2 plant started up in 1966 first with GCR fuels and from 1976 with LWR Fuel (including foreign fuels): La Hague UP3 plant started up in 1990 Foreign Utilities signed Reprocessing Contracts with COGEMA from 1970's, providing returns of residues to the country of origin where they will be managed in a safe storage facility. Therefore, for nearly 30 years Spent Fuel coming from Japan, Germany, Belgium, Switzerland and the Netherlands are processed on La Hague site

  15. Radioactivity in waste water samples from COGEMA supplied by Greenpeace

    International Nuclear Information System (INIS)

    Reinen, H.A.J.M.; Kwakman, P.J.M.; Overwater, R.M.W.; Tax, R.B.; Nissan, L.A.

    1999-01-01

    The environmental organization Greenpeace sampled waste water from the reprocessing plant COGEMA in La Hague, France, in May 1999. On request of the Inspection Environmental Hygiene, The Dutch National Institute for Public Health and Environmental Protection (RIVM) determined the radioactivity of the waste water samples. 5 refs

  16. Transport and reprocessing of irradiated nuclear fuel

    International Nuclear Information System (INIS)

    Lenail, B.

    1981-01-01

    This contribution deals with transport and packaging of oxide fuel from and to the Cogema reprocessing plant at La Hague (France). After a general discussion of nuclear fuel and the fuel cycle, the main aspects of transport and reprocessing of oxide fuel are analysed. (Auth.)

  17. The safety of the reprocessing plant of Cogema La Hague

    International Nuclear Information System (INIS)

    Ledermann, P.

    1997-01-01

    The risks associated to the operation of a reprocessing plant come from the important quantities of radioactive matter. To insure the reprocessing safety consists in keeping, in any circumstance, the containment of radioactive matter. That this objective that leads the safety at any step of the factory life. Three risks families are listed: the risks from nuclear origin, associated to the specific physico-chemical behaviours of radioactive matter (dispersion and criticality, thermal risks and risks bound to the hydrogen production); the second family is the group of internal risks resulting from the industrial activity (chemical risks, fire risks, dysfunctions of electric installations or falls of loads); the last family is the group of external risks resulting from the impact of events reaching the site where are established the installations (risks associated to climatic conditions, risks associated to surrounding activities such explosions, fires, impact resulting from the fall of a tourism plane or road transport of hazardous matter). (N.C.)

  18. Research at COGEMA: benefits and a future outlook of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Poncelet, Francois; Masson, Herve

    2004-01-01

    COGEMA research expenses represent about Euro 100 million per year. They include the expenses for internal and external research programs and research management as well as the expenses for pre-engineering studies leading to cost evaluation. They are divided between front-end, back-end and nuclear services. Front-end expenses fell sharply when research on the SILVA enrichment process was dropped. The main objectives of the research are to maintain the ability of the industrial tool to satisfy COGEMA's clients and to increase operational safety while reducing the impact on the environment. It is also to eliminate the legacy of previous operations and to prepare for future evolutions. As far as the back-end is concerned, a large part of expenses is devoted to the 'Program of Common Interest' (PIC) with the CEA. Thanks to this fruitful collaboration, outstanding results have been obtained in the building, start-up and operation of the two modern reprocessing plants in La Hague. A new agreement is about to be signed with the CEA to follow on from the first one signed in 1978. According to this agreement, COGEMA will be financing as a lump sum a part of the expenses of ATALANTE, which is considered a very valuable research tool. Today, the main program in the PIC is still support to the La Hague reprocessing plant. More specifically, some work is still needed in the Puretex program to further improve the present performance of the plants and adapt them to the burn-up increase. There are significant programs on innovative waste vitrification, historical waste retrieval and conditioning and waste characterization including long-term behavior. Concerning Partition and Transmutation, COGEMA support is limited to the former. There is a strong incentive to understand and prepare evolutions to come that can contribute to sustainable development. Such advanced programs are also under consideration in other countries, which were not up to now willing to reprocess, such as the US

  19. 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.

  20. 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.)

  1. Nuclear propaganda war in Normandie. Cogema and Greenpeace fighting over nuclear waste disposal at Cap La Hague, France; Nucleaire propagandaoorlog in Normandie. Cogema en Greenpeace ruzien over lozingen van Cap La Hague

    Energy Technology Data Exchange (ETDEWEB)

    Passchier, W.F. [ed.

    1997-10-01

    Some background information is given with respect to the controversy between the environmental organization Greenpeace and nuclear fuel reprocessing plant of Cogema in Cap La Hague, France. On the basis of radioactivity measurements in the vicinity of the plant it is concluded that there is no radiation risk. 1 fig., 3 refs.

  2. COGEMA's UMF [Uranium Management Facility

    International Nuclear Information System (INIS)

    Lamorlette, G.; Bertrand, J.P.

    1988-01-01

    The French government-owned corporation, COGEMA, is responsible for the nuclear fuel cycle. This paper describes the activities at COGEMA's Pierrelatte facility, especially its Uranium Management Facility. UF6 handling and storage is described for natural, enriched, depleted, and reprocessed uranium. UF6 quality control specifications, sampling, and analysis (halocarbon and volatile fluorides, isotopic analysis, uranium assay, and impurities) are described. In addition, the paper discusses the filling and cleaning of containers and security at UMF

  3. Advanced Purex process for the new French reprocessing plants

    International Nuclear Information System (INIS)

    Viala, M.; Ledermann, P.; Pradel, P.

    1993-01-01

    The paper describes the main process innovations of the new Cogema reprocessing plants of La Hague (UP3 and UP2 800). Major improvements of process like the use of rotary dissolvers and annular columns, and also entirely new processes like solvent distillation and plutonium oxidizing dissolution, yield an advanced Purex process. The results of these innovations are significant improvements for throughput, end-products purification performances and waste minimization. They contribute also to limit personnel exposure. The main results of the first three years of operation are described. (author). 3 refs., 5 figs

  4. Reprocessing ability of high density fuels for research and test reactors

    International Nuclear Information System (INIS)

    Gay, A.; Belieres, M.

    1997-01-01

    The development of a new high density fuel is becoming a key issue for Research Reactors operators. Such a new fuel should be a Low Enrichment Uranium (LEU) fuel with a high density, to improve present in core performances. It must be compatible with the reprocessing in an industrial plant to provide a steady back-end solution. Within the framework of a work group CEA/CERCA/COGEMA on new fuel development for Research Reactors, COGEMA has performed an evaluation of the reprocessing ability of some fuel dispersants selected as good candidates. The results will allow US to classify these fuel dispersants from a reprocessing ability point of view. (author)

  5. Development of a continuous dissolution process for the new reprocessing plants at La Hague

    International Nuclear Information System (INIS)

    Auchapt, P.; Patarin, L.; Tarnero, M.

    1984-01-01

    The French Commissariat a l'Energie Atomique has designed a continuous rotary dissolver for LWR fuel reprocessing. An industrial prototype has been tested since 1979 at the Service des Prototypes Industriels, at Marcoule. This type of dissolver will be installed at the COGEMA's Reprocessing Plants at La Hague. The advantages of a continuous process are listed, compared to batch dissolutions (chemistry, operation, capacity). The industrial prototype, featuring safe geometry, is described. The R and D program is indicated, and the main results of inactive tests already performed on the industrial prototype are given, including heating, mechanical, and chemical tests (UO 2 dissolutions at 4tU per day)

  6. Development of a continuous dissolution process for the new reprocessing plants at La Hague

    International Nuclear Information System (INIS)

    Auchapt, P.; Patarin, L.; Tarnero, M.

    1984-08-01

    The French Commissariat a l'Energie Atomique has designed a continuous rotary dissolver for LWR fuel reprocessing. An industrial prototype has been tested since 1979 at the Service des Prototypes Industriels, at Marcoule. This type of dissolver will be installed at the COGEMA's Reprocessing Plants at La Hague. The advantages of a continuous process are listed, compared to batch dissolutions (chemistry, operation, capacity). The industrial prototype, featuring safe geometry, is described. The R and D program is indicated, and the main results of inactive tests already performed on the industrial prototype are given, including heating, mechanical, and chemical tests (UO 2 dissolutions at 4tU per day)

  7. Nuclear propaganda war in Normandie. Cogema and Greenpeace fighting over nuclear waste disposal at Cap La Hague, France

    International Nuclear Information System (INIS)

    Passchier, W.F.

    1997-01-01

    Some background information is given with respect to the controversy between the environmental organization Greenpeace and nuclear fuel reprocessing plant of Cogema in Cap La Hague, France. On the basis of radioactivity measurements in the vicinity of the plant it is concluded that there is no radiation risk. 1 fig., 3 refs

  8. A JNFL - COGEMA cooperation. Focus on the uranium tests of the Rokkasho mura Reprocessing Plant

    International Nuclear Information System (INIS)

    Griffon, Jean-Paul; Ohtou, Yoshihiro

    2005-01-01

    Description of a new type of cooperation for the start-up of the Rokkasho-mura Reprocessing Plant. After recalling the background of this cooperation the paper describes its main features: training on a sister plant and in RRP facilities, on site assistance backed-up by a dedicated team having full access to the sister plant information from the design stage to actual operations. (author)

  9. Facility - transportation system interface at COGEMA (experience in taking delivery of spent fuel)

    International Nuclear Information System (INIS)

    Lenail, B.

    1983-01-01

    COGEMA has long experience in taking delivery of spent fuel from LWR's. This activity is now fully industrialized. Great care is taken by COGEMA and their affiliates in this business, generally beyond the normal regulatory limits, and this is quite normal, COGEMA wanting to prevent, by all possible means, causes of incidents or accidents which could destroy the position it has established and the confidence placed in it by many customers. It is clear that the situation is quite different at reactors and at reprocessing plants; the limited number of flasks handled at reactors (in general five per year) is generally not enough to lead reactor operators to invest in sophisticated equipment and to adopt procedures allowing extremely small exposures of their personnel, while the great number of flasks received each year in a plant like La Hague (not fewer than 200 per year) justifies the investment in more specialized equipment (automation, remote operation, more sophisticated tools, etc.) and allows the personnel to be very well trained to that particular type of work. These are factors leading to very limited exposures of the personnel although the work performed in a repocessing plant is generally more complex (deeper decontamination, closer work, maintenance, etc.) than in a reactor

  10. 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

  11. 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)

  12. Polyvalent intermediate storage: first step in the cleaning of the Cogema Marcoule site

    Energy Technology Data Exchange (ETDEWEB)

    Cabe, J.M. [Cogema, 30 - Marcoule (France); Seurat, Ph. [Societe Generale pour les Techniques Nouvelles, SGN, 30 - Bagnols sur Ceze (France)

    1998-07-01

    Cleaning operations of Marcoule site consist, beside the permanent stop and the dismantling of the Cogema 's nuclear fuel reprocessing plant U.P.1., in assuring waste retaking and conditioning not dispatched to C.S.M., for the moment stored on production or pretreatment facilities, under a stabilized form. The Polyvalent Intermediate Storage (E.I.P.) receives preconditioned waste before treatment and reconditioning, receives storing over about 50 years conditioned waste before a permanent repository. Its main function is to wait for the construction of long term repository. (N.C.)

  13. Polyvalent intermediate storage: first step in the cleaning of the Cogema Marcoule site

    International Nuclear Information System (INIS)

    Cabe, J.M.; Seurat, Ph.

    1998-01-01

    Cleaning operations of Marcoule site consist, beside the permanent stop and the dismantling of the Cogema 's nuclear fuel reprocessing plant U.P.1., in assuring waste retaking and conditioning not dispatched to C.S.M., for the moment stored on production or pretreatment facilities, under a stabilized form. The Polyvalent Intermediate Storage (E.I.P.) receives preconditioned waste before treatment and reconditioning, receives storing over about 50 years conditioned waste before a permanent repository. Its main function is to wait for the construction of long term repository. (N.C.)

  14. Total data management in the La Hague reprocessing plant

    International Nuclear Information System (INIS)

    Berthion, Y.; Perot, J.P.; Silie, P.

    1993-01-01

    Due to the complexity of a spent fuel reprocessing plant and its nuclear characteristics, the operators must have real-time access to updated information on many subjects. To meet these requirements effectively, Cogema has installed a number of diversified data processing systems linked by a communications network called Haguenet. The whole system forms the La Hague Total Data Management System (TDMS) which performs a full range of functions, namely production data management, maintenance data management, technical documentation and miscellaneous. Some examples of the main process data management applications implemented within the La Hague TDMS are briefly described (nuclear materials and waste follow-up, analytical data management, operating procedures management and site inspection management). Also presented are some examples of the maintenance-related systems implemented within the La Hague TDMS (diagnostic assistance system, software maintenance center, maintenance interventions demand and spare parts data management). (Z.S.)

  15. 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

  16. Diagnostic aid and maintenance at the La Hague reprocessing plants

    International Nuclear Information System (INIS)

    Bern, J.B.; Chabert, J.

    1989-01-01

    The Cogema plant at La Hague is the world's leading nuclear fuel reprocessing plant. A major extension program was initiated in 1980. It includes the construction of a new 800 t/year capacity plant (UP3), to be commissioned in 1989, and the doubling of the capacity of the present plant (UP2 800) scheduled to go on stream in 1992. On the occasion of this huge capital investment, an overall assessment was made of the operating and maintenance systems of the site. The general objective was to achieve maximum productivity and availability, in view of: - the extreme importance of safety for the protection of workers and the environment, - the high level of automation required by the complexity of the process, - the inaccessibility of the nuclear equipment, the scale of the investment. To achieve this goal, a set of diagnostic and maintenance aid systems were developed and installed. A general site data network serves to link these systems and to distribute the corresponding data to the different users. This paper describes these different systems, presents the functionalities of the network and demonstrates the sequencing of the operations in a typical maintenance application

  17. The activities of COGEMA in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Galaud, G.

    1981-02-01

    COGEMA (Compagnie Generale des Matieres Nucleaires) is a private company entirely owned by the C.E.A. Its activity covers the whole of the fuel cycle: uranium mining, production of concentrates from the extracted ore, conversion into hexafluoride, enrichment, fabrication of fuel assemblies, reprocessing of spent fuel, and packaging of waste. These different types of activity are reviewed [fr

  18. Cogema gives its communication a new impetus

    International Nuclear Information System (INIS)

    Saulnier, J.-E.

    2001-01-01

    Starting 2 November 1999, COGEMA launched a mass public communication campaign and creating an Internet site, equipped with cameras (web-cams), to make everyone familiar with the COGEMA plant at La Hague. This system is designed to serve a communication policy that is resolutely open and attentive to French public concerns: - The COGEMA plant at La Hague is often perceived as a mystery, occult and dehumanized world. This communication campaign, entitled 'We have nothing to hide', illustrated COGEMA's determination to inform the citizens in the greatest possible transparence and its wish to bring the Group's industrial operations and the persons working there closer to the public. The campaign included TV commercials and press ads. The underlying principle is to work on issues that have made news. The televised system included two films, shot at La Hague. The first, lasting 90 seconds, consists of interviews and testimonies of employees who represent the professional and human diversity of the plant. The second, in 45-second format, presents the questions to which public opinion wants answers. These questions are also repeated in the press ads. - To ensure that everyone obtains all the answers to his questions, the TV spots and press ads refer to the website http://www.cogemalahague.fr and to a toll-free number 0 800-64-64-64 . This campaign was the first stage of a long-term approach. Its positive reception from the public strengthens COGEMA's resolution to anticipate the legitimate information's needs expressed by the public opinion. As a responsible firm, COGEMA means to adapt her communication policy in order to make the whole activities of the Group widely known. Beyond communication, COGEMA intends to carry on showing her attachment to nuclear industry and bolstering this sector's interests on the international scene. (authors)

  19. COGEMA: yesterday, today, tomorrow

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    CEA's 100%-owned subsidiary Cogema was set up in July 1966. 1979 was satisfactory and 1980 looks promising. Cogema is involved in all the phases of the nuclear fuel cycle except for the manufacture of the fuel itself, a gap that it is planning to fill. Cogema's discovery of the Coutras deposit in the Gironde is 'the good news' of the year. Work on the Eurodif uranium enrichment plant at Tricastin is almost finished and by the end of 1981 it will be operating at its full capacity of 10,8 million SWU. On the processing side, work on expanding existing facilities has begun (UP2 800 and UP3). In 1985 La Hague's foreign clients UP2 will process 1,200 tons and UP3 6000 tons [fr

  20. 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.)

  1. Cogema experience on retrieving and conditioning solid radwaste previously stored in pits. The La Hague north west pit case

    International Nuclear Information System (INIS)

    Bodin, F.; Alexandre, D.; Fournier, Ph.

    2000-01-01

    Short lived, low and medium level waste called 'technological waste' produced by the La Hague Reprocessing Plant have been stored in the La Hague North-West concrete-lined pits until implementation at ANDRA's Centre de Stockage de la Manche (CSM). COGEMA decided to retrieve and condition 11,000 m 3 of humid solid radwaste, stored in bulk in pits. This report describes the experience gained from February 1990 to December 1998, taking into account radwaste and integrated dose rate results conditioning such waste. The procedures and means used and improved by COGEMA to comply with ANDRA's storage standards and the ever-decreasing financial costs generated by the workers, allowed to retrieve and condition 11,000 m 3 of old solid radwaste with competitive costs and in complete safety and protection of the environment. (authors)

  2. Contribution of research and development and engineering to a large reprocessing plant project. Extension of the La Hague plant

    International Nuclear Information System (INIS)

    Boutaud de la Combe, P.; Courouble, J.M.; Sauteron, J.; Redon, A.

    1983-01-01

    Two reprocessing plants are operated by Cogema: Marcoule (since 1958) and La Hague (since 1967). Since 1976 the latter has been reprocessing LWR assemblies in its 'HAO' workshop, operation of which has provided industrial experience in the reprocessing of this type of fuel. This experience will be drawn upon in the construction of extensions to the La Hague plant, namely the UP3 plant, which will have a capacity of 800 t/a, and UP2-800, which will expand the present plant likewise to a capacity of 800 t/a. These extensions will contain a number of improvements, particularly in the areas of safety and waste treatment, and of procedure and equipment. A considerable R and D contribution is provided by the French Atomic Energy Commission (CEA), which is the licence holder, with its laboratories at Fontenay and the pilot workshop and industrial prototypes service at Marcoule. This activity supports all phases of the project, from the establishment of basic principles to the definition of essential characteristics of equipment, covering also the testing of full-scale prototypes (mock-ups) for the principal components: rotating continuous dissolver, swinging decanter, subcritical pulsed columns, used-solvent distilling apparatus, fission-product vitrification furnace, etc. Engineering work for the new facilities is performed by the Societe generale pour les techniques nouvelles in four phases: (1) establishment of basic data; (2) preparation of preliminary plans (including an estimate and a preliminary schedule) and of the preliminary safety reports; (3) drafting of the 'project' file, giving definitive costs and deadlines; (4) implementation, up to and including the operational testing stage. All phases of design and implementation are subject to a quality assurance programme. Extension of the La Hague plant represents an investment of 23,500 million French francs (in July 1981). Construction is expected to be completed in 1989. (author)

  3. Cogema looks to wider markets

    International Nuclear Information System (INIS)

    Cruikshank, A.

    1984-01-01

    As the pace of the French nuclear programme slackens off, Cogema is planning to compete even more vigorously in world fuel cycle markets. The company believes the foundations for success lie in its comprehensive range of fuel cycle activities, its status as a wholly-owned subsidiary of the Commissariat a l'Energie Atomique, and its experience in fulfilling the bulk of French fuel cycle needs. To build on these foundations, Cogema is exploring for uranium, investing heavily in new plant, and strengthening its commercial management. (author)

  4. Japanese national reference reprocessing plant

    International Nuclear Information System (INIS)

    1978-08-01

    This paper gives a general description of the proposed Japanese national reprocessing plant and of the design philosophy. The plant is in most respects similar to the base case reprocessing plant, with an annual throughput of 100-1500 tU. The plant would be co-located with a fuel fabrication facility

  5. 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

  6. 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.)

  7. Environment supervision in a nuclear industry plant: Cogema example in Pierrelatte

    International Nuclear Information System (INIS)

    Faure, M.L.

    1993-07-01

    Every nuclear industrial facility must achieve radioactivity measurements of its environment: COGEMA is therefore very careful of its environmental quality and guarantees the supervision of it with a programme corresponding to the activities and to the environment characteristics. We shall study- the atmospheric control- the waters control- the plants control and we shall end on results synthesis, which must be analysed according to the natural omnipresent radioactivity. 6 Annexes

  8. A look inside Cogema

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    This article highlights four major acquisition by Cogema as it attempts to become the world's only fully integrated supplies of nuclear fuel. April 1992, Cogema buys 70% of German mining and trading company Urangesellschaft, significantly increasing its uranium reserves in the so-called open-quotes dollar-zoneclose quotes of the US, Canada, and Australia, as well as in Namibia and Niger. The UG deal solidifies Cogema's stature as a top-rank uranium producer and gives it a large presence in uranium trading. July 1992, As part of the consolidation of the French nuclear industry, Cogema buys the front-end fuel cycle and transportation businesses of Pechiney. February 1993, Cogema buys Cameco's 20% share of the Cluff Lake mine in Saskatchewan, giving it full ownership of one of the world's leading uranium deposits, with ore grades around 1% U3O8. May 1993, in its biggest deal yet, Cogema buys all the uranium assets of the French oil group Total. The deal leaves Cogema as France's only uranium producer

  9. Multipurpose interim storage facility: first step in cleanup of the Cogema Marcoule site

    Energy Technology Data Exchange (ETDEWEB)

    Cabe, J.M.; Themines, R.; Pasquale, B. [Cogema, 30 - Marcoule (France); Misraki, J. [CIE CODEM Paniscoule, 30 - Bagnols sur Ceze (France); Seurat, Ph. [SGN 30 - Bagnols sur Ceze (France)

    2000-07-01

    The COGEMA's graphite-gas fuel reprocessing plant UP1, located in Marcoule (Gard department in France) as been started up in the late fifties. UP1 has been in the final shutdown process since 1998. The function of the Multi-purpose Interim Storage (EIP) is to receive waste - before treatment and reconditioning, - already treated, waiting for a decision on the final disposal according to the law of december 30. 1991. For the purpose, the design was based on a system of modular storage compartments by kinds of waste and a variety of multi-purpose handling means consistent with the reception of different types of packages. The installation has been designed for a lifetime of 50 years as from the basic design phase. (authors)

  10. Multipurpose interim storage facility: first step in cleanup of the Cogema Marcoule site

    International Nuclear Information System (INIS)

    Cabe, J.M.; Themines, R.; Pasquale, B.; Misraki, J.; Seurat, Ph.

    2000-01-01

    The COGEMA's graphite-gas fuel reprocessing plant UP1, located in Marcoule (Gard department in France) as been started up in the late fifties. UP1 has been in the final shutdown process since 1998. The function of the Multi-purpose Interim Storage (EIP) is to receive waste - before treatment and reconditioning, - already treated, waiting for a decision on the final disposal according to the law of december 30. 1991. For the purpose, the design was based on a system of modular storage compartments by kinds of waste and a variety of multi-purpose handling means consistent with the reception of different types of packages. The installation has been designed for a lifetime of 50 years as from the basic design phase. (authors)

  11. Base case industrial reprocessing plant

    International Nuclear Information System (INIS)

    1978-11-01

    This paper briefly describes an industrial scale plant for reprocessing thermal oxide fuel. This description was used as a base case by the Group for their later assessments and for comparing actual national plans for reprocessing plants. The plant described uses the Purex process and assumes an annual throughput of 1000 t/U. The maintenance, safety and safeguards philosophy is described. An indication of the construction schedule and capital and operating costs is also given

  12. The UP3-UP2 800 reprocessing plants control systems. Use of tools for the diagnosis, the track of control softwares and the management of technical data

    International Nuclear Information System (INIS)

    Chabert, J.; Michon, J.C.

    1995-01-01

    After a rapid presentation of control systems architectures of the La Hague COGEMA reprocessing plants, details are given about the tools used to master the control and instrumentation softwares and technical data. The paper focusses more particularly on the CML (Software Maintenance Center) tool which manages the software versions installed on the driving system, on the SYDDEX tool devoted to the management of the control and instrumentation associated data and documents, and on the SAD tool used for diagnosis assistance. (J.S.). 5 figs

  13. Mining activities of the Cogema group; Activite miniere du groupe Cogema

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1996-12-31

    This brochure is a general presentation of the mining activities of the COGEMA group. COGEMA is specialized in the whole operations of the nuclear fuel cycle and is responsible for about 20% of the worldwide uranium production with the exploitation of French mines and its participation in the exploitation of mines abroad, mainly in Canada, USA, Niger and Gabon. This document is divided in seven chapters: the search for uranium ores and the mining prospecting, the uranium deposits and the worldwide market, the exploitation of uranium ores (techniques and mines exploited by the COGEMA group), the processing of ores, the radioactivity and the mining installations, the environmental protection and the rehabilitation of sites (environmental survey and management of mining sites), application of COGEMA`s know-how to other domains such as: gold ore processing, research and development studies, instrumentation and radioprotection, soils cleansing and sites rehabilitation. This brochure is illustrated with several photos and pictures. (J.S.).

  14. Safeguarding a future industrial reprocessing plant

    International Nuclear Information System (INIS)

    1978-11-01

    This paper is submitted to Working Group 5, Sub-Group B for information. It is being submitted to Working Group 4 for discussion at their meeting in January 1979 and shows that by a combination of accountancy, surveillance and containment a reliable safeguards system can be designed for the reprocessing of fuels of the BWR and PWR type. Its arguments can, in general terms, be applied to plants for reprocessing LMFBR fuels, with due allowance for future advances which should improve our overall knowledge of the reliability of safeguards systems. In the reprocessing of fast reactor (LMFBR) fuels, as compared with LWR fuels, the main differences are the higher plutonium concentration and lower heavy metal throughput in the early stages of the reprocessing operations. At later stages in the process (after plutonium/uranium separation) the plants could be similar and have similar safeguarding problems. Plants for reprocessing LMFBR on a commercial scale will not be in operation for a number of years. In these plants greater attention may have to be paid to safeguards at the early stages, especially to waste/raffinate streams, than in the PWR/BWR reprocessing plant. The actual balance between containment, surveillance and accountancy adopted will depend on the status of the technology of safeguards and reprocessing. It can be anticipated that improvements to measurement systems will be made which may allow greater reliance on actual measurement. Treatment and recycle of solid wastes will advance and could therefore lead to improvements in accountancy in, for example, the ''head-end''

  15. Burn-up credit applications for UO2 and MOX fuel assemblies in AREVA/COGEMA

    International Nuclear Information System (INIS)

    Toubon, H.; Riffard, C.; Batifol, M.; Pelletier, S.

    2003-01-01

    For the last seven years, AREVA/COGEMA has been implementing the second phase of its burn-up credit program (the incorporation of fission products). Since the early nineties, major actinides have been taken into account in criticality analyses first for reprocessing applications, then for transport and storage of fuel assemblies Next year (2004) COGEMA will take into account the six main fission products (Rh103, Cs133, Nd143, Sm149, Sm152 and Gd155) that make up 50% of the anti-reactivity of all fission products. The experimental program will soon be finished. The new burn-up credit methodology is in progress. After a brief overview of BUC R and D program and COGEMA's application of the BUC, this paper will focus on the new burn-up measurement for UO2 and MOX fuel assemblies. It details the measurement instrumentation and the measurement experiments on MOX fuels performed at La Hague in January 2003. (author)

  16. COGEMA experience on retrieving and conditioning solid radwaste previously stored in pits. The La Hague North-West pit case

    International Nuclear Information System (INIS)

    Bodin, F.; Alexandre, D.; Fournier, P.

    1999-01-01

    Short lived, low and medium level waste called 'technological waste' produced by the La Hague Reprocessing Plant have been stored in the La Hague North-West concrete-lined pits until implementation at ANDRA's Centre de Stockage de la Manche (CSM). COGEMA decided to retrieve and condition 11,000 m 3 of humid solid radwaste, stored in bulk in pits. On account of the variety of radwaste kinds, retrieving and conditioning operations represented real challenge. One goal of these operations was to ensure that the work was performed in complete safety towards environment with optimum containment and with the best radiation protection for the personnel involved. COGEMA decided to split the work into two phases. The feedback from the first phase was very helpful to the second phase. This report describes the experience gained from February 1990 to December 1998, taking into account radwaste and integrated dose rate results conditioning such waste. The procedures and means used and improved by COGEMA to comply with ANDRA's storage standards and the ever-decreasing financial costs generated by the workers, allowed to retrieve and condition 11,000 m 3 of old solid radwaste with competitive costs and in complete safety and protection of the environment. (author)

  17. Seismic tests on a reduced scale mock-up of a reprocessing plant cooling pond

    International Nuclear Information System (INIS)

    Queval, J.C.; Gantenbein, F.; Lebelle, M.

    1995-01-01

    In conjunction with COGEMA and SGN, CEA has launched an important research program to validate the reprocessing plant cooling pond calculation mainly for the effect of the racks on the fluid-pond interaction. The paper presents the tests performed on a reduced scale mock-up (scale 1/5). The tests are composed by: -random excitations at very low excitation level to measure the natural frequencies, especially the first sloshing mode frequency; -sinusoidal tests to measure the damping; -seismic tests performed with 3 different time reduction scales (1, 1/5, 1/√5) and 3 different synthetic accelerograms. Two types of simplified model with added masses and finite element model were developed. Comparisons of measured and calculated pressure fields against the panels will be presented. The measured frequencies, obtained during tests, are in good agreement with Housner's results. (authors). 2 refs., 4 figs., 5 tabs

  18. 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

  19. Actinides exposure: review of Ca-DTPA injections inside Cea-Cogema plants

    International Nuclear Information System (INIS)

    Grappin, L.; Berard, P.; Beau, P.; Carbone, L.; Castagnet, X.; Courtay, C.; Le Goff, J.P.; Menetrier, F.; Neron, M.; Piechowski, J.

    2006-01-01

    Ca-DTPA has been used for medical treatment of plutonium and americium contaminations in the CEA and COGEMA plants from 1970 to 2003. This report is a survey of the injections administered of Ca-DTPA as a chelating molecule. This report will be a part of the AMM process for Ca-DTPA by intravenous administration submitted by the Central Pharmacy of the french Army. Out of 1158 injections administered to 469 persons, 548 events of possible or confirmed contaminations were reported. These employees were followed by occupational physicians according to the current regulations. The first part of the report is a synthesis of the most recent findings. Due to its short biological period and its limited action in the blood, Ca-DTPA does not chelate with plutonium and americium as soon as these elements are deposited in the target organs. It justifies an early treatment, even in cases of suspected contamination followed by additional injections if necessary. The second part presents data concerning these 1158 injections (way of contamination, posology, adverse effects...). These incidents took place at work, were most often minor, not requiring follow-up treatment. A study concerning the effectiveness of the product was done on a group of people having received 5 or more injections. These results were compared with effectiveness estimated from theoretical basis. Posologies and therapeutic schemes were proposed based on these observations. Additional studies are needed to confirm these findings. This document is the first synthesis in this field. It is the result of a collective work having mobilized the occupational medicine departments, the laboratories of CEA and COGEMA and a working group CEA-COGEMA-SPRA. (authors)

  20. 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

  1. The case for reprocessing: the operational experience of a modern reprocessing industry

    International Nuclear Information System (INIS)

    Giraud, J.P.; Kelly, W.

    1993-01-01

    Reprocessing is a high-tech industry that works. An impressive effort of R and D, industrial deployment and operational experience has been accumulated by COGEMA and BNFL, leading these companies to offer a commercial service which is the only proper management of spent fuel and waste that is both technically demonstrated and qualified by the safety authorities of European and overseas countries. Reprocessing, as every technology-based industry will continue to progress in the future. Recycling the fissile materials reclaimed from spent fuel: uranium and plutonium, is the complementary and indispensable last link to effectively close the fuel cycle and control in particular the production of plutonium and other long-lived actinides. This paper will describe the state of development attained in France and Great Britain and will underline the main advantages of the reprocessing/recycling strategy

  2. Discharges from a fast reactor reprocessing plant

    International Nuclear Information System (INIS)

    Barnes, D.S.

    1987-01-01

    The purpose of this paper is to assess the environmental impact of the calculated routine discharges from a fast reactor fuel reprocessing plant. These assessments have been carried out during the early stages of an evolving in-depth study which culminated in the design for a European demonstration reprocessing plant (EDRP). This plant would be capable of reprocessing irradiated fuel from a series of European fast reactors. Cost-benefit analysis has then been used to assess whether further reductions in the currently predicted routine discharges would be economically justified

  3. Cogema's transatlantic partnership

    International Nuclear Information System (INIS)

    McMurphy, M.; Ihde, R.

    1991-01-01

    Cogema's transatlantic partnership, the B+W Fuel Company, is a natural evolution of Cogema's US fuel cycle activities. The partnership in which important elements of the French nuclear industry teamed with a long-established, well-respected US industrial partner to build a company for the future is explained. 1 fig

  4. 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

  5. Cogema and the recycling of nuclear military materials

    International Nuclear Information System (INIS)

    1999-04-01

    The signature of the Start 1 and Start 2 treaties in 1991 and 1993 has marked the start-up of nuclear disarmament. This process covers two aspects: the destruction of vectors (missiles, planes..) and the dismantling of warheads carrying weapon grade radioactive materials (uranium and plutonium). This dossier explains the political and technical choices made by Russia and the USA for the management of their weapon grade plutonium: fabrication of MOX fuels (cooperation between Minatom (Russia), Siemens and Cogema for the building of conversion and fabrication plants, collaboration between Cogema, Duke Engineering and Stone and Webster (DCS) for the building of a MOX fabrication plant and for the irradiation of MOX fuels in US reactors), disposal of hardly convertible plutonium. (J.S.)

  6. Development of Tokai reprocessing plant maintenance support system (TORMASS) in the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Shimizu, Kazuyuki; Tomita, Tsuneo; Sakai, Katsumi

    2008-01-01

    The maintenance work of many equipments such as mechanical, electrical and instrumentations installed in Tokai reprocessing plant has been performed more then 10,000 times per year and about 90% of maintenances were preventive work. For the maintenance management, optimization of maintenance information is required. Therefore, Tokai Reprocessing Plant Maintenance Support System (TORMASS) was developed from 1985 to 1992 as the aim of construction for suitable maintenance management system. About 24,000 equipments of specifications and about 261,000 maintenance detail were registered in this system. TORMASS has been used for the repair, inspection and replacement of equipment since 1992. (author)

  7. 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)

  8. The 4th technological meeting of Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Ohnishi, Tohru; Maki, Akira; Shibata, Satomi; Yatogi, Hideo; Nyui, Daisuke; Hashimoto, Takakazu; Fukuda, Kazuhito; Ohzeki, Tatsuya

    2001-11-01

    ''The 4th technological meeting of Tokai Reprocessing Plant (TRP)'' was held in JNFL Rokkasho site on October 11 th , 2001. The report contains the proceedings, transparencies and questionnaires of the meeting. This time, we reported about ''Maintenance and repair results of Tokai Reprocessing Plant'' based on technology and knowledge accumulated in Tokai Reprocessing Plant. (author)

  9. Safeguards for reprocessing and enrichment plants

    International Nuclear Information System (INIS)

    1977-01-01

    Agency safeguards are entering a new phase with the coming under active safeguards for the first time of reprocessing plants in several regions of the world. This is taking place at a time when not only the safeguards aspect itself is coming under international scrutiny, but also at a time when the necessity of reprocessing plants is being called into question. Attracting less attention at the moment, but potentially of equal significance, are the enrichment plants that soon will be coming under Agency safeguards. It is not unreasonable in view of the present controversies to ask what is the significance of these reprocessing and enrichment plants, what are the problems concerning safeguards that appear to have given rise to the controversies, and how these problems are to be solved. The question of significance is an easy one to answer. The output of these plants is material which some people consider can be used directly for military purposes, whereas the output from other plants, for instance, reactors, would require long and extensive processing before it could be used for military purposes. Like most short answers, this one is an over-simplification which requires some elaboration to make it strictly accurate. For example, the material output of a power reactor is in the form of irradiate assemblies containing plutonium which is potentially of military use if the irradiation had been within a certain range. However, to utilize this plutonium under clandestine conditions, the highly radioactive material would have to be secretly transported to a reprocessing plant and there would have to be simultaneous falsification of the reactor material accounts and the plant records. Such falsification would be difficult to conceal. The total time required to obtain usable plutonium would be many months. Diversion of material from a uranium fabrication plant making fuel for power reactors would be easier physically but strategically it would be of little value. The

  10. Radioactive wastes from reprocessing plants

    International Nuclear Information System (INIS)

    Huppert, K.L.

    1977-01-01

    The lecture deals with definition, quantity and type of radioactive waste products occurring in a fuel reprocessing plant. Solid, liquid and gaseous fission and activation products are formed during the dissolution of the fuel and during the extraction process, and they must be separated from the fissionalble uranium and plutonium not spent. The chemical behaviour of these products (Zr, Ru, Np, gaseous substances, radiolysis products), which is sometimes very problematic, necessitates careful process control. However, the lifetime of nuclides is just as important for the conditions of the reprocessing procedure. The types of waste obtained after reprocessing are classified according to their state of aggregation and level of activity and - on the basis of the operational data of a prototype plant - they are quantitatively extrapolated for the operation of a large-scale facility of 1,400 tons of fuel annually. (RB) [de

  11. UP3 plant first reprocessing campaigns

    International Nuclear Information System (INIS)

    Leudet, A.; Hugelmann, D.; Fournier, W.; Dalverny, G.

    1991-01-01

    The UP3 plant start up has been achieved in two successive steps. The first one, from November 89 to April 90, involved all the facilities but T1, the head-end facility. During that period, shearing, dissolution and the first cycle extraction operations were performed in UP2 plant. 100 tons of fuel have been reprocessed that way. The second step began in August 1990, with the T1 facility start-up and the reprocessing of the resulting active solutions in the rest of the plant. This second phase involving the entire UP3 plant continued until the end of January 1991. At that time, 160 tons of fuel have been completely treated in UP3 plant

  12. Refurbishment of the BNFL Magnox reprocessing plant

    International Nuclear Information System (INIS)

    Carr, V.M.; Edgar, R.

    1998-01-01

    The Magnox Reprocessing Plant was commissioned in 1964. Since then it has reprocessed more than 35,000 t of irradiated uranium metal fuel. The plant is subject to routine shutdowns to allow maintenance and project work to be undertaken. During the 1997 shutdown the opportunity was taken to replace several life limiting parts of the plant to ensure Magnox reprocessing capability well beyond the year 2010. This shutdown was the largest and most complex undertaken by Magnox Reprocessing, with a total committed value of 130 million UK pounds, 17.5 million UK pounds committed in the shutdown itself and the balance on installation, design and procurement preparing for the shutdown. The work was completed within safety targets, to programme and within budget. The lessons learned and experience gained have been fed into the methodologies and procedures for planning future project and shutdown work within BNFL. This report is part of the output from this process of continually improving performance. (author)

  13. COGEMA, fueling the nuclear power industry

    International Nuclear Information System (INIS)

    Ferre, Isabelle; Modigliani, Sylvie

    1993-01-01

    On June 29, for the first time, Cogema's name has appeared on television screens as part of an advertising campaign which will also include the print media. The campaign is the culmination of a program requested by a vast majority of Cogema personnel. The kick-off of this campaign marks a new direction in communications for Cogema, one designed to widen the reach of its reputation and to build a positive image of the Group in the eyes of the public. The publics is not familiar with Cogema now. Our domestic and international achievements and our technical and human capabilities are rarely mentioned by the media. Cogema decided to take action and to make ourselves known, as would any other commercial company operating in a competitive environment, confident of our capabilities and in our future prospects for growth. We want the public to know about our company's strengths, so that they may contribute the building of Cogema's future

  14. COGEMA, fueling the nuclear power industry

    Energy Technology Data Exchange (ETDEWEB)

    Ferre, Isabelle; Modigliani, Sylvie [COGEMA, Communication Division (France); and others

    1993-07-01

    On June 29, for the first time, Cogema's name has appeared on television screens as part of an advertising campaign which will also include the print media. The campaign is the culmination of a program requested by a vast majority of Cogema personnel. The kick-off of this campaign marks a new direction in communications for Cogema, one designed to widen the reach of its reputation and to build a positive image of the Group in the eyes of the public. The publics is not familiar with Cogema now. Our domestic and international achievements and our technical and human capabilities are rarely mentioned by the media. Cogema decided to take action and to make ourselves known, as would any other commercial company operating in a competitive environment, confident of our capabilities and in our future prospects for growth. We want the public to know about our company's strengths, so that they may contribute the building of Cogema's future.

  15. 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

  16. COGEMA gives communication a new impetus: transparency to conduct a new dialog

    International Nuclear Information System (INIS)

    Graffin, K.

    2000-01-01

    COGEMA launched in November 1999 a mass public communication campaign and created an Internet site equipped with cameras (web-cams) to make everyone familiar with the COGEMA plant at La Hague. This system is designed to serve as a communication policy that is resolutely open and attentive to French public concerns. The campaign includes TV commercials and press ads. The underlying principle is to work on issues that have made the news. The televised system includes two films shot at La Hague. The first, lasting 90 seconds, consists of interviews and testimonies of employees who represent the professional and human diversity of the plant. The second, in 45-second format, presents the questions to which public opinion wants answers. To ensure that everyone obtains all the answers to their questions, the TV spots and press ads refer to the web-site: www.cogemalahague.fr. Cybemauts can witness live, by means of a dozen web-cams, what actually happens in different places at COGEMA La Hague: general view of the site, spent fuel unloading installations, storage ponds, Valognes rail terminal, etc. The gist of this first step in the new dialog that COGEMA wants to establish with public opinion is to get beyond irrational fears through transparency, and to show that COGEMA's men and women are fully responsible and determined to contribute actively to the information of the public at large. (authors)

  17. The influence of size of plant upon reprocessing costs

    International Nuclear Information System (INIS)

    1978-10-01

    This paper reviews recent published estimates for capital and operating costs of reprocessing plants in an attempt to establish a relative variation of unit reprocessing costs with plant design capacity and load factor. It is concluded that capital costs follow the well established ''rule of thumb'' for chemical plants in being proportional to (design capacity)sup(2/3). Operating costs vary significantly with variation in labour costs. Unit reprocessing costs are presented as a function of plant design capacity, load factor and method of financing

  18. Actinides exposure: review of Ca-DTPA injections inside Cea-Cogema plants; Exposition aux actinides: bilan des injections de Ca-DTPA dans les centres CEA-Cogema

    Energy Technology Data Exchange (ETDEWEB)

    Grappin, L.; Berard, P.; Beau, P.; Carbone, L.; Castagnet, X.; Courtay, C.; Le Goff, J.P.; Menetrier, F.; Neron, M.; Piechowski, J. [CEA Cadarache, Dir. de l' Energie Nucleaire, Dept. de Soutien en surete et securite, Sev. de Sante au Travail, 13 - Saint-Paul-lez-Durance (France)

    2006-07-01

    Ca-DTPA has been used for medical treatment of plutonium and americium contaminations in the CEA and COGEMA plants from 1970 to 2003. This report is a survey of the injections administered of Ca-DTPA as a chelating molecule. This report will be a part of the AMM process for Ca-DTPA by intravenous administration submitted by the Central Pharmacy of the french Army. Out of 1158 injections administered to 469 persons, 548 events of possible or confirmed contaminations were reported. These employees were followed by occupational physicians according to the current regulations. The first part of the report is a synthesis of the most recent findings. Due to its short biological period and its limited action in the blood, Ca-DTPA does not chelate with plutonium and americium as soon as these elements are deposited in the target organs. It justifies an early treatment, even in cases of suspected contamination followed by additional injections if necessary. The second part presents data concerning these 1158 injections (way of contamination, posology, adverse effects...). These incidents took place at work, were most often minor, not requiring follow-up treatment. A study concerning the effectiveness of the product was done on a group of people having received 5 or more injections. These results were compared with effectiveness estimated from theoretical basis. Posologies and therapeutic schemes were proposed based on these observations. Additional studies are needed to confirm these findings. This document is the first synthesis in this field. It is the result of a collective work having mobilized the occupational medicine departments, the laboratories of CEA and COGEMA and a working group CEA-COGEMA-SPRA. (authors)

  19. Evaluation on maintenance technology developed in Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Yamamura, Osamu

    2008-01-01

    Tokai reprocessing plant (TRP) has been processing 1,140 tons of spent fuels, including 29tons of Fugen MOX fuels, since the beginning of its active operation in Sept.1977. For 30 years operation of TRP, many technological problems have been overcome to obtain the stable and reliable operation. This knowledge of maintenance technology could contribute to the safety and stable operation of Rokkasho reprocessing plant (RRP), as well as to the design and construction of the next reprocessing plant. (author)

  20. 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)

  1. EURATOM safeguards. Safeguards verifications in reprocessing plants

    International Nuclear Information System (INIS)

    Heppleston, M.

    1999-01-01

    This paper provides a brief historical view of the legal basis for EURATOM. The specific application of safeguards to large scale reprocessing plants, from the theoretical model to the practical application of inspection is considered. The challenge to adequately safeguard major commercial reprocessing facilities has led to many novel approaches being developed. These lessons will also benefit other safeguard projects as a result. Good cooperation between the operator and regulator is essential for the satisfactory installation of adequate safeguard controls. The use of modern data processing technology combined with other diverse monitoring techniques has shown that a major industrial scale reprocessing plant can be controlled under international safeguards to provide a high level of assurance [ru

  2. COGEMA's national advertising campaign concerning nuclear fuel recycling

    International Nuclear Information System (INIS)

    Gallot, Christine

    1999-01-01

    Goals of COGEMA's advertising campaign concerning nuclear fuel recycling are to: speak out in an area where COGEMA has legitimacy and is expected; and to take part in the discussion to support and defend an activity that is important for COGEMA. Targets are: back up opinion relays by reaching the general public; and back COGEMA personnel. The advertising strategy can be defined as follows: what is recommended for other industries (sorting and then recycling) is COGEMA's practice for spent fuel, with very significant advantages for the community in terms of economy and ecology

  3. 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

  4. 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)

  5. The Cogema Group and the sustainable development; Le groupe Cogema et le developpement durable

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This document presents the COGEMA Group commitment to sustainable development. Through this commitment, COGEMA is pursuing a policy of ''global performance'' allying economic progress, social progress and protection of the environment, in all its activities. This report points out the many contributions that COGEMA activities make to sustainable development: monitoring of the environment and of releases from its facilities; progress in Research and Development (treatment of liquid and gas effluents, optimized recycling of spent nuclear materials and reduction of their volume, etc.); certification; support for local economic development in the areas around the Group sites, not only in France, but also abroad, as at the mines in Canada and Niger; a strong policy of openness and transparency in its nuclear activities and ongoing dialogue with NGO. The document lays the bases for a number of indicators that can be used as of next year to measure the Group contribution to meeting the challenges of sustainable development. More-detailed statistical data are also presented in the annual environmental reports from the industrial sites in the COGEMA Group. (A.L.B.)

  6. 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)

  7. Multipurpose simulator ''MR TRIOS'' for reprocessing plant

    International Nuclear Information System (INIS)

    Mitsui, Takeshi; Uehara, Shigeru; Takata, Hideo; Kamishima, Naoyuki

    1993-01-01

    MHI (Mitsubishi Heavy Industries) has developed MR TRIOS (Mitsubishi Reprocessing plant TRansient simulation code for Integrated process for Operation Support), the realtime dynamic simulator, for multipurpose use to support the Reprocessing Plant operation in various aspects. MR TRIOS integrates the Simulation Models of the unit process in a Reprocessing Plant, including Shearing, Dissolution, NOx absorption, Accountability and Adjustment and Co-decontamination process, where each Simulation Model has two kinds of models: Process and Control System. MR TRIOS can simulate the process behavior of the unit process in an integrated manner as well as independently. It is supported by MR CONTROL, the simulator control program developed by MHI. From MR TRIOS one can obtain real-time process values, such as temperature, pressure, density, flow rate, and concentration of nuclides, enabling the evaluation of the process dynamic characteristics under various operating conditions. MR TRIOS has proved to be an effective tool for the comprehensive study of the process and system dynamics, for operation technique improvements and for training

  8. Contamination of incinerator at Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Takahashi, Mutsuo

    1994-01-01

    Originally, at Tokai Reprocessing Plant an incinerator was provided in the auxiliary active facility(waste treatment building). This incinerator had treated low level solid wastes generated every facilities in the Tokai Reprocessing Plant since 1974 and stopped the operation in March 1992 because of degeneration. The radioactivity inventory and distribution was evaluated to break up incinerator, auxiliary apparatuses(bag filter, air scrubbing tower, etc.), connecting pipes and off-gas ducts. This report deals with the results of contamination survey of incinerator and auxiliary apparatuses. (author)

  9. Occupational dose at Rokkasho reprocessing plant (RRP)

    International Nuclear Information System (INIS)

    Takashima, F.; Taguchi, R.; Kano, M.; Moriyama, T.; Ogaki, K.; Noda, K.

    2008-01-01

    In Japan, Rokkasho Reprocessing Plant (RRP) is going to start the operation in service as the first large-scale commercial reprocessing plant of spent fuels that has annual reprocessing quantity of 800tU pr in maximum. The occupational external exposure is controlled for the purpose of keeping dose as low as reasonably achievable, and it is monitored by the personal dosimeter. On the other hand, the occupational internal exposure is controlled for the purpose of preventing, and it is monitored by the periodical evaluation of internal dose from the radioactive concentration in air of workplace. The individual doses of radiation workers are less than the dose limits in the statute and our lower management values enough. Dose data will be stored continuously and the rational management method will be examined. (author)

  10. 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.)

  11. Nondestructive assay measurements applied to reprocessing plants

    International Nuclear Information System (INIS)

    Ruhter, Wayne D.; Lee, R. Stephen; Ottmar, Herbert; Guardini, Sergio

    1999-01-01

    Nondestructive assay for reprocessing plants relies on passive gamma-ray spectrometry for plutonium isotopic and plutonium mass values of medium-to-low-density samples and holdup deposits; on active x-ray fluorescence and densitometry techniques for uranium and plutonium concentrations in solutions; on calorimetry for plutonium mass in product; and passive neutron techniques for plutonium mass in spent fuel, product, and waste. This paper will describe the radiation-based nondestructive assay techniques used to perform materials accounting measurements. The paper will also discuss nondestructive assay measurements used in inspections of reprocessing plants [ru

  12. 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)

  13. 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

  14. 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

  15. Development of exhaust air filters for reprocessing plants

    International Nuclear Information System (INIS)

    Furrer, J.; Kaempffer, R.; Jannakos, K.; Apenberg, W.

    1975-01-01

    Investigations of the iodine loading capacity of highly impregnated iodine sorption material (AC 6,120/H 1 ) for the GWA-filters (GWA: reprocessing plant for 1,500 metric tons per year of uranium) have been continued for low NO 2 -contents of the simulated dissolver offgas from GWA. When fully loading AC 6,120/H 1 , a conversion to silver iodides of Ag + of the impregnation of about 80% was reached in experiments with 1% NO 2 in the carrier gas. Despite the consumption of a substantial portion of the impregnation removal efficiencies > 99.99% were measured for a bed depth corresponding to a GWA filter stage. The test facility allowing to examine the behavior and the capacity of the AC 6,120/H 1 iodine sorption material under actual conditions at SAP Marcoule (reprocessing plant) has been completed except for installation in the reprocessing plant. (orig.) [de

  16. The unrivalled expertise for Pu recycling

    International Nuclear Information System (INIS)

    Fournier, W.; Pouilloux, M.

    1997-01-01

    Relying on the outstanding performances of the reprocessing facilities and the growing fabrication facilities, the in-reactor Pu recycling program in France and in other European countries is steadily implemented and has reached full-scale industrial operation. The RCR strategy -Reprocessing, Conditioning and Recycling- developed by COGEMA is now a well proven industrial reality. In 1997, plutonium recycling through MOX fuel is a mature industry, with successful operational experience and large-scale fabrication plants. In this field, COGEMA is the main actor, on operating simultaneously three complete multidesign fuel production plants: MELOX plant (in Marcoule), CADARACHE plant and DESSEL plant (in Belgium). Present MOX production capacity available to COGEMA fits 175 tHM per year and will be extended to reach about 325 tHM in the year 2000, that will represent 75% of the total MOX fabrication capacity in Europe. The industrial mastery and the high production level in MOX production assured by high technology processes confers COGEMA an unrivalled expertise for Pu recycling. This allows COGEMA to be a major actor in Pu-based fuels in the coming second nuclear era with advanced fuel cycles. The paper depicts the steps of the progressive advance of COGEMA to reach the Pu recycling expertise. (author)

  17. Containment/surveillance concepts for international safeguards in reprocessing plants

    International Nuclear Information System (INIS)

    Bleck, M.E.; Cameron, C.P.; Camp, A.L.

    1980-01-01

    This paper examines the potential role of advanced containment/surveillance instrumentation systems for international safeguards in reprocessing plants. Several conceptual systems for the surveillance of containment boundary penetrations in a reference reprocessing plant are described and evaluated. The results of the evaluation aid in understanding the potential capabilities and limitations of containment/surveillance as an international safeguards concept in this type of facility

  18. Feasibility study for adapting ITREC plant to reprocessing LMFBR fuels

    International Nuclear Information System (INIS)

    Moccia, A.; Rolandi, G.

    1976-05-01

    The report evaluates the feasibility of adapting ITREC plant to the reprocessing LMFBR fuels, with the double purpose of: 1) recovering valuable Pu contained in these fuels and recycling it to the fabrication plant; 2) trying, on a pilot scale, the chemical process technology to be applied in a future industrial plant for reprocessing the fuel elements discharged from fast breeder power reactors

  19. Multi-purpose simulator 'MR TRIOS' for reprocessing plant

    International Nuclear Information System (INIS)

    Mitsui, Takeshi; Ariyoshi, Masahiro

    1993-01-01

    MHI(Mitsubishi Heavy Industries, Ltd.) has developed MR TRIOS(Mitsubishi Reprocessing plant TRansient simulator of Integrated process for Operation Support), the realtime dynamic simulator, for multipurpose use to support the Reprocessing Plant operation in various aspects. MR TRIOS integrates the simulation models of the unit process in reprocessing plant, including shearing, dissolution, NO x absorption, accountability and adjustment and co-decontamination process, where each simulation model has two kinds of models, one is Process and the other is Control System. MR TRIOS can simulate the process behavior of the above listed unit process in an integrated manner as well as independently. It is realized by MR CONTROL, the simulator control program developed by MHI. We can get from MR TRIOS the real-time process values, such as temperature, pressure, density, flow rate and concentration of eminent nuclides etc. enabling the evaluation of the process dynamic characteristics under various operating conditions. MR TRIOS has been proved to be an effective tool for the comprehensive study of the process and system dynamics, for operation technique improvements and for training. In this report we will show the introductory outline of multi-purpose simulator 'MR TRIOS' for reprocessing plant and also show the possibility to clarify the fundamental technical requirement to realize the effective material accountancy measure for Head-end Area. (author)

  20. 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

  1. 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.)

  2. Criticality safety evaluation in Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Shirai, Nobutoshi; Nakajima, Masayoshi; Takaya, Akikazu; Ohnuma, Hideyuki; Shirouzu, Hidetomo; Hayashi, Shinichiro; Yoshikawa, Koji; Suto, Toshiyuki

    2000-04-01

    Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 'Criticality safety of single unit' in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units. (author)

  3. Current applications of actinide-only burn-up credit within the Cogema group and R and D programme to take fission products into account

    International Nuclear Information System (INIS)

    Toubon, H.; Guillou, E.; Cousinou, P.; Barbry, F.; Grouiller, J.P.; Bignan, G.

    2001-01-01

    Burn-up credit can be defined as making allowance for absorbent radioactive isotopes in criticality studies, in order to optimise safety margins and avoid over-engineering of nuclear facilities. As far as the COGEMA Group is concerned, the three fields in which burn-up credit proves to be an advantage are the transport of spent fuel assemblies, their interim storage in spent fuel pools and reprocessing. In the case of transport, burn-up credit means that cask size do not need to be altered, despite an increase in the initial enrichment of the fuel assemblies. Burn-up credit also makes it possible to offer new cask designs with higher capacity. Burn-up credit means that fuel assemblies with a higher initial enrichment can be put into interim storage in existing facilities and opens the way to the possibility of more compact ones. As far as reprocessing is concerned, burn-up credit makes it possible to keep up current production rates, despite an increase in the initial enrichment of the fuel assemblies being reprocessed. In collaboration with the French Atomic Energy Commission and the Institute for Nuclear Safety and Protection, the COGEMA Group is participating in an extensive experimental programme and working to qualify criticality and fuel depletion computer codes. The research programme currently underway should mean that by 2003, allowance will be made for fission products in criticality safety analysis

  4. Current applications of actinide-only burn-up credit within the Cogema group and R and D programme to take fission products into account

    Energy Technology Data Exchange (ETDEWEB)

    Toubon, H. [Cogema, 78 - Saint Quentin en Yvelines (France); Guillou, E. [Cogema Etablissement de la Hague, D/SQ/SMT, 50 - Beaumont Hague (France); Cousinou, P. [CEA Fontenay aux Roses, Inst. de Protection et de Surete Nucleaire, 92 (France); Barbry, F. [CEA Valduc, Inst. de Protection et de Surete Nucleaire, 21 - Is sur Tille (France); Grouiller, J.P.; Bignan, G. [CEA Cadarache, 13 - Saint Paul lez Durance (France)

    2001-07-01

    Burn-up credit can be defined as making allowance for absorbent radioactive isotopes in criticality studies, in order to optimise safety margins and avoid over-engineering of nuclear facilities. As far as the COGEMA Group is concerned, the three fields in which burn-up credit proves to be an advantage are the transport of spent fuel assemblies, their interim storage in spent fuel pools and reprocessing. In the case of transport, burn-up credit means that cask size do not need to be altered, despite an increase in the initial enrichment of the fuel assemblies. Burn-up credit also makes it possible to offer new cask designs with higher capacity. Burn-up credit means that fuel assemblies with a higher initial enrichment can be put into interim storage in existing facilities and opens the way to the possibility of more compact ones. As far as reprocessing is concerned, burn-up credit makes it possible to keep up current production rates, despite an increase in the initial enrichment of the fuel assemblies being reprocessed. In collaboration with the French Atomic Energy Commission and the Institute for Nuclear Safety and Protection, the COGEMA Group is participating in an extensive experimental programme and working to qualify criticality and fuel depletion computer codes. The research programme currently underway should mean that by 2003, allowance will be made for fission products in criticality safety analysis.

  5. Tritium control in reprocessing plants

    International Nuclear Information System (INIS)

    Goumondy, J.P.; Miquel, P.

    1977-01-01

    There is a danger that the T which is formed in water reactors will prove detrimental to the environment over the next few years, and studies have been undertaken to develop techniques to contain and process it where possible. In order to retain T, which is present largely in the fuel and on the possible to adapt for use in the conventional design of reprocessing plant. In this process T is maintained in the form of an aqueous solution in the high-active area of the plant. Control is achieved by restricting as far as possible the ingress of non-tritiated water into this area, and by setting up a tritiated water barrier at the first U and Pu extraction stage, stripping the tritium-containing solvent at that point with ordinary water. In this way the T can be extracted in a small volume of water with a view to intermediate storage, disposal at sea additional processing to remove the T from the water. Experiments carried out so far have demonstrated the effectiveness of the T barrier and have shown what equipment would be required for the application of the process in new reprocessing plants. (orig.) [de

  6. 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

  7. 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)

  8. COGEMA/TRANSNUCLEAIRE's experience with burnup credit

    International Nuclear Information System (INIS)

    Chanzy, Y.; Guillou, E.

    1998-01-01

    Facing a continuous increase in the fuel enrichments, COGEMA and TRANSNUCLEAIRE have implemented step by step a burnup credit programme to improve the capacity of their equipment without major physical modification. Many authorizations have been granted by the French competent authority in wet storage, reprocessing and transport since 1981. As concerns transport, numerous authorizations have been validated by foreign competent authorities. Up to now, those authorizations are restricted to PWR Fuel type assemblies made of enriched uranium. The characterization of the irradiated fuel and the reactivity of the systems are evaluated by calculations performed with well qualified French codes developed by the CEA (French Atomic Energy Commission): CESAR as a depletion code and APPOLO-MORET as a criticality code. The authorizations are based on the assurance that the burnup considered is met on the least irradiated part of the fuel assemblies. Besides, the most reactive configuration is calculated and the burnup credit is restricted to major actinides only. This conservative approach allows not to take credit for any axial profile. On the operational side, the procedures have been reevaluated to avoid misloadings and a burnup verification is made before transport, storage and reprocessing. Depending on the level of burnup credit, it consists of a qualitative (go/no-go) verification or of a quantitative measurement. Thus the use of burnup credit is now a common practice in France and Germany and new improvements are still in progress: extended qualifications of the codes are made to enable the use of six selected fission products in the criticality evaluations. (author)

  9. 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

  10. Cost estimation of the decommissioning of nuclear fuel cycle plants

    International Nuclear Information System (INIS)

    Barbe, A.; Pech, R.

    1991-01-01

    Most studies conducted to date on the cost of decommissioning nuclear facilities pertain to reactors. Few such studies have been performed on the cost of decommissioning nuclear fuel cycle plants, particularly spent fuel reprocessing plants. Present operators of these plants nevertheless need to assess such costs, at least in order to include the related expenses in their short-, medium- or long-term projections. They also need to determine now, for example, suitable production costs that the plant owners will have to propose to their customers. Unlike nuclear reactors for which a series effect is involved (PWRs, BWRs, etc.) and where radioactivity is relatively concentrated, industrial-scale reprocessing plants are large, complex installations for which decommissioning is a long and costly operation that requires a special approach. Faced with this problem, Cogema, the owner and operator of the La Hague and Marcoule reprocessing plants in France, called on SGN to assess the total decommissioning costs for its plants. This assessment led SGN to development by SGN engineers of a novel methodology and a computerized calculation model described below. The resulting methodology and model are applicable to other complex nuclear facilities besides reprocessing plants, such as laboratories and nuclear auxiliaries of reactor cores. (author)

  11. ALPHA WASTE MINIMIZATION IN TERMS OF VOLUME AND RADIOACTIVITY AT COGEMA'S MELOX AND LA HAGUE PLANTS

    International Nuclear Information System (INIS)

    ARSLAN, M.; DUMONT, J.C.; LONDRES, V.; PONCELET, F.J.

    2003-01-01

    This paper describes the management of alpha waste that cannot be stored in surface repositories under current French regulations. The aim of the paper is to provide an overview of COGEMA's Integrated Waste Management Strategy. The topics discussed include primary waste minimization, from facility design to operating feedback; primary waste management by the plant operator, including waste characterization; waste treatment options that led to building waste treatment industrial facilities for plutonium decontamination, compaction and cement solidification; and optimization of industrial tools, which is strongly influenced by safety and financial considerations

  12. Reliability of the fuel identification procedure used by COGEMA during cask loading for shipment to LA HAGUE

    International Nuclear Information System (INIS)

    Pretesacque, P.; Eid, M.; Zachar, M.

    1993-01-01

    This study has been carried out to demonstrate the reliability of the system of the spent fuel identification used by COGEMA and NTL prior to shipment to the reprocessing plant of La Hague. This was a prerequisite for the French competent authority to accept the 'burnup credit' assumption in the criticality assessment of spent fuel packages. The probability to load a non-irradiated and non-specified fuel assembly was considered as acceptable if our identification and irradiation status measurement procedures were used. Furthermore, the task analysis enabled us to improve the working conditions at reactor sites, the quality of the working documentation, and consequently to improve the reliability of the system. The NTL experience of transporting to La Hague, as consignor, more than 10,000 fuel assemblies since the date of implementation of our system in 1984 without any non-conformance on fuel identification, validated the formalism of this study as well as our assumptions on basic events probabilities. (J.P.N.)

  13. 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

  14. 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.

  15. Treatment of actinide exposures: a review of Ca-DTPA injections inside CEA-COGEMA plants

    International Nuclear Information System (INIS)

    Grappin, Louise; Berard, Philippe; Carbone, Lise; Le Goff, Jean-Pierre; Neron, Marie-Odile; Menetrier, Florence; Courtay, Catherine; Castagnet, Xavier; Piechowski, Jean

    2007-01-01

    Calcium diethylenetriamine pent-acetate (Ca-DTPA) has been used for medical treatment of plutonium and americium contaminations in the CEA and COGEMA plants from 1970 to 2003. This paper is a survey of the injections Ca-DTPA administered as a chelating molecule and it will be a part of the authorization process for Ca-DTPA by intravenous administration. Out of 1158 injections administered to 469 persons, 548 events of possible or confirmed contamination were reported. These employees were followed by occupational physicians according to the current French regulations. These incidents took place at work, were most often minor, not requiring follow-up treatment. The authors present (1) a synthesis of the most recent findings. Due to its short biological half-time and its limited action in the blood, Ca-DTPA does not chelate with plutonium and americium as soon as these elements are deposited in the target organs. It justifies an early treatment, even in cases of suspected contamination followed by additional injections if necessary (2) data concerning these 1158 injections (route of contamination, dosage, adverse effects, etc.) The authors also investigated a study on the efficacy of the product on a group of persons having received five or more injections. These results were compared with the efficacy estimated theoretically. Dosages and therapeutic schemes were proposed based on these observations. This synthesis is the result of a collective work having mobilized the occupational medicine departments, the medical laboratories inside a working group CEA-COGEMA-SPRA. (authors)

  16. 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)

  17. Study on reprocessing plant during transition period from LWR to FBR

    International Nuclear Information System (INIS)

    Shimada, Takashi; Matsui, Minefumi; Nishimura, Masashi; Ishida, Yasuhiro; Mori, Yukihide; Kuroda, Kazuhiko

    2011-01-01

    We have proposed a concept of a reprocessing plant suitable for the transition period from the light water reactors (LWRs) to the fast breeder reactors (FBRs) by making comparison of two plant concepts: (1) Independent Plant which processes LWR fuel and FBR fuel in separately constructed lines and (2) Modularized Plant which processes LWR fuel and FBR fuel in a same line. We made construction plans based on the reference power generation plan, and evaluated the Pu supply capability using the power generation plan as an indicator of plant operation flexibility. In general, a margin of processing capacity increases the Pu supply capability. The margin of the Modularized Plant necessary to obtain equivalent Pu supply capability is smaller than that of the Independent Plant. Also the margin of the Independent Plant results in decrease in the plant utilization factor. But the margin of the Modularized Plant results in little decrease in the plant utilization factor, because the Modularized Plant can address the types of reprocessing fuel to adjust to Pu demand and processing capacity. Therefore, the Modularized Plant has a greater potential for the reprocessing plants during transition period. (author)

  18. Mechanism of 232U production in MTR fuel evolution of activity in reprocessed uranium

    International Nuclear Information System (INIS)

    Harbonnier, G.; Lelievre, B.; Fanjas, Y.; Naccache, S.J.P.

    1993-01-01

    The use of reprocessed uranium for research reactor fuel fabrication implies to keep operators safe from the hard gamma rays emitted by 232 U daughter products. CERCA has carried out, with the help of French CEA and COGEMA, a detailed study to determine the evolution of the radiation dose rate associated with the use of this material. (author)

  19. General Atomic reprocessing pilot plant: description and results of initial testing

    International Nuclear Information System (INIS)

    1977-12-01

    In June 1976 General Atomic completed the construction of a reprocessing head-end cold pilot plant. In the year since then, each system within the head end has been used for experiments which have qualified the designs. This report describes the equipment in the plant and summarizes the results of the initial phase of reprocessing testing

  20. New high density MTR fuel. The CEA-CERCA-COGEMA development program

    International Nuclear Information System (INIS)

    Languille, A.; Durand, J.P.; Gay, A.

    1999-01-01

    The development of a new generation of LEU, high in density and with reprocessing capacities MTR fuel, is a key issue to provide reactor operators with a smooth operation which is necessary for a long term development of Nuclear Energy. In the RRFM'98 meeting, a joint contribution of CEA, CERCA and COGEMA presented a technical classification of the potential candidates uranium alloys. In this paper this MTR working group presents the development program of a new high density fuel. This program is composed of three main steps: Basic Data analysis and collection, Plate Tests (Irradiation and Post Irradiation Examinations) and Lead Test Assemblies (Irradiation and Post Irradiation Examinations). The goal to be reached is to make this new fuel available before the end of the present US return policy. (author)

  1. Analysis of the options - rationale for servomanipulator maintenance in future reprocessing plants

    International Nuclear Information System (INIS)

    Herndon, J.N.; Hamel, W.R.

    1984-04-01

    The currently available maintenance systems which can be applied, in various combinations, to large-volume in-cell maintenance operations are: (1) contact, (2) overhead cranes, (3) power manipulators, (4) mechanical master/slave manipulators, and (5) servomanipulators. The requirements for reprocessing plant maintenance are reviewed, and the capabilities of remote maintenance systems are described. A basic trade-off analysis of these remote maintenance systems considering reprocessing plant requirements is given. Justification is given for selecting the overhead crane/servomanipulator-based maintenance concept as the option most desirable for future large reprocessing plant maintenance. 23 references, 6 tables

  2. Safety problems in fuel reprocessing plants

    International Nuclear Information System (INIS)

    Amaury, P.; Jouannaud, C.; Niezborala, F.

    1979-01-01

    The document first situates the reprocessing in the fuel cycle as a whole. It shows that a large reprocessing plant serves a significant number of reactors (50 for a plant of 1500 tonnes per annum). It then assesses the potential risks with respect to the environment as well as with respect to the operating personnel. The amounts of radioactive matter handled are very significant and their easily dispersible physical form represents very important risks. But the low potential energy likely to bring about this dispersion and the very severe and plentiful confinement arrangements are such that the radioactive risks are very small, both with respect to the environment and the operating personnel. The problems of the interventions for maintenance or repairs are mentioned. The intervention techniques in a radioactive environment are perfected, but they represent the main causes of operating personnel irradiation. The design principle applied in the new plants take this fact into account, involving a very significant effort to improve the reliability of the equipment and ensuring the provision of devices enabling the failing components to be replaced without causing irradiation of the personnel [fr

  3. Cogema and the environment. Environmental policy. The Cogema group in the environment service

    International Nuclear Information System (INIS)

    1997-01-01

    This document presents the organization of the environmental policy at Cogema facilities. The first part presents the environmental policy of the group: integration of environment management at all levels, reduction of effluents and control of their environmental impact, integrating environment protection at the design stage of facilities, quality and improvement policy, expenses devoted to environment protection (investments, R and D, funds), public information. The second part concerns the transfer of Cogema's know-how in environmental engineering towards other industrial sectors: radioactivity measurements, mine and quarry sites rehabilitation, industrial wastes and effluents processing, decontamination and rehabilitation of ancient polluted industrial sites, foreign activities (rehabilitation of US-DOE military sites, aid to Eastern countries. (J.S.)

  4. The Cogema Group and the sustainable development

    International Nuclear Information System (INIS)

    2002-01-01

    This document presents the COGEMA Group commitment to sustainable development. Through this commitment, COGEMA is pursuing a policy of ''global performance'' allying economic progress, social progress and protection of the environment, in all its activities. This report points out the many contributions that COGEMA activities make to sustainable development: monitoring of the environment and of releases from its facilities; progress in Research and Development (treatment of liquid and gas effluents, optimized recycling of spent nuclear materials and reduction of their volume, etc.); certification; support for local economic development in the areas around the Group sites, not only in France, but also abroad, as at the mines in Canada and Niger; a strong policy of openness and transparency in its nuclear activities and ongoing dialogue with NGO. The document lays the bases for a number of indicators that can be used as of next year to measure the Group contribution to meeting the challenges of sustainable development. More-detailed statistical data are also presented in the annual environmental reports from the industrial sites in the COGEMA Group. (A.L.B.)

  5. Impact of the Tokai reprocessing plant on the workers and on the surrounding environment

    International Nuclear Information System (INIS)

    Tago, I.

    1996-01-01

    The Tokai reprocessing plant began operation in September 1977 to establish oxide fuel reprocessing technology in Japan. Its designed capacity is about 0.7 metric tons of uranium per day. This report gives an example of the evaluation of the health and environmental aspects of a reprocessing plant. (author)

  6. Remote handling in reprocessing plants

    International Nuclear Information System (INIS)

    Streiff, G.

    1984-01-01

    Remote control will be the rule for maintenance in hot cells of future spent fuel reprocessing plants because of the radioactivity level. New handling equipments will be developed and intervention principles defined. Existing materials, recommendations for use and new manipulators are found in the PMDS' documentation. It is also a help in the choice and use of intervention means and a guide for the user [fr

  7. 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

  8. Experience of iodine removal in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Kikuchi, K.; Komori, Y.; Takeda, K.

    1985-01-01

    In the Tokai reprocessing plant about 170 ton of irradiated fuels have been processed since the beginning of hot operations in 1977. There was no effective equipment for iodine removal from the off-gas except for alkaline scrubbers when the plant construction was completed. In order to reduce the iodine discharge to the atmosphere, silver-exchanged zeolite (AgX) filters were installed additionally in 1979 and 1980, and they have been effective. However, those decontamination factors (DFs) were not as high as expected, and increasing the reprocessing amount of spent fuels it became necessary to lower the iodine discharge to the atmosphere. Therefore, other iodine removal equipment is planned to be installed in the plant. Concerning these investigations and development of iodine removal techniques, the iodine concentration of actual off-gases was measured and useful data were obtained

  9. 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

  10. General Atomic Reprocessing Pilot Plant: engineering-scale dissolution system description

    International Nuclear Information System (INIS)

    Yip, H.H.

    1979-04-01

    In February 1978, a dissolver-centrifuge system was added to the cold reprocessing pilot plant at General Atomic Company, which completed the installation of an HTGR fuel head-end reprocessing pilot plant. This report describes the engineering-scale equipment in the pilot plant and summarizes the design features derived from development work performed in the last few years. The dissolver operating cycles for both thorium containing BISO and uranium containinng WAR fissile fuels are included. A continuous vertical centrifuge is used to clarify the resultant dissolver product solution. Process instrumentation and controls for the system reflect design philosophy suitable for remote operation

  11. 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

  12. 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

  13. 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

  14. Status of the decommissioning program of the Eurochemic reprocessing plant

    International Nuclear Information System (INIS)

    Detilleux, E.J.

    1976-01-01

    Reprocessing operations at the Eurochemic demonstration plant stopped in December 1974, after 8 years of operation. Immediately thereafter, cleaning and decontamination were begun as the first phase of the decommissioning program. The facility and reprocessing program are described to indicate the magnitude of the problem, and the requirements of the local authorities are reviewed. The technical decommissioning program consists of several phases: (1) plant cleaning and rinsing, (2) establishment of the final fissile-material balance, (3) plant decontamination for access to process equipment, (4) equipment dismantling, and (5) conditioning and storage of newly generated wastes. The two first phases have been completed, and the third one is nearing completion. Some dismantling has been performed, including the plutonium dioxide production unit. Waste-conditioning and surface-storage facilities have been built to meet the dismantling requirements. Since reprocessing may be resumed in the future, decontamination has been performed with ''smooth'' reagents to limit corrosion and dismantling has been limited to subfacilities

  15. Visitor Centre at Nuclear Facility Site of La Hague

    International Nuclear Information System (INIS)

    Marie-Sainte, E.; Jozeau-Marigne, M.

    1993-01-01

    Cogema, a french fuel reprocessing plant, reprocesses spent fuel issued from french nuclear power plants, but also japanese, german, swiss, belgian, dutch ones. Since 1976, Cogema has reprocessed more than 5000 tons of spent fuel, about 85% of spent fuel in the world with a market economy. Since 1976, Cogema has a department which is in charge of visits of the firm. Five persons, communication assistants in charge of relations with the public organize all year long, visits on the site. A visitor centre has been built in 1974 by the CEA (Commissariat a l'Energie Atomique). It is opened to the public six months by year, from 1st of april until 30 of september, seven days a week. The visitor centre is situated out of the factory enclosure, so everybody can come in without formality. Entrance is free. Four floors to explain what is fuel cycle, reprocessing, environment surveillance, radiation protection, dosimetry, panels with elementary notions of nuclear physics (atom, fission, reactor working), use of atom in medicine and non nuclear industry, a whole of general information related to nuclear historical record, fuel cycle, and particularly activities of La Hague

  16. 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.)

  17. IAEA verification of materials accounting in commercial reprocessing plants

    International Nuclear Information System (INIS)

    Gutmacher, R.G.; Hakkila, E.A.

    1987-01-01

    The reprocessing plants currently under International Atomic Energy Agency (IAEA) safeguards have design capacities up to 210 tonnes of heavy metal per year. All of the plants use conventional materials accounting for safeguards. However, several larger commercial reprocessing plants are being designed with capacities of 350 to 1200 tonnes of heavy metal per year. It is likely that many of these plants, as well as some of the existing smaller ones, will adopt near-real-time materials accounting. The major effect of the combination of larger plants and near-real-time accounting on IAEA safeguards will be the demand for greater timeliness of verification. Continuous inspector presence may be required, as well as more on-site measurements by the inspector. In this paper, the authors review what needs to be verified, as well as current inspector activities in the process area. The bulk of the paper describes rapid, easy-to-use measurement techniques and instruments that may be applied to on-site verification measurements

  18. 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

  19. 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.)

  20. Report of the LASCAR forum: Large scale reprocessing plant safeguards

    International Nuclear Information System (INIS)

    1992-01-01

    This report has been prepared to provide information on the studies which were carried out from 1988 to 1992 under the auspices of the multinational forum known as Large Scale Reprocessing Plant Safeguards (LASCAR) on safeguards for four large scale reprocessing plants operated or planned to be operated in the 1990s. The report summarizes all of the essential results of these studies. The participants in LASCAR were from France, Germany, Japan, the United Kingdom, the United States of America, the Commission of the European Communities - Euratom, and the International Atomic Energy Agency

  1. Fuel reprocessing plant: No qualitative differences as compared to other sensitive process plants

    International Nuclear Information System (INIS)

    Schweinoch, J.

    1986-01-01

    Nuclear power plants like the fuel reprocessing plant belong to the highly sensitive installations in respect of safety, but involve the same risks qualitatively as liquid-gas plants or chemical plants. Therefore no consequences for basic rights are discernible. The police can take adequate preventive measures. The regulations governing police action provide proper and sufficient warrants. (DG) [de

  2. 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

  3. Pilot and pilot-commercial plants for reprocessing spent fuels of FBR type reactors

    International Nuclear Information System (INIS)

    Shaldaev, V.S.; Sokolova, I.D.

    1988-01-01

    A review of modern state of investigations on the FBR mixed oxide uranium-plutonium fuel reprocessing abroad is given. Great Britain and France occupy the leading place in this field, operating pilot plants of 5 tons a year capacity. Technology of spent fuel reprocessing and specific features of certain stages of the technological process are considered. Projects of pilot and pilot-commercial plants of Great Britain, France, Japan, USA are described. Economic problems of the FBR fuel reprocessing are touched upon

  4. Research and development on air cleaning system of reprocessing plant in Japan

    International Nuclear Information System (INIS)

    Naruki, K.

    1985-01-01

    Present status in Japan of R and D on air cleaning systems, especially of the fuel reprocessing plant is summarized. The description is centered on the R and D and experience of Tokai-reprocessing plant, which covers the plant air cleaning system, effort carried out for decreasing I 2 effluence in the actual vented off-gas, and R and D for recovery of Kr and 3 H. Some experimental results for the evaluation of HEPA filter are also described

  5. 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.)

  6. 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

  7. 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)

  8. 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.)

  9. 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.)

  10. 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)

  11. Intergovernmental action of neighbours against the Wackersdorf reprocessing plant

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    BV Art. 11, para. 2; BBauG section 12 (Federal Building Law). Art.11, para. 2 BV does not require that local development planning for a reprocessing plant should take into consideration the effects on neighbouring municipalities as a result of post-construction activities, in this case the transport of radioactive material via certain routes. Such supra-regional aspects go beyond the planning basis of a local government. These are the headnotes of a decision by the Bavarian Higher Administrative Court (BayVerfGH, 29.4.1987 - Vf. 5 - VII - 86). The issue of the proceedings commenced by a collective action is the question whether an area development plan for the purpose of erecting the Wackersdorf reprocessing plant infringes the constitutional rights of the town of Nuernberg due to the fact that after commissioning of the plant, radioactive material will be transported to and from the plant, and the envisaged route for the transports leads through the urban area. (orig./HP) [de

  12. Simulation of the atmospheric dispersion at local scale in the area of Cogema (la Hague) using PERLE system

    International Nuclear Information System (INIS)

    Sandu, Irina; Lac, Christine

    2003-01-01

    METEO-FRANCE is presently developing a new system named PERLE which permits real time evaluation of atmospheric dispersion at local scale. This system consists in a non-hydrostatic meteorological model at mezo-scale (Meso-NH) and a particular code for the dispersion of the chemically passive pollutants. As a result of several studies performed by DP/SERV/ENV at Meteo-France, two particular codes have been retained for the dispersion module of PERLE: DIFPAR (EDF) and SPRAY (Aria Technologies). In this study, the dispersion at local scale of Kr 85 in the area of the nuclear-wastes reprocessing plant COGEMA (La Hague) has been simulated with the two dispersion models, initialised with the meteorological fields provided by Meso-NH. The simulations concern the most complete sampling campaign of Kr 85 performed in this area on 18th and 19th september 2001. The evaluation the two models performances and of the PERLE system's results for this campaign has been done by using the CTA (Atmospherical Transfer Coefficient) measured values. (authors)

  13. Radiation exposures in reprocessing facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Hayes, G.; Caldwell, R.D.; Hall, R.M.

    1979-01-01

    Two large reprocessing facilities have been operating at the Savannah River Plant since 1955. The plant, which is near Aiken, South Carolina, is operated for the U.S. Department of Energy by the Du Pont Company. The reprocessing facilities have a work force of approximately 1,800. The major processes in the facilities are chemical separations of irradiated material, plutonium finishing, and waste management. This paper presents the annual radiation exposure for the reprocessing work force, particularly during the period 1965 through 1978. It also presents the collective and average individual annual exposures for various occupations including operators, mechanics, electricians, control laboratory technicians, and health physicists. Periodic and repetitive work activities that result in the highest radiation exposures are also described. The assimilation of radionuclides, particularly plutonium, by the work force is reviewed. Methods that have been developed to minimize the exposure of reprocessing personnel are described. The success of these methods is illustrated by experience - there has been no individual worker exposure of greater than 3.1 rems per year and only one plutonium assimilation greater than the maximum permissible body burden during the 24 years of operation of the facilities

  14. Radiation exposures in reprocessing facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Hayes, G.; Caldwell, R.D.; Hall, R.M.

    1979-06-01

    Two large reprocessing facilities have been operating at the Savannah River Plant since 1955. The plant, which is near Aiken, South Carolina, is operated for the US Department of Energy by the Du Pont Company. The reprocessing facilities have a work force of approximately 1,800. The major processes in the facilities are chemical separations of irradiated material, plutonium finishing, and waste management. This paper presents the annual radiation exposure for the reprocessing work force, particularly during the period 1965 through 1978. It also presents the collective and average individual annual exposures for various occupations including operators, mechanics, electricians, control laboratory technicians, and health physicists. Periodic and repetitive work activities that result in the highest radiation exposures are also described. The assimilation of radionuclides, particularly plutonium, by the work force is reviewed. Methods that have been developed to minimize the exposure of reprocessing personnel are described. The success of these methods is illustrated by experience - there has been no individual worker exposure of greater than 3.1 rems per year and only one plutonium assimilation greater than the maximum permissible body burden during the 24 years of operation of the facilities

  15. 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

  16. Summary of the status of the NFS reprocessing plant

    International Nuclear Information System (INIS)

    Clark, J.R.

    The modification program at the West Valley, New York, reprocessing plant is described. The program involves expansion, improving the plant's on-stream factor and reducing the occupational exposures, installing natural phenomena protection, and improving effluent control and waste management. Licencing requirements and their effects on scheduling are discussed. (E.C.B.)

  17. 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

  18. 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.)

  19. 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

  20. National inventory of radioactive wastes; Inventaire national des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    There are in France 1064 sites corresponding to radioactive waste holders that appear in this radioactive waste inventory. We find the eighteen sites of E.D.F. nuclear power plants, The Cogema mine sites, the Cogema reprocessing plants, The Cea storages, the different factories and enterprises of nuclear industry, the sites of non nuclear industry, the Andra centers, decommissioned installations, disposals with low level radioactive wastes, sealed sources distributors, national defence. (N.C.). 16 refs.

  1. National inventory of radioactive wastes

    International Nuclear Information System (INIS)

    1997-01-01

    There are in France 1064 sites corresponding to radioactive waste holders that appear in this radioactive waste inventory. We find the eighteen sites of E.D.F. nuclear power plants, The Cogema mine sites, the Cogema reprocessing plants, The Cea storages, the different factories and enterprises of nuclear industry, the sites of non nuclear industry, the Andra centers, decommissioned installations, disposals with low level radioactive wastes, sealed sources distributors, national defence. (N.C.)

  2. National inventory of radioactive wastes; Inventaire national des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    There are in France 1064 sites corresponding to radioactive waste holders that appear in this radioactive waste inventory. We find the eighteen sites of E.D.F. nuclear power plants, The Cogema mine sites, the Cogema reprocessing plants, The Cea storages, the different factories and enterprises of nuclear industry, the sites of non nuclear industry, the Andra centers, decommissioned installations, disposals with low level radioactive wastes, sealed sources distributors, national defence. (N.C.). 16 refs.

  3. Development of some operations in technological flowsheet for spent VVER fuel reprocessing at a pilot plant

    International Nuclear Information System (INIS)

    Lazarev, L.N.; Galkin, B.Ya; Lyubtsev, R.I.; Romanovskii, V.N.; Velikhov, E.P.

    1981-01-01

    The fuel reprocessing pilot plants for high active materials would permit the study and development or particular processing steps and flowsheet variations; in some cases, these experimental installations realize on a small scale practically all technological chains of large reprocessing plants. Such a fuel reprocessing pilot plant with capacity of 3 kg U/d has been built at V. G. Khlopin Radium Institute. The pilot plant is installed in the hot cell of radiochemical compartment, and is composed of the equipments for fuel element cutting and dissolving, the preparation of feed solution (clarification, correction), extraction reprocessing and the production of uranium, plutonium and neptunium concentrates, the complex processing of liquid and solid wastes and a special unit for gas purification and analysis. In the last few years, a series of experiments have been carried out on the reprocessing of spent VVER fuel. (J.P.N.)

  4. Trends and R and D in France to improve the performance of activity measurements systems for the reprocessing low level wastes

    International Nuclear Information System (INIS)

    Martin Deidier, L.; Silie, Ph.; Huver, M.

    1995-01-01

    In the frame of COGEMA actins to reduce the volume of the reprocessing waste, a new strategy of drumming and incinerating is going to start at LA HAGUE and MARCOULE, for the low level waste planned for surface storage. This strategy depends on the performance improvement of non destructive measurements systems used for the alpha waste evaluation. In this global, closer links between COGEMA, SGN, CEA and EURYSIS MESURE have taken place to define a program in order to obtain up to three years the required performances, using active methods with neutron generator. These developments and tests are carried out on the PROMETHEE R and D facility at CEA-CADARACHE. (authors)

  5. Plan for the civil reprocessing pilot plant of China

    International Nuclear Information System (INIS)

    Wang, D.Y.; Chen, M.

    1987-01-01

    Based on the R and D work, experience on plant operation and site situation, the necessity and feasibility of building a pilot plant for civil reprocessing in China are discussed. The capacity of 100 kg HM/day (LWR) and 3 kg HM/day (MTR) has been proposed. The plant consists of cold testing facility and hot pilot facility. It is expected to complete the pilot plant in 1990's. This paper also describes the purpose, scale, process and equipment of the pilot plant

  6. 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)

  7. Dosimetry optimization at COGEMA-La Hague

    International Nuclear Information System (INIS)

    Kalimbadjian, J.

    2000-01-01

    At the present time, the la Hague site strives to apply international recommendations together with national regulations concerning radiation protection, and especially the respect of limitation and optimization principles. The application of these principles is based on the implementation of a passive dosimetry and an active dosimetry. The monthly passive dosimetry is monitored by means of a photographic dosimetry film, completed with lithium fluorine thermoluminescent film badges. This personal dosimetry common to X, β, γ and neutron radiations is carried out in close relationship between the Radiation Protection Department, the Occupational Medical Department and the staff running the Plant. The application or ALARA's principle as well as that of radiation protection optimization implies to implement a complementary active dosimetry enabling to gain in real time, the personal dosimetry of each intervening person, either they be COGEMA's workers or external companies'. This active dosimetry provides with following information: This preventive dosimetry is based on the knowledge of doses integration in real time and is fitted with alarm thresholds according to the total amount of doses and dose rates. Thresholds on the dose rate are also set relatively to the radiological environment. This knowledge of doses and dose rates allows a stricter management of the works, while analyzing them according to the nature of the work, to the location and to the skills of the intervening people. This dosimetry allows to analyze and optimize doses integration according to the works nature for the whole intervening staff. The la Hague Site has developed an active personal dosimetry system, common to every intervening person, COGEMA or external companies. The DOSICARD was thus elaborated, shaped as an electronic dosimeter fitted with an alarm and a smart card. The access to controlled areas is conditioned to information given by the DOSICARD concerning medical aptitudes and

  8. Solvent management in a reprocessing plant

    International Nuclear Information System (INIS)

    Guillaume, B.; Germain, M.; Puyou, M.; Rouyer, H.

    1987-01-01

    Solvent management in large capacity reprocessing plant is studied to limit production of organic wastes. Chemical processing increases life time of solvent. Low pressure distillation allows the recycling of TBP and diluent at a low activity level. Besides heavy degradation products are eliminated. For the safety the flash point of distillated diluent increases slightly. Tests on an industrial scale started in 1985 and since more than 500 cubic meters were treated [fr

  9. Selective absorption pilot plant for decontamination of fuel reprocessing plant off-gas

    Energy Technology Data Exchange (ETDEWEB)

    Stephenson, M.J.; Eby, R.S.; Huffstetler, V.C.

    1977-10-01

    A fluorocarbon-based selective absorption process for removing krypton-85, carbon-14, and radon-222 from the off-gas of conventional light water and advanced reactor fuel reprocessing plants is being developed at the Oak Ridge Gaseous Diffusion Plant in conjunction with fuel recycle work at the Oak Ridge National Laboratory and at the Savannah River Laboratory. The process is characterized by an especially high tolerance for many other reprocessing plant off-gas components. This report presents detailed drawings and descriptions of the second generation development pilot plant as it has evolved after three years of operation. The test facility is designed on the basis of removing 99% of the feed gas krypton and 99.9% of the carbon and radon, and can handle a nominal 15 scfm (425 slm) of contaminated gas at pressures from 100 to 600 psig (7.0 to 42.2 kg/cm/sup 2/) and temperatures from minus 45 to plus 25/sup 0/F (-43 to -4/sup 0/C). Part of the development program is devoted to identifying flowsheet options and simplifications that lead to an even more economical and reliable process. Two of these applicative flowsheets are discussed.

  10. Design and development of effluent treatment plants for the Sellafield reprocessing factory

    International Nuclear Information System (INIS)

    Howden, M.

    1989-01-01

    The reprocessing of spent nuclear fuel has been carried out at Sellafield since the early 1950s. The storage of fuel in water filled ponds prior to reprocessing and the reprocessing operation itself results in the generation of a number of radioactive liquid effluents. The highly active liquors are stored in stainless steel tanks and will, with the commissioning of the Windscale Vitrification Plant, be converted into glass for long term storage and disposal. The medium and low active liquors are, after appropriate treatment, discharged to sea well below the Authorised Limits which are set by the appropriate Regulatory Bodies. Since 1960 these have been the Department of the Environment and the Ministry of Agriculture, Fisheries and Food. Even though the discharges have been well below the limits set, BNFL have for many years adopted a policy of reducing the levels of activity still further. Considerable progress has already been made, by changing reprocessing operations regimes but more importantly by the development and construction of specialised effluent treatment plants. Further reductions are, however, planned. Two major effluent treatment plants form the main basis of BNFL's policy to reduce activity discharges from Sellafield. The first, the Site Ion Exchange Effluent Plant, to treat storage pond water was brought into operation in 1985. The second, the enhanced Actinide Removal Plant to treat medium and low active effluents, is programmed to operate in 1992. (author)

  11. 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

  12. A new organisation for the Cogema group; Une nouvelle organisation pour le Groupe Cogema

    Energy Technology Data Exchange (ETDEWEB)

    Anon

    2000-06-01

    The Cogema group hopes to find a second business, being awaiting the nuclear area starts again. It needs eighteen months to find it. It must have an empathy with its first business and does not be in competition with its customers. (N.C.)

  13. International safeguards for reprocessing plants. Final report

    International Nuclear Information System (INIS)

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

    1981-04-01

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

  14. International safeguards for reprocessing plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

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

    1981-04-01

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

  15. Solvent distillation studies for a purex reprocessing plant

    International Nuclear Information System (INIS)

    Ginisty, C.; Guillaume, B.

    1990-01-01

    A distillation system has been developed for regeneration of Purex solvent and will be implemented for the first time in a reprocessing plant. The results are described and analyzed, with emphasis on laboratory experiments which were made with a radioactive plant solvent. Particularly the distillation provides a good separation of solvent degradation products, which was verified by measurements of interfacial tension and plutonium or ruthenium retention. 16 refs., 3 figs., 5 tabs

  16. Design of the vitrification plant for HLLW generated from the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Vematsu, K.

    1986-01-01

    Power Reactor and Nuclear Fuel Development Corporation (PNC) is now designing a vitrification plant. This plant is for the solidification of high-level liquid waste (HLLW) which is generated from the Tokai Reprocessing Plant, and for the demonstration of the vitrification technology. The detailed design of the plant which started in 1982 was completed in 1984. At present the design improvement is being made for the reduction of construction cost and for the licensing which is going to be applied in 1986. The construction will be started in autumn 1987. The plant has a large shielded cell with low flow ventilation, and employs rack-mounted module system and high performance two-armed servomanipulator system to accomplish the fully remote operations and maintenance. The vitrification of HLLW is based on the liquid-fed Joule-heated ceramic melter process. The processing capacity is equivalent to the reprocessing of 0.7 ton of heavy metals per day. The glass production rate is about 9 kg/h, and about 300 kg of glass is poured periodically from the bottom of the melter into a canister. Produced glass is stored under the forced air cooling condition

  17. 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)

  18. 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

  19. Research and development of safeguards measures for the large scale reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Kikuchi, Masahiro; Sato, Yuji; Yokota, Yasuhiro; Masuda, Shoichiro; Kobayashi, Isao; Uchikoshi, Seiji; Tsutaki, Yasuhiro; Nidaira, Kazuo [Nuclear Material Control Center, Tokyo (Japan)

    1994-12-31

    The Government of Japan agreed on the safeguards concepts of commercial size reprocessing plant under the bilateral agreement for cooperation between the Japan and the United States. In addition, the LASCAR, that is the forum of large scale reprocessing plant safeguards, could obtain the fruitful results in the spring of 1992. The research and development of safeguards measures for the Rokkasho Reprocessing Plant should be progressed with every regard to the concepts described in both documents. Basically, the material accountancy and monitoring system should be established, based on the NRTA and other measures in order to obtain the timeliness goal for plutonium, and the un-attended mode inspection approach based on the integrated containment/surveillance system coupled with radiation monitoring in order to reduce the inspection efforts. NMCC has been studying on the following measures for a large scale reprocessing plant safeguards (1) A radiation gate monitor and integrated surveillance system (2) A near real time Shipper and Receiver Difference monitoring (3) A near real time material accountancy system operated for the bulk handling area (4) A volume measurement technique in a large scale input accountancy vessel (5) An in-process inventory estimation technique applied to the process equipment such as the pulse column and evaporator (6) Solution transfer monitoring approach applied to buffer tanks in the chemical process (7) A timely analysis technique such as a hybrid K edge densitometer operated in the on-site laboratory (J.P.N.).

  20. Trends and R and D in France to improve the performance of activity measurements systems for the reprocessing low level wastes

    Energy Technology Data Exchange (ETDEWEB)

    Martin Deidier, L. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d`Etudes des Reacteurs; Masson, H.; Coryn, P. [Cogema, 78 - Velizy-Villacoublay (France); Silie, Ph. [SGN Reseau Eurisys, 78 - Saint Quentin (France); Huver, M. [Eurysis Mesure, 78 - Saint-Quentin-en Yvelines (France)

    1995-12-31

    In the frame of COGEMA actins to reduce the volume of the reprocessing waste, a new strategy of drumming and incinerating is going to start at LA HAGUE and MARCOULE, for the low level waste planned for surface storage. This strategy depends on the performance improvement of non destructive measurements systems used for the alpha waste evaluation. In this global, closer links between COGEMA, SGN, CEA and EURYSIS MESURE have taken place to define a program in order to obtain up to three years the required performances, using active methods with neutron generator. These developments and tests are carried out on the PROMETHEE R and D facility at CEA-CADARACHE. (authors) 3 refs.

  1. Design verification for large reprocessing plants (Proposed procedures)

    International Nuclear Information System (INIS)

    Rolandi, G.

    1988-07-01

    In the 1990s, four large commercial reprocessing plants will progressively come into operation: If an effective and efficient safeguards system is to be applied to these large and complex plants, several important factors have to be considered. One of these factors, addressed in the present report, concerns plant design verification. Design verification provides an overall assurance on plant measurement data. To this end design verification, although limited to the safeguards aspects of the plant, must be a systematic activity, which starts during the design phase, continues during the construction phase and is particularly performed during the various steps of the plant's commissioning phase. The detailed procedures for design information verification on commercial reprocessing plants must be defined within the frame of the general provisions set forth in INFCIRC/153 for any type of safeguards related activities and specifically for design verification. The present report is intended as a preliminary contribution on a purely technical level, and focusses on the problems within the Agency. For the purpose of the present study the most complex case was assumed: i.e. a safeguards system based on conventional materials accountancy, accompanied both by special input and output verification and by some form of near-real-time accountancy involving in-process inventory taking, based on authenticated operator's measurement data. C/S measures are also foreseen, where necessary to supplement the accountancy data. A complete ''design verification'' strategy comprehends: informing the Agency of any changes in the plant system which are defined as ''safeguards relevant''; ''reverifying by the Agency upon receiving notice from the Operator on any changes, on ''design information''. 13 refs

  2. Report of the study grou: Data Processing in Reprocessing Plants

    International Nuclear Information System (INIS)

    1976-08-01

    A study group to examine Data Processing in Spent Fuel Reprocessing Plants was created at the request of the Head of Productions and entrusted to the Director of the La Hague Centre. The groupe was made up of engineers working in different fields: piloting, architecture, building outfits, services etc. To begin with the group examined the solutions proposed by the La Hague Centre for the replacement of data processing units in service at the time but too old and unreliable to meet the safety rules laid down. Secondly, as a contribution towards France's heritage in the fuel reprocessing field, the group investigated systems and configurations for possible application to the equipment of future plants. The results of these studies were submitted in January 1974 [fr

  3. 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)

  4. Enhancements in the thorp reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Wakem, M.J.; Brownridge, M. [Thorp Technical Dept. and Research and Technology, BNFL plc, Sellafield, seascale, Cumbria, CA (United Kingdom)

    2000-07-01

    A number of successful enhancements have been made to the process at the Thorp reprocessing plant at Sellafield. After a long and detailed Research and Development programme followed by an intensive design/construction project, Thorp was inactively commissioned with first active shear in March 1994. The plant has now reached a mature stage in its development, following successful active commissioning demonstrating flowsheet or better performance in the solvent extraction cycles. Enhancements are now sought to achieve a range of objectives. Against a background of ever tighter regulatory control both in terms of safety and environmental discharge, BNFL are continuing to invest in further improvements with short, medium and longer term objectives to improve plant throughput; expand the range of feed fuels; reduce environmental discharges and reduce running costs. This paper describes a few of these enhancements. (authors)

  5. Enhancements in the thorp reprocessing plant

    International Nuclear Information System (INIS)

    Wakem, M.J.; Brownridge, M.

    2000-01-01

    A number of successful enhancements have been made to the process at the Thorp reprocessing plant at Sellafield. After a long and detailed Research and Development programme followed by an intensive design/construction project, Thorp was inactively commissioned with first active shear in March 1994. The plant has now reached a mature stage in its development, following successful active commissioning demonstrating flowsheet or better performance in the solvent extraction cycles. Enhancements are now sought to achieve a range of objectives. Against a background of ever tighter regulatory control both in terms of safety and environmental discharge, BNFL are continuing to invest in further improvements with short, medium and longer term objectives to improve plant throughput; expand the range of feed fuels; reduce environmental discharges and reduce running costs. This paper describes a few of these enhancements. (authors)

  6. Fuel reprocessing plant - no solution for the economy of the region

    International Nuclear Information System (INIS)

    Elvers, G.

    1986-01-01

    Both for the construction and operation stage, the direct and indirect impact of the fuel reprocessing plant on employment on the whole will be negative. It is not altogether certain either that there will be no adverse effects for the areas of tourism. The top organization of German trade unions (DGB) holds that a different structure-political concept from the one represented by the large-scale project of the fuel reprocessing plant would be more appropriate for the region. Employment in the steel and construction industries must be safeguarded by corresponding programmes, and new employment must be created in small- and medium-size companies. (DG) [de

  7. Head-end iodine removal from a reprocessing plant with a solid sorbent

    International Nuclear Information System (INIS)

    Wilhelm, J.G.; Furrer, J.; Schultes, E.

    1976-01-01

    In the first large-scale reprocessing plant planned in the Federal Republic of Germany a total amount of 580 kg of iodine per annum will be released in the fuel dissolution process for a maximum heavy metal throughput of 1800 tons per year and 40,000 MWd/t of burnup. The main portion of the iodine is formed by the 129 I (T/sub 1/2/ = 1.6 x 10 7 a) isotope of which 82 Ci at the maximum are released every year. With the scheduled fuel element storage time of greater than or equal to 220 d the simultaneous release of 131 I is less than or equal to 12.5 Ci the mass of which does not play any part. According to the computer model presently imposed in the Federal Republic of Germany for treatment of the environmental impact by radioiodine, a total decontamination factor of 340 must be attained. This implies a long-term diffusion factor of 1 x 10 -7 s/m 3 for releases via the stack of the reprocessing plant and a limit value of 50 mrem/a at the maximum for the thyroid dose to the critical group of the population via the ingestion path. The flowsheet for dissolver off-gas cleaning in a reprocessing plant employing solid iodine sorption material and the arrangement of filter components are discussed. The principle of an iodine sorption filter is described which allows exhaustive loading of the iodine sorption material. The removal reactions of different organic iodine compounds and the loading capacity and removal efficiency of the iodine sorption material in the original dissolver off-gases of reprocessing plants are indicated. Studies on the influence of filter poisons are reported.Operating experience gathered with a first iodine sorption filter in operation is discussed; this filter has been used to remove practically all iodine produced in the dissolver off-gas of the Karlsruhe Reprocessing Pilot Plant (WAK). Direct measurement of 129 I in samples of filter material using a low energy photon spectrometer is briefly reported

  8. 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.)

  9. Information centres: hyper-qualitative tool of Cogema's communication policy

    International Nuclear Information System (INIS)

    Chadeyron, P.

    1993-01-01

    The information centres are an indispensable link in the chain of Cogema's communication policy. They enable a complete adaptation to each visitor's different level of understanding and thus improve the quality of the transmission of information to a reduced, but totally sensitive, target. The information centres therefore represent ''quality'' tools which are complementary to other means of communication. Moreover, they emphasize Cogema's resolution to communicate and formalize its communication policy. (author)

  10. 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

  11. 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)

  12. 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

  13. 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

  14. Development of integrated parameter database for risk assessment at the Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Tamauchi, Yoshikazu

    2011-01-01

    A study to develop a parameter database for Probabilistic Safety Assessment (PSA) for the application of risk information on plant operation and maintenance activity is important because the transparency, consistency, and traceability of parameters are needed to explanation adequacy of the evaluation to third parties. Application of risk information for the plant operation and maintenance activity, equipment reliability data, human error rate, and 5 factors of 'five-factor formula' for estimation of the amount of radioactive material discharge (source term) are key inputs. As a part of the infrastructure development for the risk information application, we developed the integrated parameter database, 'R-POD' (Rokkasho reprocessing Plant Omnibus parameter Database) on the trial basis for the PSA of the Rokkasho Reprocessing Plant. This database consists primarily of the following 3 parts, 1) an equipment reliability database, 2) a five-factor formula database, and 3) a human reliability database. The underpinning for explaining the validity of the risk assessment can be improved by developing this database. Furthermore, this database is an important tool for the application of risk information, because it provides updated data by incorporating the accumulated operation experiences of the Rokkasho reprocessing plant. (author)

  15. COGEMA's employment and training policy for its foreign subsidiaries

    International Nuclear Information System (INIS)

    Hamani, A.

    2002-01-01

    COGEMA has actively pursued a policy of employing country nationals for its foreign subsidiaries in Niger, Gabon, Canada and Kazakhstan. The process of replacing foreign staff by nationals in Niger is first described, detailing the personnel management objectives and procedures, the main difficulties encountered, the current situation and the lessons to take from this experience. COGEMA's policies and ways applied in other countries to increase the proportions of nationals are then presented. (author)

  16. Status report - expert knowledge of operators in fuel reprocessing plants, enrichment plants and fuel fabrication plants

    International Nuclear Information System (INIS)

    Preuss, W.; Kramer, J.; Wildberg, D.

    1987-01-01

    The necessary qualifications of the responsible personnel and the knowledge required by personnel otherwise employed in nuclear plants are among the requirements for licensing laid down in paragraph 7 of the German Atomic Energy Act. The formal regulations for nuclear power plants are not directly applicable to plants in the fuel cycle because of the differences in the technical processes and the plant and work organisation. The aim of the project was therefore to establish a possible need for regulations for the nuclear plants with respect to the qualification of the personnel, and to determine a starting point for the definition of the required qualifications. An extensive investigation was carried out in the Federal Republic of Germany into: the formal requirements for training; the plant and personnel organisation structures; the tasks carried out by the responsible and otherwise employed personnel; and the state of training. For this purpose plant owners and managers were interviewed and the literature and plant specific documentation (e.g. plant rules) were reviewed. On the basis of literature research, foreign practices were determined and used to make comparative evaluations. The status report is divided into three separate parts for the reprocessing, the uranium enrichment, and the manufacture of the fuel elements. On the basis of the situation for reprocessing plants (particularly that of the WAK) and fuel element manufacturing plants, the development of a common (not uniform) regulation for all the examined plants in the fuel cycle was recommended. The report gives concrete suggestions for the content of the regulations. (orig.) [de

  17. The safety of the new reprocessing plants of La Hague

    International Nuclear Information System (INIS)

    Devillers, C.; Dubois, G.

    1987-09-01

    In this document the authors show the main guiding lines on which is based the safety of the new reprocessing plant of La Hague. They are: - the objectives: to limit the impacts on workers and environment - the methods: safety analysis based on the checking and evaluation of significant risks. - the means: to make a safety plant by the use of quality assurance in the conception and in the plant construction [fr

  18. Indian experience in fuel reprocessing

    International Nuclear Information System (INIS)

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

    1977-01-01

    Plant scale experience in fuel reprocessing in India was started with the successful design, execution and commissioning of the Trombay plant in 1964 to reprocess aluminium clad metallic uranium fuel from the 40 MWt research reactor. The plant has helped in generating expertise and trained manpower for future reprocessing plants. With the Trombay experience, a larger plant of capacity 100 tonnes U/year to reprocess spent oxide fuels from the Tarapur (BWR) and Rajasthan (PHWR) power reactors has been built at Tarapur which is undergoing precommissioning trial runs. Some of the details of this plant are dealt with in this paper. In view of the highly corrosive chemical attack the equipment and piping are subjected to in a fuel reprocessing plant, some of them require replacement during their service if the plant life has to be extended. This calls for extensive decontamination for bringing the radiation levels low enough to establish direct accesss to such equipment. For making modifications in the plant to extend its life and also to enable expansion of capacity, the Trombay plant has been successfully decontaminated and partially decommissioned. Some aspects of thi decontamination campaign are presented in this paper

  19. Information disclosure of troubles occurring at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Yamada, Tatsuya; Yoneyama, Mitsuru; Shinozaki, Yoshinori

    2005-01-01

    At Rokkasho Reprocessing Plant (RRP), efforts are made so that troubles occurred are promptly reported and announced publicly, and for minor troubles, etc., announcement to the society is made through the web-site and publicity magazines, so as to assure the transparency of the business. (author)

  20. The fuel reprocessing plant at Wackersdorf

    International Nuclear Information System (INIS)

    Held, M.

    1986-01-01

    For a more systematic discussion about the fuel reprocessing plant at Wackersdorf, the colloquium tried to cover the most important questions put forward in the controversies: economic efficiency and energy-political needs; safety and ecological repercussions; inner safety and consequences for basic rights and the regional economic structure; majority decisions and participation of the population of the region. Elements of evaluation are the conservation of resources, health, economic efficiency, and citizens' rights of liberty. The related basic ethical questions are considered. The 18 contributions are individually recorded in the data base. (DG) [de

  1. Nuclear fuel reprocessing in the UK

    International Nuclear Information System (INIS)

    Allardice, R.; Harris, D.; Mills, A.

    1983-01-01

    Nuclear fuel reprocessing has been carried out on an industrial scale in the United Kingdom since 1952. Two large reprocessing plants have been constructed and operated at Windscale, Cumbria and two smaller specialized plants have been constructed and operated at Dounreay, Northern Scotland. At the present time, the second of the two Windscale plants is operating, and Government permission has been given for a third reprocessing plant to be built on that site. At Dounreay, one of the plants is operating in its original form, whilst the second is now operating in a modified form, reprocessing fuel from the prototype fast reactor. This chapter describes the development of nuclear fuel reprocessing in the UK, commencing with the research carried out in Canada immediately after the Second World War. A general explanation of the techniques of nuclear fuel reprocessing and of the equipment used is given. This is followed by a detailed description of the plants and processes installed and operated in the UK

  2. Nuclear fuel reprocessing in the UK

    International Nuclear Information System (INIS)

    Allardice, R.H.; Harris, D.W.; Mills, A.

    1983-01-01

    Nuclear fuel reprocessing has been carried out on an industrial scale in the United Kingdom since 1952. Two large reprocessing plants have been constructed and operated at Windscale, Cumbria and two smaller specialized plants have been constructed and operated at Dounreay, Northern Scotland. At the present time, the second of the two Windscale plants is operating, and Government permission has been given for a third reprocessing plant to be built on that site. At Dounreay, one of the plants is operating in its original form, whilst the second is now operating in a modified form, reprocessing fuel from the prototype fast reactor. This chapter describes the development of nuclear fuel reprocessing in the UK, commencing with the research carried out in Canada immediately after the Second World War. A general explanation of the techniques of nuclear fuel reprocessing and of the equipment used is given. This is followed by a detailed description of the plants and processes installed and operated in the UK. (author)

  3. Computer aided radiation protection system at Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Ishida, J.; Saruta, J.; Yonezawa, R.

    1996-01-01

    Radiation control for workers and workforce has been carried out strictly and effectively taking into account ALARA principle at Tokai Reprocessing Plant (TRP) which has treated about 860 tons of irradiated fuels by now since 1977. The outline of radiation control method at TRP has already been described. This paper briefly describes our experiences and the capabilities of Radiological Information Management System (RIMS) for the safety operation of TRP, followed by radiation exposure control and activity discharge control as examples. By operating the RIMS, the conditions of workplace such as dose equivalent rate and air-contamination are easily and rapidly grasped to take prompt countermeasures for radiological protection, localization and elimination of contamination, and also the past experience data are properly applied to new radiological works to reduce exposures associated with routine and special repetitive maintenance operations at TRP. Finally, authors would like to emphasize that the form and system for radiological control of reprocessing plant has been established throughout our 15-year-experience at TRP. (author)

  4. Revisit of analytical methods for the process and plant control analyses during reprocessing of fast reactor fuels

    International Nuclear Information System (INIS)

    Subba Rao, R.V.

    2016-01-01

    CORAL (COmpact facility for Reprocessing of Advanced fuels in Lead cell) is an experimental facility for demonstrating the reprocessing of irradiated fast reactor fuels discharged from the Fast Breeder Test Reactor (FBTR). The objective of the reprocessing plant is to achieve nuclear grade plutonium and uranium oxides with minimum process waste volumes. The process flow sheet for the reprocessing of spent Fast Reactor Fuel consists of Transport of spent fuel, Chopping, Dissolution, Feed conditioning, Solvent Extraction cycle, Partitioning Cycle and Re-conversion of Plutonium nitrate and uranium nitrate to respective oxides. The efficiency and performance of the plant to achieve desired objective depends on the analyses of various species in the different steps adopted during reprocessing of fuels. The analytical requirements in the plant can be broadly classified as 1. Process control Analyses (Analyses which effect the performance of the plant- PCA); 2. Plant control Analyses (Analyses which indicates efficiency of the plant-PLCA); 3. Nuclear Material Accounting samples (Analyses which has bearing on nuclear material accounting in the plant - NUMAC) and Quality control Analyses (Quality of the input bulk chemicals as well as products - QCA). The analytical methods selected are based on the duration of analyses, precision and accuracies required for each type analytical requirement classified earlier. The process and plant control analyses requires lower precision and accuracies as compared to NUMAC analyses, which requires very high precision accuracy. The time taken for analyses should be as lower as possible for process and plant control analyses as compared to NUMAC analyses. The analytical methods required for determining U and Pu in process and plant samples from FRFR will be different as compared to samples from TRFR (Thermal Reactor Fuel Reprocessing) due to higher Pu to U ratio in FRFR as compared TRFR and they should be such that they can be easily

  5. Radiation protection experience during active commissioning of the Thorp reprocessing plant

    International Nuclear Information System (INIS)

    Spour, K.; Hutton, E.

    1996-01-01

    BNFL's Thermal Oxide Reprocessing Plant (Thorp) reprocesses uranium oxide fuel assemblies which have been irradiated in thermal reactors in the UK and overseas. Plans for the plant were first announced in 1974. Application for planning permission was submitted in 1977, and government permission to construct the plant was granted after the Windscale inquiry in 1977. The plant was given the license to start active commissioning in head end in early 1994, and then in chemical plants in late 1994. Presently the whole of the process is being challenged in a planned commissioning strategy which will last into 1996. Thorp is designed to reprocess the spent oxide fuel into uranium trioxide (UO 3 ) and plutonium dioxide (PuO 2 ). The Thorp complex can be essentially broken down into three distinct areas: Thorp receipt and storage provides pond storage for fuel awaiting reprocessing in Thorp. Head end fuel is transferred from receipt and storage into the feed pond where it is monitored to check fissile content, burn up and cooling time. The individual fuel assemblies for LWR fuel, or cans in the case of AGR fuel, are transferred onto the shear elevator and carried up to the shear cave. The fuel is sheared into small lengths to optimize the dissolution of the fuel inside the cladding. The sheared fuel and cladding debris is directed via a chute into one of three dissolvers, each with a nominal 1.8 teU capacity and dissolved in 8M nitric acid for approximately 16 hours. The cladding hulls are retained in a removable basket and sent for encapsulation. Insoluble fission products and fine particles of cladding are removed by centrifugation. Clarified dissolver solution is then accounted for by measurements taken for volume, mass and isotopic composition. Following this, the solution is transferred to buffer storage tarns and fed onto the chemical separation area. The liquor is transferred to the chemical separation area where it undergoes first cycle separation in pulsed columns

  6. Workshop on instrumentation and analyses for a nuclear fuel reprocessing hot pilot plant

    International Nuclear Information System (INIS)

    Babcock, S.M.; Feldman, M.J.; Wymer, R.G.; Hoffman, D.

    1980-05-01

    In order to assist in the study of instrumentation and analytical needs for reprocessing plants, a workshop addressing these needs was held at Oak Ridge National Laboratory from May 5 to 7, 1980. The purpose of the workshop was to incorporate the knowledge of chemistry and of advanced measurement techniques held by the nuclear and radiochemical community into ideas for improved and new plant designs for both process control and inventory and safeguards measurements. The workshop was athended by experts in nuclear and radiochemistry, in fuel recycle plant design, and in instrumentation and analysis. ORNL was a particularly appropriate place to hold the workshop since the Consolidated Fuel Reprocessing Program (CFRP) is centered there. Requirements for safeguarding the special nuclear materials involved in reprocessing, and for their timely measurement within the process, within the reprocessing facility, and at the facility boundaries are being studied. Because these requirements are becoming more numerous and stringent, attention is also being paid to the analytical requirements for these special nuclear materials and to methods for measuring the physical parameters of the systems containing them. In order to provide a focus for the consideration of the workshop participants, the Hot Experimental Facility (HEF) being designed conceptually by the CFRP was used as a basis for consideration and discussions

  7. COGEMA Experience in Uranous Nitrate Preparation

    International Nuclear Information System (INIS)

    Tison, E.; Bretault, Ph.

    2006-01-01

    Separation and purification of plutonium by PUREX process is based on a sequence of extraction and back extraction which requires reducing plutonium Pu IV (extractable form) into Pu III (inextractable form) Different reducers can be used to reduce Pu IV into Pu III. Early plants such as that for Magnox fuel at Sellafield used ferrous sulfamate while UP 1 at Marcoule used uranous sulfamate. These reducers are efficient and easy to prepare but generates ferric and/or sulphate ions and so complicates management of the wastes from the plutonium purification cycle. Recent plants such as UP3 and UP2 800 at La Hague, THORP at Sellafield, and RRP at Rokkasho Mura (currently under tests) use uranous nitrate (U IV) stabilized by hydrazinium nitrate (N 2 H 5 NO 3 ) and hydroxyl ammonium nitrate (HAN). In the French plants, uranous nitrate is used in U-Pu separation and alpha barrier and HAN is used in Pu purification. Compared to sulfamate, U IV does not generate extraneous chemical species and uranyl nitrate (U VI) generated by reducing Pu IV follows the main uranium stream. More over uranous nitrate is prepared from reprocessed purified uranyl nitrate taken at the outlet of the reprocessing plant. Hydrazine and HAN offer the advantage to be salt-free reagents. Uranous nitrate can be generated either by electrolysis or by catalytic hydrogenation process. Electrolytic process has been implemented in early plant UP 1 at Marcoule (when changing reducer from uranous sulfamate to uranous nitrate) and was used again in UP2 plant at La Hague. However, the electrolytic process presented several disadvantages such as a low conversion rate and problems associated with the use of mercury. Electrolysis cells with no mercury were developed for the Eurochemic plant in Belgium and then implemented in the first Japanese reprocessing plant in Tokai-Mura. But finally, in 1975, the electrolytic process was abandoned in favor of the catalytic hydrogenation process developed at La Hague. The

  8. Roles of programmable logic controllers in fuel reprocessing plants

    International Nuclear Information System (INIS)

    Mishra, Hrishikesh; Balakrishnan, V.P.; Pandya, G.J.

    1999-01-01

    Fuel charging facility is another application of Programmable Logic Controllers (PLC) in fuel reprocessing plants, that involves automatic operation of fuel cask dolly, charging motor, pneumatic doors, clutches, clamps, stepper motors and rod pushers in a pre-determined sequence. Block diagram of ACF system is given for underlining the scope of control and interlocks requirements involved for automation of the fuel charging system has been provided for the purpose at KARP Plant, Kalpakkam

  9. High capacity cask (TN28V) and International Transport System for the return shipment of vitrified high activity wastes

    International Nuclear Information System (INIS)

    Sert, G.; Savornin, B.; Rouquette, Y.

    1989-01-01

    The reprocessing of spent fuel generates different kinds of wastes. Among them fission products and non fissile actinides represent 98% of the radioactivity; these wastes are separated, concentrated, mixed with molten glass and poured into stainless steel containers. For political reasons, it is necessary to return these vitrified high activity wastes to the foreign countries which have decided to have their spent fuel reprocessed in France. So the transport of vitrified waste is vital for both the reprocessor and the utilities that have trusted the reprocessor and this operation has to be securely performed to give satisfaction to all concerned particles. For that reason Cogema will control the whole transport activity from La Hague plants to the receiving facilities of the customers. Therefore cogema will be responsible of the transport whatever the cask type (transport or storage) and will subcontract the transport operation to experienced companies such as Transnucleaire, PNTL or NTL, who will act on behalf of Cogema. Cogema will be the owner of the transport casks while the storage casks will normally be owned by the customers. Both cask types will of course have to comply with the requirements of La Hague, as published by Cogema

  10. 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)

  11. Radiological considerations in the design of Reprocessing Uranium Plant (RUP) of Fast Reactor Fuel Cycle Facility (FRFCF), Kalpakkam

    International Nuclear Information System (INIS)

    Chandrasekaran, S.; Rajagopal, V.; Jose, M.T.; Venkatraman, B.

    2012-01-01

    A Fast Reactor Fuel Cycle Facility (FRFCF) being planned at Indira Gandhi Centre for Atomic Research, Kalpakkam is an integrated facility with head end and back end of fuel cycle plants co-located in a single place, to meet the refuelling needs of the prototype fast breeder reactor (PFBR). Reprocessed uranium oxide plant (RUP) is one such plant in FRFCF to built to meet annual requirements of UO 2 for fabrication of fuel sub-assemblies (FSAs) and radial blanket sub-assemblies (RSAs) for PFBR. RUP receives reprocessed uranium oxide powder (U 3 O 8 ) from fast reactor fuel reprocessing plant (FRP) of FRFCF. Unlike natural uranium oxide plant, RUP has to handle reprocessed uranium oxide which is likely to have residual fission products activity in addition to traces of plutonium. As the fuel used for PFBR is recycled within these plants, formation of higher actinides in the case of plutonium and formation of higher levels of 232 U in the uranium product would be a radiological problem to be reckoned with. The paper discussed the impact of handling of multi-recycled reprocessed uranium in RUP and the radiological considerations

  12. 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

  13. The validation of waste assay systems during active test at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Tamura, Takayuki; Miura, Yasushi; Iwamoto, Tomonori

    2007-01-01

    In order to implement accurate material accountancy at Rokkasho Reprocessing Plant (RRP) as a large scale reprocessing plant, it is necessary to introduce accurate measurement systems not only for mainstream material, but also appropriate measurement systems for solid waste materials. In this sense, the generated wastes by the active test operation have been measured with the Non-Destructive Assay Systems, such as Rokkasho Hulls Measurement System (RHMS) and Waste Crate Assay System (WCAS) for accountancy. This paper describes the experience of the NDA operation and the evaluation results for accountancy. (author)

  14. Safety aspects of a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Donoghue, J.K.; Charlesworth, F.R.; Fairbairn, A.

    1977-01-01

    decommissioning and demolition procedures must be anticipated and suitable provision made. Application of these principles is illustrated by experience gained in the surveillance of reprocessing plants. United Kingdom regulatory procedures for the licensing and inspection of reprocessing plant, and statutory requirements influencing safety in design, construction and operation are reviewed. Recent developments in safety legislation including the Health and Safety at Work Act, 1974, are discussed

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

    International Nuclear Information System (INIS)

    Ehinger, Michael H.; Johnson, Shirley

    2010-01-01

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

  16. DIRECT DISMANTLING OF REPROCESSING PLANT CELLS THE EUREX PLANT EXPERIENCEe2d12c

    International Nuclear Information System (INIS)

    Gili, M.; Troiani, F.; Risoluti, P.

    2003-01-01

    After finishing the reprocessing campaigns in 1970-1983, the EUREX pilot reprocessing plant of ENEA Saluggia Research Center started into a new phase, aiming to materials and irradiated fuel systemation and radioactive wastes conditioning. In 1997 the project ''CORA'' for a vitrification plant for the high and intermediate liquid radioactive wastes started. The ''CORA'' plant will be hosted in some dismantled cells of the EUREX plant, reusing many of the EUREX plant auxiliary systems, duly refurbished, saving money and construction time and avoiding a new nuclear building in the site. Two of the cells that will be reused were part of the EUREX chemical process (solvent recovery and 2nd extraction cycle) and the components were obviously internally contaminated. In 2000 the direct (hands-on) dismantling of one of them started and has been completed in summer 2002; the second one will be dismantled in the next year and then the ''CORA'' plant will be assembled inside the cells. Special care w as taken to avoid spread of contamination in the cells, where ''CORA'' installation activities will start in the next years, during the dismantling process The analysis of data and results collected during the dismantling of the first cell shows that direct dismantling can be achieved with careful choice of tools, procedures and techniques, to reduce volumes of wastes to be disposed and radiological burden

  17. Radiological prevention in a reprocessing plant

    International Nuclear Information System (INIS)

    Trenta, G.

    1983-01-01

    Prevention has received a peculiar conceptual formulation in working activities with radiation risk. In order to point out the operative aspects of this formulation the authors relates here the considerations, the criteria an the precautionary measures which have guided the choice or that have been actuated to reduce the risk for the workers of the EUREX reprocessing plant. The general aspect of this formulationa has a philosophical and doctrinarian course, peculiar in the probabilistic safety approach and in radioprotection methodology. The authors quotes here some concepts and some specific application of both but he shows above all the medical aspects of the radioprotection

  18. Commissioning and Operational Experience in Power Reactor Fuel Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Pradhan, S., E-mail: spradhan@barctara.gov.in [Tarapur Based Reprocessing Plant, Bhabha Atomic Research Centre, Tarapur (India)

    2014-10-15

    After completing design, construction, commissioning, operation and maintenance experience of the reprocessing plants at Tarapur, Mumbai and Kalpakkam a new reprocessing plant is commissioned and put into operation at BARC, Tarapur since 2011. Subsequent to construction clearance, commissioning of the plant is taken in many steps with simultaneous review by design and safety committees. In spite of vast experience, all the staff was retrained in various aspects of process and utility operations and in operation of innovative changes incorporated in the design. Operating personnel are licensed through an elaborate procedure consisting of various check lists followed by personnel interview. Commissioning systems were divided in sub-systems. Sub-systems were commissioned independently and later integrated testing was carried out. For commissioning, extreme operating conditions were identified in consultation with designers and detailed commissioning procedures were made accordingly. Commissioning was done in different conditions to ensure safety, smooth operation and maintainability. Few modifications were carried out based on commissioning experience. Technical specifications for operation of the plant are made in consultation with designers and reviewed by safety committees. Operation of the plant was carried out after successful commissioning trials with Deep Depleted Uranium (DDU). Emergency operating procedures for each design basis accident were made. Performance of various systems, subsystems are quite satisfactory and the plant has given very good capacity factor. (author)

  19. International safeguards for a light-water reactor fuels reprocessing plant: containment and surveillance concepts

    International Nuclear Information System (INIS)

    Cameron, C.P.; Bleck, M.E.

    1980-12-01

    Concepts for containment/surveillance for reprocessing plants are described, conceptual designs are developed, and their effectiveness is evaluated. A technical approach to design of containment/surveillance systems is presented, and design considerations are discussed. This is the second in a series of reports. The first described the basis for the study of international safeguards for reprocessing plants. In this second report, only containment/surveillance is discussed. The third report will discuss the integration of concepts for containment/surveillance and material accountancy

  20. 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

  1. 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.)

  2. 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)

  3. The development of in-cell remote inspection system in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Ishibashi, Yuzo

    1985-01-01

    In the Tokai fuel reprocessing plant, the containment is triple, i.e. the vessel containing radioactive material, then the concrete cell structure and finally the housing building. The fuel reprocessing plant is now proceeding with the development of an in-cell remote inspection system. The inspection system is for inspection of the cell itself and the equipment etc. in the cell, concerning the integrity. Described are the following: the course taken and problems in development of the remote inspection system; development of the floor rambling type remote inspection equipment and the multiple armed type, both for inspection of in-cell ''drip trays''; in-cell equipment inspection devices in specifications etc.; problems in its future development. (Mori, K.)

  4. 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)

  5. Simulation study of near-real-time accounting in a generic reprocessing plant

    International Nuclear Information System (INIS)

    Coulter, C.A.; Whiteson, R.; Zardecki, A.

    1992-01-01

    Our simulation program FacSim has been used to estimate balance closure variances for a number of real proposed nuclear material processing facilities that rely primarily on item measurements. We are enhancing the program so that it can be applied to facilities such as reprocessing plants that handle bulk materials ad primarily perform bulk and flow measurements. The extended simulation program can apply any of several types of sequential statistical tests to near-real-time accounting information to evaluate the capability of the facility accounting system to detect material and operational anomalies in a timely fashion. The program allows facility designers and operators to evaluate measurement and anomaly detection strategies before system implementation and to demonstrate facility's capability for maintaining accurate inventory information during plant operation. These features are illustrated by application to a generic reprocessing plant

  6. 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)

  7. Application of probabilistic safety assessment to Rokkasho reprocessing plant, (2)

    International Nuclear Information System (INIS)

    Miyata, Takashi; Takebe, Kazumi; Tamauchi, Yoshikazu

    2008-01-01

    A probabilistic safety assessment (PSA) is made on the boiling accident of a highly active liquid waste tank, which may result in significant consequences, in accordance with the procedure for PSA developed for nuclear power plants. Obtained as results are the frequency of boiling accident of a certain tank of 2.0x10 -8 /y (frequency of boiling accident of any tank of 4.1x10 0-8 /y), its error factor of approx. 6, and information on the relative risk importance based on the FV index and RAW for various components, systems and activities of personnel and on the sensitivity of key parameters. Furthermore, the effect of the time required for repairing failed instruments on the frequency of accident, how to deal with the common cause of failure of the duplicated dynamic components, one of which is at least in operation, and conservative exposure dose in the event of an accident are examined. The database for the Rokkasho reprocessing plant has not been established yet, but the PSA results utilizing available failure rate databases of existing nuclear power plants and reprocessing plants in Japan and abroad can be used effectively to optimize operations and maintenance, if they are interpreted properly and some uncertainties are taken into account. (author)

  8. Concept of a tritium extraction facility for a reprocessing plant

    International Nuclear Information System (INIS)

    Tunaboylu, K.; Paulovic, M.; Ulrich, D.

    1991-01-01

    There are several alternatives for reducing the release of tritium to the environment originating from the wastewater of a reprocessing plant. Such alternatives, which are applicable for sites not located by the sea or by large rivers, are limited to either injection of tritiated wastewater into suitable deep geological formations, or final disposal into a deep underground repository after adequate treatment similar to other low and intermediate active waste. Removal of tritium from the wastewater by enrichment represents a further feasible option of the second alternative, which allows reduction of the huge volume of tritiated water to be treated before disposal. A significant volume reduction increases the safety of the subsequent steps such as transport, interim storage and final disposal of tritiated waste, furthermore, decreases the corresponding overall waste management cost. The projected Wackersdorf reprocessing plant has been considered as a reference for assessing the permitted tritium releases and other site characteristics. (orig.)

  9. Monitoring of low-level radioactive liquid effluent in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Mizutani, Tomoko; Koarashi, Jun; Takeishi, Minoru

    2009-01-01

    The Tokai reprocessing plant (TRP), the first reprocessing plant in Japan, has discharged low-level liquid wastes to the Pacific Ocean since the start of its operation in 1977. We have performed liquid effluent monitoring to realize an appropriate radioactive discharge control. Comparing simple and rapid analytical methods with labor-intensive radiochemical analyses demonstrated that the gross-alpha and gross-beta activities agreed well with the total activities of plutonium isotopes ( 238 Pu and 239+240 Pu) and major beta emitters (e.g., 90 Sr and 137 Cs), respectively. The records of the radioactive liquid discharge from the TRP showed that the normalized discharges of all nuclides, except for 3 H, were three or four orders of magnitude lower than those from the Sellafield and La Hague reprocessing plants. This was probably due to the installation of multistage evaporators in the liquid waste treatment process in 1980. The annual public doses for a hypothetical person were estimated to be less than 0.2 μSv y -1 from the aquatic pathway. Plutonium radioactivity ratios ( 238 Pu/ 239+240 Pu) of liquid effluents were determined to be 1.3-3.7, while those of the seabed sediment samples collected around the discharge point were 0.003-0.059, indicating no remarkable accumulation of plutonium in the regional aquatic environment. Thus, we concluded that there were no significant radiological effects on the public and the aquatic environment during the past 30-year operation of the TRP. (author)

  10. 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

  11. 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

  12. 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.)

  13. Fuel reprocessing: safety analysis of extraction cycles

    International Nuclear Information System (INIS)

    Dinh, B.; Mauborgne, B.; Baron, P.; Mercier, J.P.

    1991-01-01

    An essential part of the safety analysis related to the extraction cycles of reprocessing plants, is the analysis of their behaviour during steady-state and transient operations, by means of simulation codes. These codes are based on the chemical properties of the main species involved (distribution coefficient and kinetics) and the hydrodynamics inside the contactors (mixer-settlers and pulsed columns). These codes have been consolidated by comparison of calculations with experimental results. The safety analysis is essentially performed in two steps. The first step is a parametric sensitivity analysis of the chemical flowsheet operated: the effect of a misadjustment (flowrate of feed, solvent, etc) is evaluated by successive steady-state calculations. These calculations help the identification of the sensitive parameters for the risk of plutonium accumulation, while indicating the permissible level of misadjustment. These calculations also serve to identify the parameters which should be measured during plant operation. The second step is the study of transient regimes, for the most sensitive parameters related to plutonium accumulation risk. The aim is to confirm the conclusions of the first step and to check that the characteristic process parameters chosen effectively allow, the early and reliable detection of any drift towards a plutonium accumulating regime. The procedures to drive the process backwards to a specified convenient steady-state regime from a drifting-state are also verified. The identification of the sensitive parameters, the process status parameters and the process transient analysis, allow a good control of process operation. This procedure, applied to the first purification cycle of COGEMA's UP3-A La Hague plant has demonstrated the total safety of facility operations

  14. Fast breeder reactor fuel reprocessing in France

    International Nuclear Information System (INIS)

    Bourgeois, M.; Le Bouhellec, J.; Eymery, R.; Viala, M.

    1984-08-01

    Simultaneous with the effort on fast breeder reactors launched several years ago in France, equivalent investigations have been conducted on the fuel cycle, and in particular on reprocessing, which is an indispensable operation for this reactor. The Rapsodie experimental reactor was associated with the La Hague reprocessing plant AT1 (1 kg/day), which has reprocessed about one ton of fuel. The fuel from the Phenix demonstration reactor is reprocessed partly at the La Hague UP2 plant and partly at the Marcoule pilot facility, undergoing transformation to reprocess all the fuel (TOR project, 5 t/y). The fuel from the Creys Malville prototype power plant will be reprocessed in a specific plant, which is in the design stage. The preliminary project, named MAR 600 (50 t/y), will mobilize a growing share of the CEA's R and D resources, as the engineering needs of the UP3 ''light water'' plant begins to decline. Nearly 20 tonnes of heavy metals irradiated in fast breeder reactors have been processed in France, 17 of which came from Phenix. The plutonium recovered during this reprocessing allowed the power plant cycle to be closed. This power plant now contains approximately 140 fuel asemblies made up with recycled plutonium, that is, more than 75% of the fuel assemblies in the Phenix core

  15. 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.)

  16. Reprocessing considerations for a developing country

    International Nuclear Information System (INIS)

    This paper describes some of the alternatives for dealing with spent fuel that face a developing country. It then discusses the considerations that affect decisions on the size and siting of reprocessing plants, and shows how small plants may be suitable in countries without the means to transport spent fuel easily. The paper also outlines the reasons for reprocessing in India, and describes the development of India's reprocessing capability. It shows how the economic conditions in India, such as low skilled labour costs, make reprocessing plants of 100 to 200 tonnes U/yr capacity economic, and includes a table giving technical data on a 100 t U/yr national plant for inclusion in the reference cases used by INFCE Working Group 4

  17. Fast breeder reactor fuel reprocessing R and D: technological development for a commercial plant

    International Nuclear Information System (INIS)

    Colas, J.; Saudray, D.; Coste, J.A.; Roux, J.P.; Jouan, A.

    1987-01-01

    The technological developments undertaken by the CEA are applied to a plant project of a 50 t/y capacity, having to reprocess in particular the SUPERPHENIX 1 reactor fuel. French experience on fast breeder reactor fuel reprocessing is presented, then the 50 t/y capacity plant project and the research and development installations. The R and D programs are described, concerning: head-end operations, solvent extractions, Pu02 conversion and storage, out-of-specification Pu02 redissolution, fission products solution vitrification, conditioning of stainless steel hulls by melting, development of remote operation equipments, study of corrosion and analytical problems

  18. Technical specifications on the welding in fuel reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Karino, Motonobu; Uryu, Mitsuru; Matsui, N.; Nakazawa, Fumio; Imanishi, Makoto; Koizumi; Kazuhiko; Sugawara, Junichi; Tanaka, Hideo

    1999-04-01

    The past specifications SGN of the welding in JNC was reexamined for the reprocessing plants in order to further promote the quality control. The specification first concerns the quality of raw materials, items of the quality tests, material management, and qualification standards of the welders. It extends over details of the welding techniques, welding design, welding testings, inspection and the judgment standards. (H. Baba)

  19. Absorption process for removing krypton from the off-gas of an LMFBR fuel reprocessing plant

    International Nuclear Information System (INIS)

    Stephenson, M.J.; Dunthorn, D.I.; Reed, W.D.; Pashley, J.H.

    1975-01-01

    The Oak Ridge Gaseous Diffusion Plant selective absorption process for the collection and recovery of krypton and xenon is being further developed to demonstrate, on a pilot scale, a fluorocarbon-based process for removing krypton from the off-gas of an LMFBR fuel reprocessing plant. The new ORGDP selective absorption pilot plant consists of a primary absorption-stripping operation and all peripheral equipment required for feed gas preparation, process solvent recovery, process solvent purification, and krypton product purification. The new plant is designed to achieve krypton decontamination factors in excess of 10 3 with product concentration factors greater than 10 4 while processing a feed gas containing typical quantities of common reprocessing plant off-gas impurities, including oxygen, carbon dioxide, nitrogen oxides, water, xenon, iodine, and methyl iodide. Installation and shakedown of the facility were completed and some short-term tests were conducted early this year. The first operating campaign using a simulated reprocessing plant off-gas feed is now underway. The current program objective is to demonstrate continuous process operability and performance for extended periods of time while processing the simulated ''dirty'' feed. This year's activity will be devoted to routine off-gas processing with little or no deliberate system perturbations. Future work will involve the study of the system behavior under feed perturbations and various plant disturbances. (U.S.)

  20. Cogema in 1996: increasing turnover and stable net results

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    This short article gives some financial informations about the Cogema group for 1996. The net result for 1996 reached 977 millions of French Francs (FF) with respect to 973 for the previous year. The turnover reached 34.427 billions of FF in 1996 and 30.611 in 1995, which represents a 12.5% growth. In the mining sector, the turnover has decreased to 2.853 billions of FF with respect to 3.238 in 1995. In the engineering and industry services sector the turnover of the overall companies, with the exception of Cogema, has considerably progressed (2.199 billions of FF in 1996, 1.738 in 1995). (J.S.)

  1. A new organisation for the Cogema group

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The Cogema group hopes to find a second business, being awaiting the nuclear area starts again. It needs eighteen months to find it. It must have an empathy with its first business and does not be in competition with its customers. (N.C.)

  2. Alternative reprocessing schemes evaluation

    International Nuclear Information System (INIS)

    1979-02-01

    This paper reviews the parameters which determine the inaccessibility of the plutonium in reprocessing plants. Among the various parameters, the physical and chemical characteristics of the materials, the various processing schemes and the confinement are considered. The emphasis is placed on that latter parameter, and the advantages of an increased confinement in the socalled PIPEX reprocessing plant type are presented

  3. COGEMA in Niger. Inquiry report on the situation of workers of SOMAiR and COMINAK, Niger's subsidies of the AREVA-COGEMA group

    International Nuclear Information System (INIS)

    2005-01-01

    After having briefly recalled the activities of COGEMA's subsidies in Niger, presented the context of the inquiry, and made some remarks about COGEMA's attitude with respect to this inquiry, this report gives an extremely critical analysis of security measures and working conditions: non existent information about risks related to radioactivity, non existent or insufficient security equipment, exposure of workers to ionizing radiation by water, ignored security orders, random dosimetry controls. The second part recalls the radiological risks present in uranium mines, gives a critical analysis of the worker medical follow-up quality, considers as inexplicable the absence of professional diseases, and discusses the issue of work accidents. It finally outlines that control structures (Mine Direction, Work Inspection) are inadequate

  4. Potential fire or explosion risks in reprocessing plants

    International Nuclear Information System (INIS)

    Lefort, G.

    1983-05-01

    Installation for reprocessing are large chemical plants handling large quantities of inflammable solvents and products allowing large risk of fire. Further, the chemical process involves the use of oxidizer and reducer agents which can have a very strong chemical activity and by certain circumstances create overpressures or large explosions. This paper shows the principal radioactive consequences we can retain in safety analyses. As an example the combustion phenomenon involved in a solid waste storage silo with irradiated uranium traces is described [fr

  5. 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.)

  6. A comprehensive fuel nuclide analysis at the reprocessing plant

    International Nuclear Information System (INIS)

    Arenz, H.J.; Koch, L.

    1983-01-01

    The composition of spent fuel can be determined by various methods. They rely partially on different information. Therefore the synopsis of the results of all methods permits a detection of systematic errors and their explanation. Methods for determining the masses of fuel nuclides at the reprocessing input point range from pure calculations (shipper data) to mere experimental determinations (volumetric analysis). In between, a mix of ''fresh'' experimental results and ''historical'' data is used to establish a material balance. Deviations in the results obtained by the individual methods can be attributed to the information source, which is unique for the method in question. The methodology of the approach consists of three steps: by paired comparison of the operator analysis (usually volumetric or gravimetric) with remeasurements the error components are determined on a batch-by-batch basis. Using the isotope correlation technique the operator data as well as the remeasurements are checked on an inter-batch basis for outliers, precision and bias. Systematic errors can be uncovered by inter-lab comparison of remeasurements and confirmed by using historical information. Experience collected during the reprocessing of LWR fuel at two reprocessing plants prove the flexibility and effectiveness of this approach. An example is presented to demonstrate its capability in detecting outliers and determining systematic errors. (author)

  7. Remote maintenance in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Herndon, J.N.

    1985-01-01

    Remote maintenance techniques applied in large-scale nuclear fuel reprocessing plants are reviewed with particular attention to the three major maintenance philosophy groupings: contact, remote crane canyon, and remote/contact. Examples are given, and the relative success of each type is discussed. Probable future directions for large-scale reprocessing plant maintenance are described along with advanced manipulation systems for application in the plants. The remote maintenance development program within the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory is also described. 19 refs., 19 figs

  8. 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

  9. Melter operation results in chemical test at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Kanehira, Norio; Yoshioka, Masahiro; Muramoto, Hitoshi; Oba, Takaaki; Takahashi, Yuji

    2005-01-01

    Chemical Test of the glass melter system of the Vitrification Facility at Rokkasho Reprocessing Plant (RRP) was performed. In this test, basic performance of heating-up of the melter, melting glass, pouring glass was confirmed using simulated materials. Through these tests and operation of all modes, good results were gained, and training of operators was completed. (author)

  10. Present status of fuel reprocessing plant in PNC

    International Nuclear Information System (INIS)

    Koyama, Kenji

    1981-01-01

    In the fuel reprocessing plant of the Power Reactor and Nuclear Fuel Development Corporation, its hot test has now been completed. For starting its full-scale operation duly, the data are being collected on the operation performance and safety. The construction was started in June, 1971, and completed in October, 1974. In July, 1977, spent fuel was accepted in the plant, and the hot test was started. In September, the same year, the first fuel shearing was made. So far, a total of about 31 t U from both BWR and PWR plants has been processed, thus the hot test was entirely completed. The following matters are described: hot test and its results, research on Pu and U mixed extraction, utilization of product plutonium, development of safeguard technology, and repair work on the acid recovery evaporation tank. (J.P.N.)

  11. 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)

  12. Safety demonstration tests of postulated solvent fire accidents in extraction process of a fuel reprocessing plant, (2)

    International Nuclear Information System (INIS)

    Tukamoto, Michio; Takada, Junichi; Koike, Tadao; Nishio, Gunji; Uno, Seiichiro; Kamoshida, Atsusi; Watanabe, Hironori; Hashimoto, Kazuichiro; Kitani, Susumu.

    1992-03-01

    Demonstration tests of hypothetical solvent fire in an extraction process of the reprocessing plant were carried out from 1984 to 1985 in JAERI, focusing on the confinement of radioactive materials during the fire by a large-scale fire facility (FFF) to evaluate the safety of air-ventilation system in the plant. Fire data from the demonstration test were obtained by focusing on fire behavior at cells and ducts in the ventilation system, smoke generation during the fire, transport and deposition of smoke containing simulated radioactive species in the ventilation system, confinement of radioactive materials, and integrity of HEPA filters by using the FFF simulating an air-ventilation system of the reference reprocessing plant in Japan. The present report is published in a series of the report Phase I (JAERI-M 91-145) of the demonstration test. Test results in the report will be used for the verification of a computer code FACE to evaluate the safety of postulated fire accidents in the reprocessing plant. (author)

  13. Management of regenerant effluent waste at reprocessing plant, Tarapur- a new approach

    Energy Technology Data Exchange (ETDEWEB)

    Chandra, Munish; Bajpai, D D; Mudaiya, Avinash; Varadarajan, N [Power Reactor Fuel Reprocessing Plant, Tarapur (India)

    1994-06-01

    Power Reactor Fuel Reprocessing (PREFRE) Plant, Tarapur has been processing zircaloy clad spent fuel arising from PHWR namely RAPS and MAPS. The plant has been provided with a water pool to receive and store the irradiated fuel assemblies from the reactor site for an interim period before they are taken up for chop-leach and further reprocessing by PUREX process. This paper highlights the important and innovative modifications like introduction of a cation exchanger for water polishing and using nitric acid as regenerant. The regenerant effluent (nitric acid) is recycled to the main process cells where it is mixed and further treated along with process waste stream. This is a step towards minimising effluent generation. The paper describes the advantages of modified system like operational simplification, manpower, man-rem saving and minimising release of activity to environment. 3 figs., 4 tabs.

  14. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Shirley J.; Ehinger, Michael

    2010-08-07

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

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

    International Nuclear Information System (INIS)

    Johnson, Shirley J.; Ehinger, Michael

    2010-01-01

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

  17. Process analysis in a THTR trial reprocessing plant

    International Nuclear Information System (INIS)

    Brodda, B.G.; Filss, P.; Kirchner, H.; Kroth, K.; Lammertz, H.; Schaedlich, W.; Brocke, W.; Buerger, K.; Halling, H.; Watzlawik, K.H.

    1979-01-01

    The demands on an analytical control system for a THTR trial reprocessing plant are specified. In a rather detailed example, a typical sampling, sample monitoring and measuring process is described. Analytical control is partly automated. Data acquisition and evaluation by computer are described for some important, largely automated processes. Sample management and recording of in-line and off-line data are carried out by a data processing system. Some important experiments on sample taking, sample transport and on special analysis are described. (RB) [de

  18. Annual report on the environmental radiation monitoring around Tokai Reprocessing Plant. FY 2001. Document on present state of affairs

    International Nuclear Information System (INIS)

    Shinohara, Kunihiko; Takeishi, Minoru; Miyagawa, Naoto

    2002-06-01

    Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on ''Safety Regulations for the Tokai Reprocessing Plant, Chapter IV - Environmental Monitoring''. This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant during April 2001 to March 2002. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant. (author)

  19. Experience and trends at the Belgonucleaire plant

    International Nuclear Information System (INIS)

    Deramaix, P.; Eeckhout, F.; Pay, A.; Pelckmans, E.

    2000-01-01

    The BN Dessel plant started operation in 1973. During the initial period (up to 1984), the plant was equipped to fabricate FBR as well as LWR fuel (5 tHM/year) within the framework of LWR demonstration and FBR programmes. The first ten years of operation have laid down the basis for all modifications or improvements in the fields of fuel fabrication and control processes, waste management, safety and safeguards, which were implemented in the 1984-1985 refurbishment. On this occasion, the MIMAS fabrication process has been introduced to make MOX fuel reprocessable in the operating conditions of the modern reprocessing plants (COGEMA in La Hague and BNFL in Sellafield) and the capacity of the plant has been upgraded to the current nominal capacity of 35 tHM per year (with a maximum licensed of 40 tHM per year). The nominal fabrication capacity was achieved in 1989, maintained consistently since then at least at that level, approaching even the license limit. The process has proved its high flexibility, in particular in terms of the large variety of MOX manufactured for both PWRs (14 x 14, 15 x 15, 16 x 16, 17 x 17, types) and BWRs (8 x 8, 9 x 9, 10 x 10 types), of the size of the campaign (from less than 4 tHM to 28 tHM), of the origin of the PuO 2 (from COGEMA and BNFL reprocessing plants, Pu from second generation), of the Pu content (up to 8.6 w/o in HM). From 1986 up to the end of March 1999, more than 21 t Pu as PuO 2 have been processed into more than 388 tHM of MIMAS fuel, delivered or to be delivered for use in 796 PWR assemblies and 184 BWR assemblies for 21 large power reactors (17 PWRs and 4 BWRs) in 5 countries (France, Germany, Switzerland, Japan, Belgium). The MOX fuel produced has been demonstrated to reach at least the same performance as the UO 2 fuel used simultaneously in the same reactors. An increasing number of the MOX assemblies are discharged at a burnup of at least 45 GWd/tHM assembly average. One assembly reached 51 GWd/tHM assembly average

  20. Contribution to the study of the degradation of the solvent used in a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Goasmat, F.

    1984-01-01

    The degradation of a mixed solvent (tributylphosphate - hydrocarbons) in a fuel reprocessing plant (UP 2 at La Hague, France) is studied in this thesis. Laboratory studies on degradation mechanisms, decomposition products and regeneration processes are reviewed in a bibliographic synthesis. Solvent degradation is investigated on a real solvent from a reprocessing plant. Influence of degradation on solvent performance is shown and regeneration processes should be improved. Many regeneration processes are tested on solvent from the plant and results are discussed. Separation and analysis of degradation products show the polyfunctional structure of compounds formed [fr

  1. PSA application on the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Ishida, Michihiko; Nakano, Takafumi; Morimoto, Kazuyuki; Nojiri, Ichiro

    2003-01-01

    The Periodic Safety Review (PSR) of the Tokai Reprocessing Plant (TRP) has been carrying out to obtain an overall view of actual plant safety. As a part of the PSR, Probabilistic Safety Assessment (PSA) methodology has been applied to evaluate the relative importance of safety functions that prevent the progress of events causing to postulated accidents. Based on the results of the safety reassessments of the TRP that was carried out in 1999, event trees were developed to model sequences of postulated accidents. Event trees were quantified by using the results of fault tree analysis and human reliability analysis. In the quantification, the reliability data generally used in PSA of nuclear power plants were mainly used. Operating experiences of the TRP were also utilized to evaluated both component/system reliability and human reliability. The relative importance of safety functions was evaluated by using two major importance measures, Fussell-Vesely and Risk Achievement Worth both generally used in PSA of nuclear power plants. Through these evaluations, some useful insights into the safety of the TRP have been obtained. The results of the relative importance measures would be utilized to qualify TRP component/equipment important to the safety. (author)

  2. Optimal installation program for reprocessing plants

    International Nuclear Information System (INIS)

    Kubokawa, Toshihiko; Kiyose, Ryohei

    1976-01-01

    Optimization of the program of installation of reprocessing plants is mathematically formulated as problem of mixed integer programming, which is numerically solved by the branch-and-bound method. A new concept of quasi-penalty is used to obviate the difficulties associated with dual degeneracy. The finiteness of the useful life of the plant is also taken into consideration. It is shown that an analogous formulation is possible for the cases in which the demand forecasts and expected plant lives cannot be predicted with certainty. The scale of the problem is found to have kN binary variables, (k+2)N continuous variables, and (k+3)N constraint conditions, where k is the number of intervals used in the piece-wise linear approximation of a nonlinear objective function, and N the overall duration of the period covered by the installation program. Calculations are made for N=24 yr and k=3, with the assumption that the plant life is 15 yr, the plant scale factor 0.5, and the maximum plant capacity 900 (t/yr). The results are calculated and discussed for four different demand forecasts. The difference of net profit between optimal and non-optimal installation programs is found to be in the range of 50 -- 100 M$. The pay-off matrix is calculated, and the optimal choice of action when the demand cannot be forecast with certainty is determined by applying Bayes' theory. The optimal installation program under such conditions of uncertainty is obtained also with a stochastic mixed integer programming model. (auth.)

  3. Fast reactor fuel reprocessing in the UK

    International Nuclear Information System (INIS)

    Allardice, R.H.; Williams, J.; Buck, C.

    1977-01-01

    Enriched uranium metal fuel irradiated in the Dounreay Fast Reactor has been reprocessed and refabricated in plants specifically designed for the purpose in the U.K. since 1961. Efficient and reliable fuel recycle is essential to the development of a plutonium based fast reactor system and the importance of establishing at an early stage fast reactor fuel reprocessing has been reinforced by current world difficulties in reprocessing high burn-up thermal reactor oxide fuel. In consequence, the U.K. has decided to reprocess irradiated fuel from the 250 MW(E) Prototype Fast Reactor as an integral part of the fast reactor development programme. Flowsheet and equipment development work for the small scale fully active demonstration plant have been carried out over the past 5 years and the plant will be commissioned and ready for active operation during 1977. In parallel, a comprehensive waste management system has been developed and installed. Based on this development work and the information which will arise from active operation of the plant a parallel development programme has been initiated to provide the basis for the design of a large scale fast reactor fuel reprocessing plant to come into operation in the late 1980s to support the projected U.K. fast reactor installation programme. The paper identifies the important differences between fast reactor and thermal reactor fuel reprocessing technologies and describes some of the development work carried out in these areas for the small scale P.F.R. fuel reprocessing operation. In addition, the development programme in aid of the design of a larger scale fast reactor fuel reprocessing plant is outlined and the current design philosophy is discussed

  4. Reprocessing-conditioning-recycling: A competitive industry at the service of the utilities

    International Nuclear Information System (INIS)

    Giraud, J.P.; Devezeaux de Lavergne, J.G.

    1997-01-01

    In order to answer to the future energy needs, the countries who have chosen nuclear power as a main energy source, have also opted for an optimisation of their policy through the Reprocessing-Conditioning-Recycling (RCR) strategy. The RCR industry is today totally mature and comprehensive thanks to proven industrial means for reprocessing through the UP3 and UP2-800 plants of the la Hague site and for Mixed Oxide fuel (Mox) supply. The optimisation of the RCR industry following the chromological logic of the fuel cycle development, has now focused on two main items: The fabrication of the Mox fuel and the management of the residues with a notably drastic reduction of the total volume of residues. From 1990 to 1994, several studies of the total fuel cycle cost have been carried out; German studies generally concluded to a potential advantage of the Direct Disposal option compared to the RCR strategy. But a 1996 Cogema-study, integrating the most recent data and based on a cost model of the complete fuel cycle, has shown (like the 1994 OECD study) very similar costs between the two options. Thanks to the industry optimisation, the RCR strategy has allowed to decrease the fuel cycle cost to a very low level of 1,5 Pf/kWh. The RCR strategy is economically competitive and less sensitive to price variations. Furthermore, it is immediately available for the utilities who consequently take advantage of a global service with firm prices. (orig.) [de

  5. 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.)

  6. Statement on the Consolidated Fuel Reprocessing Program

    International Nuclear Information System (INIS)

    Trauger, D.B.

    1984-01-01

    Oak Ridge National Laboratory has chosen the following objectives for future reprocessing plant design: reduced radiation exposure to workers; minimal environmental impact; improved plant operation and maintenance; improved accountability; no plutonium diversion; and reduced overall capital and operating cost. These objectives lead to a plant with totally remote operation. The Breeder Reactor Engineering Test (BRET) has been designed to perform a key role in demonstrating advanced reprocessing technology. It has been scheduled to be available to reprocess spent fuel from the Fast Flux Test Facility. The principal features of the Consolidated Fuel Reprocessing Program and of the BRET facility are appropriate for all reactor types

  7. Moving the largest capacity PWR dual-purpose cask in the world from Goesgen NPP to the Zwilag interim storage site

    International Nuclear Information System (INIS)

    Delannay, M.; Dudragne, S.

    2002-01-01

    The Swiss Goesgen nuclear power plant (NPP) has decided to use two different methods for the disposal of its spent fuel. (1) To reprocess some of its spent fuel in dedicated facilities. Some of the vitrified waste from the reprocessing will be shipped back to Switzerland using the new COGEMA Logistics, TN81 cask. (2) To ship the other part of its spent fuel to the central interim storage facility of Zwilag (Switzerland) using a COGEMA Logistics dual-purpose TN24G cask. The TN24G is the heaviest and largest dual-purpose cask manufactured so far by COGEMA Logistics in Europe. It is intended for the transport and storage of 37 pressurised water-reactor (PWR) spent fuel assemblies. Four casks were delivered by COGEMA Logistics to Goesgen NPP. Three transports of loaded TN24G casks between Goesgen and Zwilag were successfully performed at the beginning of 2002 with the new COGEMA Logistics Q76 wagon specifically designed to transport heavy casks. This article describes the procedure of operations and shipments for the first TN24G casks up to storage at Zwilag. The fourth transport of loaded TN24G was due to happen in October 2002. The TN24G cask, as part of the TN24 casks family, proved to be a very efficient solution for the KKG spent fuel management. (author)

  8. 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.)

  9. 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

  10. 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)

  11. Spent solvent treatment process at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Sasaki, Akihiro; Saka, Munenori; Araya, Toshiyuki; Kitamura, Tomohiro; Wakamatsu, Toshiyuki

    2005-01-01

    In order to dispose of spent organic solvent and diluent produced by the PUREX method, it is desirable that it should be in stable form for easy handling. For this reason, spent solvent is reduced to powder form and further molded so that it becomes easier to handle for temporary storage at Rokkasho Reprocessing Plant (RRP). In this paper, the treatment unit for reducing spent solvent to powder form and the treatment unit for modeling the powder are introduced as well as their treatment results during Chemical Test. (author)

  12. Government on the spot over Sellafield's reprocessing plant

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The 18-year gestation of British Nuclear Fuels' Thermal Oxide Reprocessing Plant (THORP) is almost at an end. Only one hurdle seemingly remains - the authorisation to dispose of its wastes. Opponents see this as the last chance to scrap what they regard as an environmental and financial white elephant. BNF's original rationale for THORP has grown increasingly threadbare since it was proposed in the mid-1970s - and the Government may now be forced into a last-minute rethink of the consequences of allowing it to be commissioned. (Author)

  13. A study on graded approach for risk assessment of the Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Shoji, Tatsuro; Kohata, Yuuji; Takebe, Kazumi; Tamauchi, Yoshikazu; Hayashi, Kazuya; Kurosu, Katsuya

    2005-01-01

    In a reprocessing plant, radioactive materials exist in several chemical processes and storage facilities, therefore we should evaluate risks of many events with various types, scenarios, frequencies and consequences in order to assess total risk of the plant. In order to assess risks of many events efficiently and effectively, the 'Graded Approach' should be applied to the assessment method taking account of importance of the consequence, complexity of scenarios and necessitated uncertainty. Therefore, we have developed a simplified quantitative method, so-called the 'improved risk index method', based on the 'risk index method' recommended by US NRC as qualitative risk evaluation method for 'Integrated safety analysis (ISA)' of fuel cycle facilities, to enhance quantitability, consistency and traceability in evaluation. The results of the 'improved risk index method' well agree with the detailed PSA in spite of the simplification. We will use this method in combination with the detailed PSA method, and will use the results for risk-informed management/regulation of the Rokkasho reprocessing plant. (author)

  14. 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

  15. The conditioned reprocessing waste returns. An overview of the question

    International Nuclear Information System (INIS)

    Donato, A.

    1987-01-01

    Although the spent nuclear fuel reprocessing is at present under careful reconsideration and analysis in several countries, the economics, the environmental and health protection aspects being taken into consideration by many experts, it is nevertheless currently carried out in Great Britain and in France as a commercial service offered to the domestic utilities an to foreign customers, according to the contracts and the agreements signed in the past. Such contracts have been signed with COGEMA and/or BNFL by seven countries: Germany, Sweden, Japan, Belgium, Switzerland, Italy, Holland. As a consequence of this, a big number of high level radioactive glass containers and of cemented and bituminized waste will be returned in order to be stored and disposed off in these European countries and in Japan. The disposal of the conditioned wastes will only be possible if their characteristics comply with the acceptance criteria established or to be established in each customer country. A brief review of the situation will be presented in this paper, particular attention being given to the problems possibly arising from the acceptance point of view of the different reprocessing waste categories

  16. Closing the fuel cycle

    International Nuclear Information System (INIS)

    Aycoberry, C.; Rougeau, J.P.

    1987-01-01

    The progressive implementation of some key nuclear fuel cycle capecities in a country corresponds to a strategy for the acquisition of an independant energy source, France, Japan, and some European countries are engaged in such strategic programs. In France, COGEMA, the nuclear fuel company, has now completed the industrial demonstration of the closed fuel cycle. Its experience covers every step of the front-end and of the back-end: transportation of spent fuels, storage, reprocessing, wastes conditioning. The La Hague reprocessing plant smooth operation, as well as the large investment program under active progress can testify of full mastering of this industry. Together with other French and European companies, COGEMA is engaged in the recycling industry, both for uranium through conversion of uranyl nitrate for its further reeichment, and for plutonium through MOX fuel fabrication. Reprocessing and recycling offer the optimum solution for a complete, economic, safe and future-oriented fuel cycle, hence contributing to the necessary development of nuclear energy. (author)

  17. 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)

  18. Capital and operating costs of irradiated natural uranium reprocessing plants

    International Nuclear Information System (INIS)

    Thiriet, L.; Jouannaud, C.; Couture, J.; Duboz, J.

    1966-01-01

    This paper presents first a method of analysing natural uranium reprocessing plants investment costs (method similar to LANG and BACH well known in the fuel oil industry) and their operating costs (analysed according to their economic type). This method helps establishing standard cost structures for these plants, allowing thus comparisons between existing or planned industrial facilities. It also helps evaluating the foreseeable consequences of technical progress. Some results obtained are given, concerning: the investment costs sensitivity to the various technical parameters defining the fuel and their comparison according to the country or the economic area taken into account. Finally, the influence of the plants size on their investment costs is shown. (author) [fr

  19. Zirconium-made equipment for the new La Hague reprocessing plants

    International Nuclear Information System (INIS)

    Decours, J.; Demay, R.; Bernard, C.; Mouroux, J.P.; Simonnet, J.

    1991-01-01

    The use of zirconium was developed to solve some problems of severe corrosion in boiling nitric medium, and to guarantee the service life of the equipment concerned. The paper presents the experience gained since the early 1970s, when the first units made of zirconium were used in French reprocessing plants. For the new La Hague UP3 and UP2 800 plants, it was decided to extend the use of zirconium to make large-scale equipment and, to do so, a major R and D program was implemented, of which the main results are presented

  20. French experience of regulation and operation on reprocessing facilities of LWR spent fuels

    Energy Technology Data Exchange (ETDEWEB)

    Mercier, J P [DES/SESUL (France)

    1992-02-01

    conformable to the whole documents (reports and operating rules) analyzed during safety assessment. The procedure for commissioning of UP3-A reprocessing plant of the La Hague COGEMA establishment associates two approaches: a technical one, based on safety assessment of the facility (normal operating, incidents and accidents); an administrative one, involving to take the advice of the public, of the local authorities and of the competent ministries. The operator must demonstrate that the design is in agreement with the safety regulations. These regulations require compliance with the ALARA principle and limiting values for exposure of staff and public. In other respects, the operator studied all foreseeable incident and accident situations whose occurrence reduces the safety of the facility, the forerunner events originating inside the installations or being specific to the site. The ability of the systems to ensure a safety level satisfactory in all plausible circumstances has been validated using deterministic and (whenever probabilities can be calculated with adequate accuracy) probabilistic approaches. (author)

  1. 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

  2. Monitoring of released radioactive gaseous and liquid effluent at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Oka, M.; Keta, S.; Nagai, S.; Kano, M.; Ishihara, N.; Moriyama, T.; Ogaki, K.; Noda, K.

    2009-01-01

    Rokkasho Reprocessing Plant (RRP) Rokkasho Reprocessing Plant started its active tests with spent fuel at the end of March 2006. When spent fuels are sheared and dissolved, radioactive gaseous effluent and radioactive liquid effluent such as krypton-85, tritium, etc. are released into the environment. In order to limit the public dose as low as reasonably achievable in an efficient way, RRP removes radioactive material by evaporation, rinsing, filtering, etc., and then releases it through the main stack and the sea discharge pipeline that allow to make dispersion and dilution very efficiently. Also, concerning the radioactive gaseous and liquid effluent to be released into the environment, the target values of annual release have been defined in the Safety Rule based on the estimated annual release evaluated at the safety review of RRP. By monitoring the radioactive material in gaseous exhaust and liquid effluent RRP controls it not to exceed the target values. RRP reprocessed 430 tUpr of spent fuel during Active Test (March 2006 to October 2008). In this report, we report about: The outline of gaseous and liquid effluent monitoring. The amount of radioactive gaseous and liquid effluent during the active test. The performance of removal of radioactive materials in gaseous and liquid effluents. The impact on the public from radioactive effluents during the active test. (author)

  3. 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.).

  4. 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)

  5. Use of fuel reprocessing plant instrumentation for international safeguards

    International Nuclear Information System (INIS)

    Ayers, A.L.

    1977-01-01

    The International Atomic Energy Agency has a program for developing instrumentation to be used by safeguards inspectors at reprocessing facilities. These instruments have generally been individual pieces of equipment for improving the accuracy of existing measurement instrumentation or equipment to perform nondestructive assay on a selected basis. It is proposed that greater use be made of redundant plant instrumentation and data recovery systems that could augment plant instrumentation to verify the validity of plant measurements. Use of these methods for verfication must be proven as part of an operating plant before they can be relied upon for safeguards surveillance. Inspectors must be qualified in plant operations, or have ready access to those so qualified, if the integrity of the operation is to be properly assessed. There is an immediate need for the development and in-plant proof testing of an integrated gamma, passive neutron, and active neutron measurement system for drum quantities of radioactive trash. The primary safeguards effort should be limited to plutonium and highly enriched uranium

  6. Safeguards implementation in UP3 reprocessing plant

    International Nuclear Information System (INIS)

    Laurent, J.P.; Regnier, J.; Talbourdet, Y.; De Jong, P.

    1991-01-01

    The implementation of safeguards in a large size reprocessing plant is a challenge, considering the high throughput of nuclear material and the sophisticated automation of such facilities. In the case of UP3, a pragmatic and realistic approach has been devised and is applied through an efficient cooperation between the safeguards organizations, the french national authorities and the operator. In essence, they consist in verification of every significant inputs and outputs, in timely analysis by NDA (e.g. solutions of dissolution through an on site k-edge equipment), in monitoring selected parts of the inprocess inventory and in specific containment/surveillance systems for the spent fuel storage ponds and the PuO2 storage. (author)

  7. Krypton 85 at La Hague; Krypton 85 a La Hague

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    The gaseous effluents from the fuel reprocessing plant of Cogema-La Hague (France) are regularly measured and controlled. This paper reports on three press releases: the one of Cogema from November 6, 1998 concerning the impact of these effluents and the results of {sup 85}Kr measurements performed in the vicinity of the facility, and the two communiques of the French office of protection against ionizing radiations (OPRI) from November 13 and 20, 1998 relative to the environmental and human impacts of the {sup 85}Kr releases from the La Hague facility. (J.S.)

  8. Krypton 85 at La Hague

    International Nuclear Information System (INIS)

    1998-11-01

    The gaseous effluents from the fuel reprocessing plant of Cogema-La Hague (France) are regularly measured and controlled. This paper reports on three press releases: the one of Cogema from November 6, 1998 concerning the impact of these effluents and the results of 85 Kr measurements performed in the vicinity of the facility, and the two communiques of the French office of protection against ionizing radiations (OPRI) from November 13 and 20, 1998 relative to the environmental and human impacts of the 85 Kr releases from the La Hague facility. (J.S.)

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

    International Nuclear Information System (INIS)

    Herrmann, F.J.; Herrmann, B.; Hoeflich, V.

    1997-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-08-01

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

  11. 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.)

  12. Development and demonstration of near-real-time accounting systems for reprocessing plants

    International Nuclear Information System (INIS)

    Cobb, D.D.; Hakkila, E.A.; Dayem, H.A.; Shipley, J.P.; Baker, A.L.

    1981-01-01

    A program to develop and demonstrate near-real-time accounting systems for reprocessing plants has been active at Los Alamos since 1976. The technology has been developed through modeling and simulation of process operation and measurement systems and evaluation of these data using decision analysis techniques. Aspects of near-real-time systems have been demonstrated successfully at the AGNS reprocessng plant as part of a joint study of near-real-time accounting

  13. 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

  14. Remote handling developments for inspection and repair of highly active reprocessing plant

    International Nuclear Information System (INIS)

    Jones, E.L.

    1988-01-01

    Having the capability to carry out regular and comprehensive inspection of active plant can have benefits beyond the need to satisfy the possible requirements of National Regulatory Authorities. Intermediate inspection can provide qualitative data on the state of the plant, whilst regular inspection can provide quantitative data on which to base predictive judgments. Information of this sort can allow confidence in predicting the actual life of the plant as opposed to the theoretical. The following paper addresses the areas of plant inspection and repair by reference to specific projects either already completed or at an advanced stage of development at BNFL's Sellafield reprocessing plant. (author)

  15. Fast-reactor fuel reprocessing in the United Kingdom

    International Nuclear Information System (INIS)

    Allardice, R.H.; Buck, C.; Williams, J.

    1977-01-01

    Enriched uranium metal fuel irradiated in the Dounreay Fast Reactor has been reprocessed and refabricated in plants specifically designed for the purpose in the United Kingdom since 1961. Efficient and reliable fuel recycle is essential to the development of a plutonium-based fast-reactor system, and the importance of establishing at an early stage fast-reactor fuel reprocessing has been reinforced by current world difficulties in reprocessing high-burnup thermal-reactor oxide fuel. The United Kingdom therefore decided to reprocess irradiated fuel from the 250MW(e) Prototype Fast Reactor (PFR) as an integral part of the fast reactor development programme. Flowsheet and equipment development work for the small-scale fully active demonstration plant has been carried out since 1972, and the plant will be commissioned and ready for active operation during 1977. In parallel, a comprehensive waste-management system has been developed and installed. Based on this development work and the information which will arise from active operation of the plant, a parallel development programme has been initiated to provide the basis for the design of a large-scale fast-reactor fuel-reprocessing plant to come into operation in the late 1980s to support the projected UK fast-reactor installation programme. The paper identifies the important differences between fast-reactor and thermal-reactor fuel-reprocessing technologies and describes some of the development work carried out in these areas for the small-scale PFR fuel-reprocessing operation. In addition, the development programme in aid of the design of a larger scale fast-reactor fuel-reprocessing plant is outlined and the current design philosophy discussed. (author)

  16. Results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal

    International Nuclear Information System (INIS)

    Galkin, A.V.; Baldov, A.N.

    2001-01-01

    In the paper the results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal are presented. Ground for the examination conducting was Health of Nation Programme ratified by the President and a number of Governmental decisions. The special plant is planned in the Mangystau Region. In the framework of feasibility study the data base by the worldwide known technologies was implemented, on reprocessing and experience of radioactive waste disposal. The technical requirements for the special plant construction are determined. The alternative options by structure content and site location of the special plant and radioactive waste disposal are cited

  17. Nuclear fuel transport and particularly spent fuel transport

    International Nuclear Information System (INIS)

    Lenail, B.

    1986-01-01

    Nuclear material transport is an essential activity for COGEMA linking the different steps of the fuel cycle transport systems have to be safe and reliable. Spent fuel transport is more particularly examined in this paper because the development of reprocessing plant. Industrial, techmical and economical aspects are reviewed [fr

  18. The treatment of liquid effluents of reprocessing plants by a chemical process: French experience

    International Nuclear Information System (INIS)

    Fernandez, N.; Taillard, D.

    1977-01-01

    The goal of radioactive effluent processing is to obtain a liquid with a residual activity level allowing disposal and a minimum amount of slurries. Insolubilization methods used in France are described to eliminate fission products in reprocessing plants effluents i.e. strontium, cesium, ruthenium and antimony; others radioelements are generally carried away with others precipitates. Evolution of the process is expressed in terms of reprocessing needs and improvements. Decontamination factors better than 100 are now possible with concentration factors between 30 and 50 [fr

  19. Safeguarding of large scale reprocessing and MOX plants

    International Nuclear Information System (INIS)

    Howsley, R.; Burrows, B.; Longevialle, H. de; Kuroi, H.; Izumi, A.

    1997-01-01

    In May 97, the IAEA Board of Governors approved the final measures of the ''93+2'' safeguards strengthening programme, thus improving the international non-proliferation regime by enhancing the effectiveness and efficiency of safeguards verification. These enhancements are not however, a revolution in current practices, but rather an important step in the continuous evolution of the safeguards system. The principles embodied in 93+2, for broader access to information and increased physical access already apply, in a pragmatic way, to large scale reprocessing and MOX fabrication plants. In these plants, qualitative measures and process monitoring play an important role in addition to accountancy and material balance evaluations in attaining the safeguard's goals. This paper will reflect on the safeguards approaches adopted for these large bulk handling facilities and draw analogies, conclusions and lessons for the forthcoming implementation of the 93+2 Programme. (author)

  20. 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.)

  1. 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

  2. Experience of in-cell visual inspection using CCD camera in hot cell of Reprocessing Plant

    International Nuclear Information System (INIS)

    Reddy, Padi Srinivas; Amudhu Ramesh Kumar, R.; Geo Mathews, M.; Ravisankar, A.

    2013-01-01

    This paper describes the selection, customization and operating experience of the visual inspection system for the hot cell of a Reprocessing Plant. For process equipment such as fuel chopping machine, dissolver, centrifuge, centrifugal extractors etc., viewing of operations and maintenance using manipulators is required. For this, the service of in-cell camera is essential. The ambience of the hot cell of Compact facility for Reprocessing of Advanced fuels in Lead cell (CORAL) for the reprocessing of fast reactor spent fuel has high gamma radiation and acidic vapors. Black and white Charge Coupled Device (CCD) camera has been used in CORAL incorporating in-house modifications to suit the operating ambient conditions, thereby extending the operating life of the camera. (author)

  3. Return of vitrified residues from France to Japan

    International Nuclear Information System (INIS)

    1995-08-01

    For more than 15 years now, COGEMA facilities in La Hague have received, stored and reprocessed spent fuel from France, Japan and other countries: Germany, Switzerland, Belgium and the Netherlands. According to contracts, COGEMA ensures the reprocessing service, consisting in separating the recyclable products (uranium and plutonium) from the wastes which are then duly conditioned and returned to their owners for final disposal. The transportation aspects of returning the reprocessed residues to Japan is presented. (K.A.)

  4. Extraction process technology for the new reprocessing plants in France and Japan

    International Nuclear Information System (INIS)

    Boullis, B.; Drain, F.; Hugelman, D.

    1991-01-01

    The new reprocessing plants UP3 and UP2-800 in France and Rokkasho in Japan use or will use an improved technology for their extraction cycles. The equipment selected are pulse columns (cylindrical and annular) and mixer-settlers (normal type and extra-flat type). This paper presents the equipment selected for each plant and the extensive R and D performed especially for pulsed columns by CEA and also the results of first active runs in UP3

  5. Transportation of spent fuel from light water reactors

    International Nuclear Information System (INIS)

    Bernard, H.

    1993-01-01

    The French 'Compagnie Generale des Matieres Nucleaires' - COGEMA - is involved in the whole nuclear fuel cycle about 20 years. Among the different parts of the cycle, the Transport of Radioactive Materials, acting as a link between the differents plants has a great importance. As nuclear material transportation is the only fuel cycle step to be performed on public grounds, the industrial task has to be performed with the utmost stringent safety criteria. COGEMA and associates is now operating a fully mature commercial activity, with some 300 spent fuel shipments per year from its reprocessing customer's reactors to the LA HAGUE plant, either by rail, road or sea. The paper will review the organization of COGEMA transportation business, the level of technology with an update of the casks used for spent fuel, and the operational experience, with a particular view of the maintenance policy. (author)

  6. Solvent distillations studies for a reprocessing plant

    International Nuclear Information System (INIS)

    Ginisty, C.; Guillaume, B.

    1989-01-01

    The substantial amounts of solvent used in large reprocessing plants are such that considerable care must be paid to solvent management to limit the production of organic wastes. The installation of intensive treatment by chemical regeneration serves to increase the service life of the solvent. General solvent management, combined with a distillation unit under reduced pressure also helps to recycle the two components of the solvent at a low activity level. Distillation also serves to remove the heavy degradation products that are generally responsible for poor hydraulic behavior and for the holdup of radioactive products such as plutonium, zirconium and ruthenium. From the safety standpoint, the flashpoint of the distilled diluent tends to rise. It can therefore be recycled without risk

  7. Experience and projects concerning treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Fukuda, G.; Matsumoto, K.; Miyahara, K.

    1984-01-01

    The active operation of Tokai reprocessing plant started in September 1977, and about 170 t U of spent fuel were reprocessed between then and December 1982. During this period, the low-level waste processing plant reduced the amount of radioactivity discharged into the environment. For radioactive liquid waste, the treatment procedures consist mainly of evaporation to keep the discharge into the sea at a low level. For combustible low-level solid waste and the solvent waste, which is of low tributyl phosphate content, incineration has been used successfully (burned: about 150 t of combined LLSW, about 50 m 3 of solvent waste, i.e. diluent waste). Most of the past R and D work was devoted to reducing the activity discharged into the environment. Current R and D work is concerned with the treatment of solvent waste, the conditioning of solid wastes, the bituminization of low-level liquid waste and the vitrification of high-level liquid waste. The paper describes present practices, R and D work and future aspects of the treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant. (author)

  8. Spent fuel storage and transportation - ANSTO experience

    International Nuclear Information System (INIS)

    Irwin, Tony

    2002-01-01

    The Australian Nuclear Science and Technology Organisation (ANSTO) has operated the 10 MW DIDO class High Flux Materials Test Reactor (HIFAR) since 1958. Refuelling the reactor produces about 38 spent fuel elements each year. Australia has no power reactors and only one operating research reactor so that a reprocessing plant in Australia is not an economic proposition. The HEU fuel for HIFAR is manufactured at Dounreay using UK or US origin enriched uranium. Spent fuel was originally sent to Dounreay, UK for reprocessing but this plant was shutdown in 1998. ANSTO participates in the US Foreign Research Reactor Spent Fuel Return program and also has a contract with COGEMA for the reprocessing of non-US origin fuel

  9. Decontamination and remote dismantling tests in the Itrec reprocessing plant

    International Nuclear Information System (INIS)

    Candelieri, T.; Gerardi, A.; Soffietto, G.

    1993-01-01

    The scope of this research is to evaluate the advantages of the rack removal system in the dismantling of reprocessing installations. The objective of this work is to verify experimentally the possibility of the decontamination of any particular module and the capability of the remote dismantling of components installed in the mobile rack. In particular, the main objective is to develop remotely operated equipment for the dismantling of centrifugal contactors. The decontamination of the equipment which represents the most important preliminary phase of the decommissioning operation, allowed to obtain low-level radioactivity. A supporting programme has been performed in order to collect sufficient data for the project and design of the remote dismantling machine. On the basis of technological cold test results, the project of the dismantling machine's construction has been optimized. Positive results obtained during the hot dismantling operations on the Rack 6 bis attested the effectiveness of the rack removal system as an original design which facilitates decommissioning of reprocessing plants. 2 tabs., 18 figs

  10. Catalogue and classification of technical safety rules for light-water reactors and reprocessing plants

    International Nuclear Information System (INIS)

    Bloser, M.; Fichtner, N.; Neider, R.

    1975-08-01

    This report on the cataloguing and classification of technical rules for land-based light-water reactors and reprocessing plants contains a list of classified rules. The reasons for the classification system used are given and discussed

  11. Study on the abnormal reaction in an evaporator at a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Kida, Takashi; Sugikawa, Susumu; Ohsaki, Hiroshi

    2004-01-01

    The calculation code was constructed in order to evaluate a self-accelerated reaction in an evaporator in a fuel reprocessing plant due to organic-nitric acid reactions. This report describes the model of the calculation code and the result of the trial calculation. (author)

  12. Improvement of shearing machine in the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Takae, Akiyoshi; Otani, Yoshikuni

    1994-01-01

    The shearing machine in the Tokai Reprocessing Plant has been improved and refurbished through its operational experience for about 20 years. Every component except the shear housing and magazine is changed for improved things by PNC, while the shearing machine had been designed and fabricated originally by a French Company. The improvement of the shearing machine was carried out for the purpose of settling the problems which were experienced in the past operation, and improving durability, remote maintainability, and operability. The details of their improvement work are described. (author)

  13. Concept of off-gas purification in reprocessing plants

    International Nuclear Information System (INIS)

    Henrich, E.; von Ammon, R.

    1986-01-01

    Concepts and individual processes for the off-gas purification in reprocessing plants are described which are suited to achieve a better retention of the gaseous and volatile radionuclides 129 I, 85 Kr, 14 C, and tritium. Improved and new process steps have been developed to the cold pilot plant scale. Essential individual process steps are an efficient iodine desorption from the dissolver solution, improved and new off-gas scrubs with nitric acid, a cryogenic as well as a selective absorption process for rare gas recovery plus the required prepurification steps and a process for the continuous and pressure-free fixation and storage of krypton in a metal matrix. Individual facilities have been selected and combined to investigate integrated dissolver off-gas systems. Advanced concepts based on a process using low flows and loads of all off-gas streams including the cell ventilation off-gas are briefly discussed

  14. 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

  15. Abnormal reactions in a evaporator in a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Kida, Takashi; Umeda, Miki; Sugikawa, Susumu

    2003-01-01

    In order to evaluate a self-accelerated reaction in an evaporator in a fuel reprocessing plant due to organic-nitric acid reactions, a development of a calculation code is under way. Mock-up tests were performed to investigate the fluid dynamic behavior of the organic solvent in the evaporator. Based on these results, the model of the calculation code was constructed. This report describes the results of mock-up tests and the model of the calculation code. (author)

  16. Methods for separating actinides from reprocessing and refabrication plant wastes

    International Nuclear Information System (INIS)

    Tedder, D.W.; Finney, B.C.; Blomeke, J.O.

    1979-01-01

    Chemical processing flowsheets have been developed to partition actinides from all actinide-bearing LWR fuel reprocessing and refabrication plant wastes. These wastes include high-activity-level liquids, scrap recovery liquors, HEPA filters and incinerator ashes, and chemical salt wastes such as sodium carbonate scrub solutions, detergent cleanup streams, and alkaline off-gas scrubber liquors. The separations processes that were adopted for this study are based on solvent extraction, cation exchange chromatography, and leaching with Ce 4+ -HNO 3 solution

  17. Progress and experiences from the decommissioning of the Eurochemic reprocessing plant

    International Nuclear Information System (INIS)

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

    2007-01-01

    Belgoprocess started the industrial decommissioning of the main process building of the former EUROCHEMIC reprocessing plant in 1990, after completion of a pilot project in which two buildings were emptied and decontaminated to background levels. The remaining structures were demolished and the concrete debris was disposed of as industrial waste and green field conditions restored. The Eurochemic reprocessing plant operated from 1966 to 1974 to process fuel from power reactors and research reactors. The main building is a large concrete structure, comprising a surface area of 55,000 m 2 , concrete volume 12,500 m 3 , and 1,500 Mg of metal components. The building is divided into multiple cells. About 106 individual cell structures have to be dismantled, involving the removal and decontamination of equipment from each cell, the decontamination of the cell walls, ceilings and floors, the dismantling of the ventilation system. Most of the work involves hands-on operations under protective clothing tailored to each specific task. Tool automation and automatic positioning systems are successfully applied. In view of the final demolition of the main process building, the main process building is divided into three parts - each part is isolated from the others. In the middle of 2008, after the removal of the NDA-IPAN/GEA installation, the eastern part will be demolished. The paper presents a status overview of the decommissioning and decontamination activities at the main process building of the former Eurochemic reprocessing plant on the nuclear site of Dessel in Belgium. The specific BELGOPROCESS approach will be highlighted, in which the decommissioning activities are carried out on an industrial scale with special emphasis on cost minimisation, the use of technology on an industrial representative scale and the specific alpha contamination of equipment and building surfaces, requiring that the decommissioning work is done with adequate protective clothing. Also

  18. 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

  19. Spent fuel handling and storage facility for an LWR fuel reprocessing plant

    International Nuclear Information System (INIS)

    Baker, W.H.; King, F.D.

    1979-01-01

    The facility will have the capability to handle spent fuel assemblies containing 10 MTHM/day, with 30% if the fuel received in legal weight truck (LWT) casks and the remaining fuel received in rail casks. The storage capacity will be about 30% of the annual throughput of the reprocessing plant. This size will provide space for a working inventory of about 50 days plant throughput and empty storage space to receive any fuel that might be in transit of the reprocessing plant should have an outage. Spent LWR fuel assemblies outside the confines of the shipping cask will be handled and stored underwater. To permit drainage, each water pool will be designed so that it can be isolated from the remaining pools. Pool water quality will be controlled by a filter-deionizer system. Radioactivity in the water will be maintained at less than or equal to 2 x 10 -4 Ci/m 3 ; conductivity will be maintained at 1 to 2 μmho/cm. The temperature of the pool water will be maintained at less than or equal to 40 0 C to retard algae growth and reduce evaporation. Decay heat will be transferred to the environment via a heat exchanger-cooling tower system

  20. The thermal oxide reprocessing plant at Sellafield: three years of active operation in the chemical separation plant

    International Nuclear Information System (INIS)

    Philips, C.

    1998-01-01

    The Thermal Oxide Reprocessing Plant at British Nuclear Fuels' Sellafield site started operating in March 1994 with the shearing of its first irradiated fuel. In January 1995 the Chemical Separation part of the plant commenced processing the irradiated fuel feed solution that had been produced in the previous year by the Head End plant. By the Spring of 1998 over 1400 t of irradiated fuel has been reprocessed in Thorp, and the plant is being steadily and successfully ramped up to its normal operating throughput. The performance of the Thorp Chemical Separation Plant has been excellent, with the solvent extraction contactors performing as predicted by the extensive development programme. In particular the uranium-plutonium separation stage, which received intensive development to deal with the effects of the fission product technetium, has given an overall separation performance well in excess of the minimum flowsheet requirement. Decontamination of the uranium and plutonium products from fission products has in general been better than flowsheet requirements and the solvent extraction equipment has operated stably under the automatic controls developed during the R and D programme. Discharges of contaminants to waste streams have generally been in line with, or better than, expectation. This paper compares with flowsheet predictions a range of the key fission product and transuranic decontamination factors achieved in Thorp, shows how waste stream discharges are a small fraction of Sellafield Site discharge limits, demonstrates how uranium - plutonium separation performance has compared with expectation and summarises the overall performance of the Chemical Separation Plant. (author)

  1. 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)

  2. Management of low level wastes at Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Moriya, N.; Ochi, E.

    2006-01-01

    Full text: At Rokkasho Reprocessing Plant (RRP), after start-up of the commercial operation, radioactive wastes will be generated. Wastes generated from a reprocessing plant generally consist of many kinds of characteristics in view of ''activity level'', ''nuclide composition'', ''chemical properties'', ''physical properties'', and so on. For stable operation of a reprocessing plant, we should t reat , ''condition'' and ''dispose'' these wastes considering these wastes characteristics. To contribute to the nuclear fuel cycle project, it is important to evaluate technologies such as, ''Treatment'', ''Conditioning'' and ''Final Disposal'', not only for technical but also for economical aspects. Considering the final disposal in the future, the basic policy in ''Treatment'' and ''Conditioning'' at RRP is shown below: Recover and reuse chemicals (such as nitric acid and TBP, etc.) in plant; Radioactive waste shall be divided, classified and managed according to activity level, nuclide composition, the radiation level, its physical properties, chemical properties, etc.; Treat them based on ''classification'' management with proper combination; Condition them as intermediate forms in order to keep flexibility in the future disposal method; Original volume of annually generated wastes at RRP is estimated as 5600m3 except highly radioactive vitrified waste, and these wastes shall be treated in the following units, which are now under commisioning, in order to reduce and stabilize wastes. Low-level concentrated liquid waste to be treated with a ''Drying and peptization'' unit; Spent solvent to be treated with a ''Pyrolysis and hydrothermal solidification'' unit; Relatively low-level non-alfa flammable wastes to be treated with a ''Incineration and hydrothermal solidification'' unit; CB/BP (Channel Box and Burnable Poison) to be processed with a ''Cutting'' unit; Other wastes to be kept as their generated state with a ''Intermediate storage''. As a result of these

  3. How to simplify the analytics for input-output accountability measurements in a reprocessing plant

    International Nuclear Information System (INIS)

    Ottmar, H.; Eberle, H.; Matussek, P.; Michel-Piper, I.

    1986-02-01

    An analytical approach to high-performance uranium and plutonium accountancy measurements in reprocessing input and output solutions is presented, which provides larger operational simplicity than the conventionally applied chemical methods. The proposed alternative is based on energy-dispersive absorption edge and fluorescence X-ray spectrometry, using the proven and reliable K-edge densitometry technique as reference method. Two X-ray densitometers developed for accurate and reliable uranium and plutonium analysis in both the feed and product solutions are described. Practical experiences and results from their performance evaluation on actual process solutions from a reprocessing plant are presented and discussed. (orig.) [de

  4. Optimizing near real time accountability for reprocessing

    International Nuclear Information System (INIS)

    Cipiti, Benjamin B.

    2010-01-01

    Near Real Time Accountability (NRTA) of actinides at high precision in reprocessing plants has been a long sought-after goal in the safeguards community. Achieving this goal is hampered by the difficulty of making precision measurements in the reprocessing environment, equipment cost, and impact to plant operations. Thus the design of future reprocessing plants requires an optimization of different approaches. The Separations and Safeguards Performance Model, developed at Sandia National Laboratories, was used to evaluate a number of NRTA strategies in a UREX+ reprocessing plant. Strategies examined include the incorporation of additional actinide measurements of internal plant vessels, more use of process monitoring data, and the option of periodic draining of inventory to key tanks. Preliminary results show that the addition of measurement technologies can increase the overall measurement uncertainty due to additional error propagation, so care must be taken when designing an advanced system. Initial results also show that relying on a combination of different NRTA techniques will likely be the best option. The model provides a platform for integrating all the data. The modeling results for the different NRTA options under various material loss conditions will be presented.

  5. 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

  6. Outline of material accountancy system for Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Kitamura, Touko; Yamazaki Yoshihiro; Ai, Hironobu

    2004-01-01

    In January 2004, Facility Attachment (FA) for Rokkasho Reprocessing Plant (RRP) was entered into force and the safeguards has been implemented in accordance with the FA. So operator must carry out the effectual material accountancy on the basis of facility operation. RRP is large and complex facility and operated based on automatic and remote system. For efficient material accounting viewpoint, the system especially automatic data collection is established using RRP computer network. The paper describes the outline of material accountancy system, the structure of RRP computer network including how to collect the source data, to convert the batch data and the reporting. (author)

  7. Safety demonstration tests on pressure rise in ventilation system and blower integrity of a fuel-reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Takada, Junichi; Suzuki, Motoe; Tsukamoto, Michio; Koike, Tadao; Nishio, Gunji [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1996-12-01

    In JAERI, the demonstration test was carried out as a part of safety researches of the fuel-reprocessing plant using a large-scale facility consist of cells, ducts, dumpers, HEPA filters and a blower, when an explosive burning due to a rapid reaction of thermal decomposition for solvent/nitric acid occurs in a cell of the reprocessing plant. In the demonstration test, pressure response propagating through the facility was measured under a blowing of air from a pressurized tank into the cell in the facility to elucidate an influence of pressure rise in the ventilation system. Consequently, effective pressure decrease in the facility was given by a configuration of cells and ducts in the facility. In the test, transient responses of HEPA filters and the blower by the blowing of air were also measured to confirm the integrity. So that, it is confirmed that HEPA filters and the blower under pressure loading were sufficient to maintain the integrity. The content described in this report will contribute to safety assessment of the ventilation system in the event of explosive burning in the reprocessing plant. (author)

  8. Total Data Management System for the La Hague spent fuel reprocessing plants

    International Nuclear Information System (INIS)

    Chabert, J.; Coignaud, G.; Perot, J.P.; Fournier, W.; Silvain, B.

    1991-01-01

    Operation of the UP2 and UP3 reprocessing plants at La Hague, France, generates considerable data processing requirements. To meet these requirements, a Total Data Management System (TDMS) has been designed and installed to operate the biggest Ethernet industrial network in Europe. This network, called Haguenet, interconnects a large number of computers and user terminals. The TDMS' main operational functions are plant operation and production data management, maintenance data management, technical documents management and computer-aided design (CAD). Extensive experience was gained through the design and operation of the TDMS at La Hague. (author)

  9. Operating experience and development of fluidized-bed denitrators for UNH at Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Sasaki, Minoru; Nakamichi, Hideya; Takeda, Seiichiro; Kubota, Kanya; Katoh, Shuji

    1983-01-01

    The fluidized bed denitrator for uranyl nitrate hexahydrate (UNH) at Tokai reprocessing plant has been operated since 1976. About 170 tons of spent fuel have been reprocessed, and the denitrator has encountered numerous operational problems during the period. This report deals with these technical problems and the associated countermeasures taken, including the dismantling and reconstruction of equipment and the improvement of operating method. The major problems encountered were as follows: (1) the crystallization of UNH on the UNH feeding line, (2) spray nozzle clogging and candle filter clogging, (3) particle growth, (4) plugging of the drawing-out line by nozzle caking, and (5) slugging in fluidized-bed denitration. The total quantity and quality of UO 3 products obtained so far at the plant are also briefly described together with some future R and D programs such as the improvement of UO 3 reactivity and the automation of denitrators. (Aoki, K.)

  10. Reprocessing of LEU silicide fuel at Dounreay

    International Nuclear Information System (INIS)

    Cartwright, P.

    1996-01-01

    UKAEA have recently reprocessed two LEU silicide fuel elements in their MTR fuel reprocessing plant at Dounreay. The reprocessing was undertaken to demonstrate UKAEA's commitment to the world-wide research reactor communities future needs. Reprocessing of LEU silicide fuel is seen as a waste treatment process, resulting in the production of a liquid feed suitable for conditioning in a stable form of disposal. The uranium product from the reprocessing can be used as a blending feed with the HEU to produce LEU for use in the MTR cycle. (author)

  11. Reprocessing and waste management in the UK

    International Nuclear Information System (INIS)

    Mogg, C.S.; Howarth, G.G.

    1987-01-01

    The paper concerns the progress in irradiated fuel reprocessing and waste management at the Sellafield site. Magnox fuel reprocessing is reviewed and oxide fuel reprocessing, due to commence in the early 1990s, is compared with existing practices. The article describes how magnox fuel reprocessing will be sustained by recent additions of new plant and shows how waste management downstream of reprocessing will be integrated across the Sellafield site. This article was first presented as a paper at the Waste Management '87 (1-5 March, Tucson, Arizona) conference. (author)

  12. The regulations concerning the reprocessing business of spent fuels

    International Nuclear Information System (INIS)

    1987-01-01

    Regulations specified here cover application for such matters as designation of reprocessing undertaking, permission of construction of reprocessing facilities, permission and approval of alteration (of plan for reprocessing facilities), etc. The regulations also cover application for prior inspection, execution of prior inspection, technical standards concerning performance of reprocessing facilities, certificate of prior inspection, reprocessing facilities subject to welding inspection, application for welding inspection, execution of welding inspection, facilities not subject to welding inspection, approval of welding method, welding inspection for imported equipment, certificate of welding inspection, reprocessing facilities subject to regular inspection, application for regular inspection, technical standards for regular inspection, operation plan, application for approval of joint management, record keeping, restriction on access to areas under management, measures concerning exposure to radioactive rays, patrol and checking in reprocessing facilities, operation of reprocessing facilities, self-imposed regular inspection of reprocessing facilities, transportation within plant or operation premises, storage, waste disposal within plant or operation premises, safety rules, notice of disassembly, measures for emergency, notice of abolition of business, notice of disorganization, measures concerning cancellation of designation, submission of report, etc. (Nogami, K.)

  13. Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Munson, L F; Nemec, J F; Koochi, A K

    1978-06-01

    The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively. (DLC)

  14. Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

    International Nuclear Information System (INIS)

    Munson, L.F.; Nemec, J.F.; Koochi, A.K.

    1978-06-01

    The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively

  15. Selection of construction materials for equipment in an experimental reprocessing plant

    International Nuclear Information System (INIS)

    Mizrahi, R.; Cragnolino, G.A.

    1994-01-01

    A review is made of the most significant corrosion problems that may be present in different stages of the process in a spent fuel reprocessing plant. The influence of different variables is analyzed: concentration of nitric acid and other oxidizing species, temperature, etc., in corrosion of materials of most frequent use in pipings and equipment. The materials are austenitic stainless steels and refractory metals, especially zirconium and its alloys. Both general and localized corrosion phenomena are analyzed for these materials. Selection criteria for the use of adequate material in different components of the plant are also discussed. (author). 32 refs., 20 figs., 3 tabs

  16. Advanced techniques for analytic liquid wastes management in the Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Madic, C.; Moulin, J.P.; Runge, S.; Schott, R.; Kashiwai, T.; Hayashi, M.

    1991-01-01

    The JNFS Rokkasho reprocessing plant is a large scale commercial reprocessing plant. Liquid waste treatment relies on concentration by evaporation. The management of liquid wastes is rather sophisticated and implies, beside the organic wastes, sorting out between process and non-process, acidic and salt-bearing, tritiated and low tritiated streams and also according to their level of activity. A particular attention had to be paid to the analytical wastes, as their particularity is to contain not only a significant amount of radioactivity but also some fissile material and exotic chemicals which are useful for analytical purpose but unwanted in the main process mainly because of their corrosive and chelating properties. The analytical wastes are sorted out according to their activity level and fissile material content. On the one hand, a specific process has been developed to recover the bulk of plutonium from the analytical wastes. On the other hand, the foreseeable amount of unwanted chemicals (such as chloride ions) has been drastically reduced by carefully selecting all the analytical methods either by modification of already known methods or in some cases by working out new methods

  17. Reprocessing of spent nuclear fuel

    International Nuclear Information System (INIS)

    Schmitt, D.

    1985-01-01

    How should the decision in favour of reprocessing and against alternative waste management concepts be judged from an economic standpoint. Reprocessing is not imperative neither for resource-economic reasons nor for nuclear energy strategy reasons. On the contrary, the development of an ultimate storage concept representing a real alternative promising to close, within a short period of time, the nuclear fuel cycle at low cost. At least, this is the result of an extensive economic efficiency study recently submitted by the Energy Economics Institute which investigated all waste management concepts relevant for the Federal Republic of Germany in the long run, i.e. direct ultimate storage of spent fuel elements (''Other waste disposal technologies'' - AE) as well as reprocessing of spent fuel elements where re-usable plutonium and uranium are recovered and radioactive waste goes to ultimate storage (''Integrated disposal'' - IE). Despite such fairly evident results, the government of the Federal Republic of Germany has favoured the construction of a reprocessing plant. From an economic point of view there is no final answer to the question whether or not the argumentation is sufficient to justify the decision to construct a reprocessing plant. This is true for both the question of technical feasibility and issues of overriding significance of a political nature. (orig./HSCH) [de

  18. 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.

  19. Application of electrochemical techniques in fuel reprocessing- an overview

    Energy Technology Data Exchange (ETDEWEB)

    Rao, M K; Bajpai, D D; Singh, R K [Power Reactor Fuel Reprocessing Plant, Tarapur (India)

    1994-06-01

    The operating experience and development work over the past several years have considerably improved the wet chemical fuel reprocessing PUREX process and have brought the reprocessing to a stage where it is ready to adopt the introduction of electrochemical technology. Electrochemical processes offer advantages like simplification of reprocessing operation, improved performance of the plant and reduction in waste volume. At Power Reactor Fuel Reprocessing plant, Tarapur, work on development and application of electrochemical processes has been carried out in stages. To achieve plant scale application of these developments, a new electrochemical cycle is being added to PUREX process at PREFRE. This paper describes the electrochemical and membrane cell development activities carried out at PREFRE and their current status. (author). 5 refs., 4 tabs.

  20. Fully integrated safeguards and security for reprocessing plant monitoring

    International Nuclear Information System (INIS)

    Duran, Felicia Angelica; Ward, Rebecca; Cipiti, Benjamin B.; Middleton, Bobby D.

    2011-01-01

    Nuclear fuel reprocessing plants contain a wealth of plant monitoring data including material measurements, process monitoring, administrative procedures, and physical protection elements. Future facilities are moving in the direction of highly-integrated plant monitoring systems that make efficient use of the plant data to improve monitoring and reduce costs. The Separations and Safeguards Performance Model (SSPM) is an analysis tool that is used for modeling advanced monitoring systems and to determine system response under diversion scenarios. This report both describes the architecture for such a future monitoring system and present results under various diversion scenarios. Improvements made in the past year include the development of statistical tests for detecting material loss, the integration of material balance alarms to improve physical protection, and the integration of administrative procedures. The SSPM has been used to demonstrate how advanced instrumentation (as developed in the Material Protection, Accounting, and Control Technologies campaign) can benefit the overall safeguards system as well as how all instrumentation is tied into the physical protection system. This concept has the potential to greatly improve the probability of detection for both abrupt and protracted diversion of nuclear material.

  1. 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.)

  2. Progress and experiences from the decommissioning of the Eurochemic reprocessing plant - 16022

    International Nuclear Information System (INIS)

    Walthery, Robert; Lewandowski, Patrick; Ooms, Bart; Reusen, Nancy; Van Laer, Wim

    2009-01-01

    Belgoprocess started the industrial decommissioning of the main process building of the former EUROCHEMIC reprocessing plant in 1990, after completion of a pilot project in which two buildings were emptied and decontaminated to background levels. The remaining structures were demolished and the concrete debris was disposed of as industrial waste and green field conditions restored. The Eurochemic reprocessing plant operated from 1966 to 1974 to process fuel from power reactors and research reactors. The main building is a large concrete structure, comprising a surface area of 55,000 m 2 , concrete volume 12,500 m 3 , and 1,500 Mg of metal components. The building is divided into multiple cells. About 106 individual cell structures have to be dismantled, involving the removal and decontamination of equipment from each cell, the decontamination of the cell walls, ceilings and floors, the dismantling of the ventilation system. Most of the work involves hands-on operations under protective clothing tailored to each specific task. Tool automation and automatic positioning systems are successfully applied. In view of the final demolition of the main process building, the main process building has been divided into three parts - each part is isolated from the others. In September 2008 the eastern part of the building has been demolished. The paper presents a status overview of the decommissioning and decontamination activities at the main process building of the former Eurochemic reprocessing plant on the nuclear site of Dessel in Belgium. The specific BELGOPROCESS strategy will be highlighted, in which the decommissioning activities are carried out on an industrial scale with special emphasis on cost minimisation, the use of technology on an industrial representative scale and the specific alpha contamination of equipment and building surfaces, requiring that the decommissioning work is done with adequate protective clothing. Also specific breathing and cooling air

  3. Radioactive airborne effluent discharged from Tokai reprocessing plant. 1998-2007

    International Nuclear Information System (INIS)

    Nakada, Akira; Miyauchi, Toru; Akiyama, Kiyomitsu; Momose, Takumaro; Kozawa, Tomoyasu; Yokota, Tomokazu; Ohtomo, Hiroyuki

    2008-10-01

    This report provides the data set of atmospheric discharges from Tokai reprocessing plant in Tokai-mura, Japan over the period from 1998 to 2007. Daily and weekly data are shown for 85 Kr that is continuously monitored and for the other nuclides (alpha emitters, beta emitters, 3 H, 14 C, 129 I and 131 I) whose activities are evaluated based on weekly samplings (Weekly sampling is continuous for 1 week). The data contained in this report are expected to apply for studying the behavior of the radioactive airborne effluent in the environment. (author)

  4. Seismic analysis of the Nuclear Fuel Service Reprocessing Plant at West Valley, New York: documentation

    International Nuclear Information System (INIS)

    Murray, R.C.; Nelson, T.A.; Davito, A.M.

    1977-01-01

    This material was generated as part of a seismic case review of the NFS Reprocessing Plant. This study is documented in UCRL-52266. The material is divided into two parts: mathematical model information, and ultimate load calculations and comparisons

  5. Development of the system for the estimation of materials flow in pyrochemical reprocessing plant. Characteristic evaluation of the oxide electrowinning plant

    International Nuclear Information System (INIS)

    Okamura, Nobuo; Tozawa, Katuhiro; Sato, Koji

    2002-07-01

    The operation of the plant with the non-aqueous reprocessing technology depends on the materials handling equipment closely. Because the value of decontamination factor of the products in the plant is low, treatment of nuclear materials requires remote operation technology. So the system for the evaluation of materials flow in the plant was built to evaluate the production ability of the plant and to check out the plant operation from the viewpoint of materials flow. The system is only based on information of the treatment abilities of materials handling machines and process installations and the arrangement of process installations in the reprocessing cell that influences a way to operate materials handling machines intensity. Therefore the system can be used to estimate the characteristics of non-aqueous plants that are not in detail design stage. The amount of production and the characteristics of the oxide electrowinning plant (operation term 200days/year, plant capacity 50tHM/year in design) designed in Feasibility Study Phase1 were estimated using the system. The results show that the practical amount of production of the plant design is about 88% of the designed value. To increase the amount of production, it is more useful to speed up materials handling machine time than to install new installation or to give priority to conduct bottleneck processes. It is because materials handling influences the production ability of the plant deeply. (author)

  6. APL used for control of a reprocessing plant

    International Nuclear Information System (INIS)

    Petruschka, B.

    1975-05-01

    A package of interactive APL functions for data maintaining and processing is discussed in some detail. The data is recorded during the cycle of irradiated fuels and is used to control the reprocessing plant at the Karlsruhe Nuclear Research Center (WAK). First nuclear fuel processing is explained. A short justification is given of the reasons why the program language APL and the facilities of the file subsystem APL PLUS had been chosen for data handling. This is followed by the description of workspace and file organisation, all mainfunctions and files are described. Finally all functions are listed, an example of a user session and the output of daily and monthly reports from terminal and high-speed printer are presented. (orig.) [de

  7. 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

  8. CEA R and D contribution to the La Hague extension plant

    International Nuclear Information System (INIS)

    Auchapt, P.; Bonniaud, R.; Bourgeois, M.; Courouble, J.M.; Tarnero, M.

    1986-06-01

    Through its subsidiary COGEMA, the CEA Group is engaged in building a very large industrial complex, designed to raise French capacity for reprocessing LWR fuels to 1600 t/year. This refers to the UP3 and UP2-800 plants currently being built at La Hague. Naturally, the well-knoxn ''Purex'' process is employed in its main features, since it has proved entirely satisfactory in the UP2 facilities. Scaling up, essentially applied to capacity and aiming at a factor of 4, nevertheless requires a thorough re-assessment of all the steps in the process. Main research topics include components for bulk chopping of the fuel bundle (blades, roller, rails, ventilation, anticorrosion barriers) dissolution, liquid-liquid extraction solvent recycling, PuO 2 redissolution, liquid and solid waste treatment

  9. Computer integrated construction at AB building in reprocessing plant

    International Nuclear Information System (INIS)

    Takami, Masahiro; Azuchi, Takehiro; Sekiguchi, Kenji

    1999-01-01

    JNFL (Japan Nuclear Fuel Limited) is now processing with construction of the spent nuclear fuel reprocessing plant at Rokkasho Village in Aomori Prefecture, which is coming near to the busiest period of construction. Now we are trying to complete the civil work of AB Building and KA Building in a very short construction term by applying CIC (Computer Integrated Construction) concept, in spite of its hard construction conditions, such as the massive and complicated building structure, interferences with M and E (Mechanical and Electrical) work, severe winter weather, remote site location, etc. The key technologies of CIC are three-dimensional CAD, information network, and prefabrication and mechanization of site work. (author)

  10. 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

  11. Estimation of gamma dose rate from hulls and shield design for the hull transport cask of Fuel Reprocessing Plant (FRP)

    International Nuclear Information System (INIS)

    Chandrasekaran, S.; Rajagopal, V.; Jose, M.T.; Venkatraman, B.

    2012-01-01

    In Fuel Reprocessing Plant (FRP), un-dissolved clad of fuel pins known as hulls are the major sources of high level solid waste. Safe handling, transport and disposal require the estimation of radioactivity as a consequent of gamma dose rate from hulls in fast reactor fuel reprocessing plant in comparison with thermal reactor fuel. Due to long irradiation time and low cooling of spent fuel, the evolution of activation products 51 Cr, 58 Co, 54 Mn and 59 Fe present as impurities in the fuel clad are the major sources of gamma radiation. Gamma dose rate from hull container with hulls from Fuel Sub Assembly (FSA) and Radial Sub Assembly (RSA) of Fuel Reprocessing Plant (FRP) was estimated in order to design the hull transport cask. Shielding computations were done using point kernel code, IGSHIELD. This paper describes the details of source terms, estimation of dose rate and shielding design of hull transport cask in detail. (author)

  12. 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

  13. Solvent extraction for spent nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Masui, Jinichi

    1986-01-01

    The purex process provides a solvent extraction method widely used for separating uranium and plutonium from nitric acid solution containing spent fuel. The Tokai Works has adopted the purex process with TPB-n dodecane as the extraction agent and a mixer settler as the solvent extraction device. The present article outlines the solvent extraction process and discuss the features of various extraction devices. The chemical principle of the process is described and a procedure for calculating the number of steps for countercurrent equilibrium extraction is proposed. Discussion is also made on extraction processes for separating and purifying uranium and plutonium from fission products and on procedures for managing these processes. A small-sized high-performance high-reliability device is required for carrying out solvent extraction in reprocessing plants. Currently, mixer settler, pulse column and centrifugal contactor are mainly used in these plants. Here, mixer settler is comparted with pulse column with respect to their past achievements, design, radiation damage to solvent, operation halt, controllability and maintenance. Processes for co-extraction, partition, purification and solvent recycling are described. (Nogami, K.)

  14. Commissioning and operating experience of compressed air system of a reprocessing plant (Paper No. 5.10)

    International Nuclear Information System (INIS)

    Nair, M.K.T.; Bajpai, D.D.; Mishra, A.K.; Kulkarni, H.B.; Raje, R.V.; Rajeshwar, S.

    1992-01-01

    Compressed air system is one of the most important utility systems, required in the continued operation of a radiochemical plant. Moisture and oil free compressed air is used in large scale for process control and process operations in reprocessing plants. Commissioning and operating experience of this system is described in detail, to indicate the importance of the system in the overall design and operation of such chemical plant. (author). 1 tab

  15. Radiation protection aspects in decommissioning of a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Kotrappa, P.; Joshi, P.P.; Theyyunni, T.K.; Sidhwa, B.M.; Nadkarni, M.N.

    1980-01-01

    The decontamination of a fuel reprocessing plant which underwent partial decommissioning is described. The following radiation protection aspects of the work are discussed: dismantling and removal of process vessels, columns and process off-gas filters; decontamination of various process areas; and management of liquid and solid wastes. The work was completed safely by using personnel protective equipment such as plastic suits and respirators (gas, particulate and fresh air). Total dose commitment for this work was around 3000 man-rems, including dose received by staff for certain jobs related to the operation of a section of the plant. The external dose was kept below the annual limit of 5000 mrems for any individual. No internal contamination incident occurred which caused a dose commitment in excess of 10% of the annual limit. The fact that all the work was completed by the staff normally associated with the operation of the plant contributed significantly to the management and control of personnel exposures. (H.K.)

  16. 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

  17. Problems of nuclear fuel reprocessing in Japan

    International Nuclear Information System (INIS)

    Tanaka, Naojiro

    1974-01-01

    The reprocessing capacity of the plant No. 1 of Power Reactor and Nuclear Fuel Development Corporation, which is scheduled to start operation in fiscal year 1975, will be insufficient after fiscal year 1978 for the estimated demand for reprocessing based on Japanese nuclear energy development program. Taking into consideration the results examined by JAIF's study team to Europe and the U.S., it is necessary that Japan builds 2nd reprocessing plant. But there will be a gap from 1978 to 1984 during which Japan must rely on overseas reprocessing services. The establishment of a reprocessing system is a task of national scale, and there are many problems to be solved before it can be done. These include the problems of site and environment, the problem of treatment and disposal of radioactive wastes, the raising of huge required funds and so on. Therefore, even if a private enterprise is allowed to undertake the task, it will be impossible to achieve the aim without the cooperation and assistance of the government. (Wakatsuki, Y.)

  18. 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.)

  19. Chemical forms and discharge ratios to stack and sea of tritium from Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Mikami, Satoshi; Akiyama, Kiyomitsu; Miyabe, Kenjiro

    2002-03-01

    Chemical forms and discharge ratios to stack and sea of tritium form Tokai Reprocessing Plant of Japan Nuclear Cycle Development Institute (JNC) were investigated by analyzing monitoring data. It was ascertained that approximately 70-80% of tritium discharged from the main stack was tritiated water vapor (HTO) and approximately 20-30% was tritiated hydrogen (HT) as a result of analyzing the data taken from reprocessing campaign's in 1994, 1995, 1996, 1997, 2000 and 2001, and also that the amount of tritium released from the stack was less than 1% of tritium inventory in spent fuel and the amount of tritium released into sea was approximately 20-40% of inventory. (author)

  20. 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)

  1. Risk assessment approach for Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Ootou, Y.; Tamauchi, Y.; Hayashi, Y.; Takebe, K.; Miyata, T.

    2006-01-01

    Full text: It is desirable that the operation and maintenance of Rokkasho Reprocessing Plant (RRP) be established and conducted with maximum effectiveness and efficiency, making the best use of risk information to help the plant achieve further enhanced safety. Risk assessment is applied for RRP, and upgraded risk information is established. In the basic design phase, the potential incidents and accidents that might occur in the plant were identified systematically and exhaustively adopting the HAZOP method. After screening the potential for occurrence, the design basis accidents (DBAs) were identified and it was confirmed that the plant would not put the general public at risk of significant radiation exposure in the case of such accidents, even when assuming the single failure of dynamic apparatus in the prevention and mitigation systems. To support the deterministic safety assessment mentioned above, the risk assessment was conducted during the basic design phase. Of the DBAs and out-of-design basis accidents excluded from DBAs because of extremely rare occurrence possibilities, the risk assessment was conducted for such accidents which might cause relatively high consequence for the general public. The risk assessment was conducted using the PSA method generally used for nuclear power plants. After that, a review of the occurrence frequency assessment for some of the accidents was made, taking into account information relating to detailed design and operation procedures. Typical examples are a loss of the hydrogen scavenging function in the plutonium solution tank and a loss of cooling capability in the high-active liquid waste storage tank. The occurrence frequency for a loss of the hydrogen scavenging function was less than 10 -5 /year. The occurrence frequency for a loss of cooling capability was less than 10 -7 /year. In addition, an importance assessment (FV index, Risk Achievement Worth) was conducted, such as a contribution to the occurrence frequency

  2. A prototype for actinide alpha monitoring in liquid effluents of reprocessing plants

    International Nuclear Information System (INIS)

    Bardone, G.; Mattia, B.; Durante, R.; Frazzoli, F.V.

    1983-01-01

    The report deals with the design criteria of prototype measuring device, based on the alpha spectrometry, aimed to the determination of actinides solutions in reprocessing plants. The described instrument is considered as the result of a preliminary stage of development. Taking into account the experimental results obtained with Pu bearing solutions the performances achievable are evaluated; in particular, it turns out that the minimum detectable activity is about 10 -5 Ci/l

  3. Impact of uranium exploitation by Cogema-Areva subsidiaries in Niger. Assessment of analyses performed by the CRIIRAD laboratory in 2004 and at the beginning of 2005

    International Nuclear Information System (INIS)

    2005-01-01

    After a description of the uranium exploitation context (involved companies, production) in Arlit, Niger, by Cogema-Areva subsidiary companies, this report describes the context of controls performed by the CRIIRAD laboratory. Then, it reports and comments the contamination of underground so-called drinkable waters (contamination risks, Cogema statement, detection of a rather high concentration of alpha emitters, measurements performed in 2004 and 2005). The authors notice that water contamination is known by Cogema. Then, the report analyzes the issue of contaminated scrap metal dispersal, comments and criticizes the attitude of Cogema with respect to the associated risks. It comments the uranate transport accident which occurred in February 2004, the subsequent contamination, actions performed by Cogema, the associated health risks, and the statements made by Areva and Cogema. It also comments and analyzes the risks related to radioactive radon dusts inhalation around different sites and because of some technical practices, and Cogema statements about this issue. In conclusion, the authors outline the need of reinforced controls and of an epidemiological study, and outlines how Areva propagates wrong ideas

  4. 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)

  5. Maintenance management of emergency power supply equipment (uninterruptible power supply) in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Nishida, Kyosuke; Hiyama, Hisao; Shibata, Satomi; Iwasaki, Shogo; Inami, Shinichi

    2009-01-01

    Uninterruptible power supply systems are installed in the Tokai reprocessing plant in preparation for the emergency case that the commercial power supply is stopped by an accidental or intentional interruption in the supply of electricity. The uninterruptible power supply system particularly provides a temporary power source to the important devices for the radiation control of nuclear critical monitoring in the plant. Thus, the system is potentially important and essential for nuclear plants. The paper reports the current activities such as regular inspections, replacement of parts and system update, to maintain the function of uninterruptible power supply systems. (author)

  6. Off-gas processing method in reprocessing plant

    International Nuclear Information System (INIS)

    Kobayashi, Yoshihiro; Seki, Eiji.

    1990-01-01

    Off-gases containing a radioactive Kr gas generated in a nuclear fuel reprocessing plant are at first sent to a Kr gas separator. Then, the radioactive Kr gas extracted there is introduced to a Kr gas fixing device. A pretreatment and a post-treatment are applied by using a non-radioactive clean inert gas except for the Kr gas as a purge gas. If the radioactive Kr gas is contained in the off-gases discharged from the Kr gas fixing device after applying the post-treatment, the off gases are returned to the Kr gas separator. Accordingly, in a case where the radioactive Kr gas is contained in the off-gases discharged from the Kr gas fixing device, it is not necessary to apply the fixing treatment to all of the off gases. In view of the above, increase of the amount of processing gases can be suppressed and the radioactive Kr gas can be fixed efficiently and economically. (I.N.)

  7. Characteristics of radioactive waste streams generated in HTGR fuel reprocessing

    International Nuclear Information System (INIS)

    Lin, K.H.

    1976-01-01

    Results are presented of a study concerned with identification and characterization of radioactive waste streams from an HTGR fuel reprocessing plant. Approximate quantities of individual waste streams as well as pertinent characteristics of selected streams have been estimated. Most of the waste streams are unique to HTGR fuel reprocessing. However, waste streams from the solvent extraction system and from the plant facilities do not differ greatly from the corresponding LWR fuel reprocessing wastes

  8. Demonstration and development of safeguards techniques in the PNC reprocessing plant. Part of a coordinated programme on the use of installed instrumentation in fuel reprocessing facilities for safeguards purposes

    International Nuclear Information System (INIS)

    Kurihara, H.

    1979-04-01

    A hull-monitoring system in the Head-End facility and systems for surveillance and containment in the spent fuel receiving and storage facility at Tokai Reprocessing Plant are described. Operating experience on them is analyzed

  9. Reliability analysis of repairable safety systems of a reprocessing plant allowing for tolerable system downtimes

    International Nuclear Information System (INIS)

    Schaefer, H.

    1987-01-01

    GRS has been engaged in safety analysises of the German Reprocessing Plant for several years. The development and verification of appropriate reliability analysis methods, the generation of data as well as the search for an adequate structural presentation of the results to form a basis of recommendations for technical or administrative measures or contributions to risk oriented evaluations have been or are in the process of being established. In contrast to NPP-studies, the reliability assessment of safety systems of a reprocessing plant is applied to repairable and often relatively small systems allowing for tolerable system downtimes. A sketch of the diverse cooling systems of a vessel containing a selfheating solution is given. The interruption of the cooling function for about one day might be tolerable before boiling will be reached. This interval is suitable for transfer of the solution to a spare vessel or for repairing the failed components, thus restoring the cooling function

  10. 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)

  11. 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.

  12. 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

  13. 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

  14. 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)

  15. Spent fuel management: reprocessing or storage

    International Nuclear Information System (INIS)

    Lima Soares, M.L. de; Oliveira Lopes, M.J. de

    1986-01-01

    A review of the spent fuel management concepts generally adopted in several countries is presented, including an analysis of the brazilian situation. The alternatives are the reprocessing, the interim storage and the final disposal in a repository after appropriate conditioning. The commercial operating reprocessing facilities in the Western World are located in France and in the United Kingdom. In the USA the anti-reprocessing policy from 1977 changed in 1981, when the government supported the resumption of commercial reprocessing and designated the private sector as responsible for providing these services. Small scale facilities are operating in India, Italy, Japan and West Germany. Pilot plants for LWR fuel are being planned by Spain, Pakistan and Argentina. (Author) [pt

  16. Spent fuel management: reprocessing or storage

    International Nuclear Information System (INIS)

    Lima Soares, M.L. de; Oliveira Lopes, M.J. de.

    1986-01-01

    A review of the spent fuel management concepts generally adopted in several countries is presented, including an analysis of the brazilian situation. The alternatives are the reprocessing, the interim storage and the final disposal in a repository after appropriate conditioning. The commercial operating reprocessing facilities in the Western World are located in France and in the United Kingdom. In the USA the anti-reprocessing policy from 1977 changed in 1981, when the Government supported the resumption of commercial reprocessing and designated the private sector as responsible for providing these services. Small scale facilities are operating in India, Italy, Japan and West Germany. Pilot plant for LWR fuel are being planned by Spain, Pakistan and Argentina. (Author) [pt

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  18. Low and medium level liquid waste processing at the new La Hague reprocessing plant

    International Nuclear Information System (INIS)

    Alexandre, D.

    1986-05-01

    Reprocessing of spent nuclear fuels produces low and medium activity liquid wastes. These radioactive wastes are decontamined before release in environment. The new effluent processing plant, which is being built at La Hague, is briefly described. Radionuclides are removed from liquid wastes by coprecipitation. The effluent is released after decantation and filtration. Insoluble sludges are conditioned in bitumen [fr

  19. Dynamic analysis and response spectra for the main processing building of a reprocessing plant

    International Nuclear Information System (INIS)

    Mischke, J.; Hilpert, H.J.; Henkel, F.O.

    1984-01-01

    The article deals with the determination of the floor response spectra for the main processing building of the planned reprocessing plant due to the special loading conditions of earthquake, airplane crash and blast. With these spectra the stress and strain of the components and their bearing forces which react on the building can be calculated. (orig.) [de

  20. The extraction behavior of some noticeable nuclides in the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Yamanouchi, T.; Sasao, N.; Ozawa, M.; Yamana, H.

    1987-01-01

    The extraction behavior of some TRU nuclides and Ru-106 were investigated on the basis of the process analytical data obtained during this decade of the hot operation in the Tokai Reprocessing Plant. Some characteristics of their extraction behavior under Tokai-flowsheet became clear. They were explainable by the chemical features of these nuclides in conjunction with the chemical conditions of the process. Some extraction-simulation calculations were performed to supplement the understanding of their characteristic behaviors

  1. HTGR fuel reprocessing pilot plant: results of the sequential equipment operation

    International Nuclear Information System (INIS)

    Strand, J.B.; Fields, D.E.; Kergis, C.A.

    1979-05-01

    The second sequential operation of the HTGR fuel reprocessing cold-dry head-end pilot plant equipment has been successfully completed. Twenty standard LHGTR fuel elements were crushed to a size suitable for combustion in a fluid bed burner. The graphite was combusted leaving a product of fissile and fertile fuel particles. These particles were separated in a pneumatic classifier. The fissile particles were fractured and reburned in a fluid bed to remove the inner carbon coatings. The remaining products are ready for dissolution and solvent extraction fuel recovery

  2. Density and volume measurements of reprocessing plant feed

    International Nuclear Information System (INIS)

    Platzer, R.; Carrier, M.; Neuilly, M.; Dedaldechamp, P.

    1985-05-01

    A theoretical study of the phenomenon of gas bubbles formation within a liquid led to an adaptation of the differential pressure bubbling technique for the measurement of liquid levels and densities in tanks. Experiments, carried out on a 800 liters tank with water and uranyl nitrate solutions had the double aim to study the precision attainable on volume and density measurements and to design a method for corrections of influencing factors. In parallel, procedures for transfer of known volumes through the use of siphons and for tank calibration by liquid level measurement are also investigated. The paper presents the first results obtained so far and the conclusions to be drawn for the elaboration of calibration and exploitation procedures suitables for use in reprocessing plants. The demonstration to transfer mass of solution with an accuracy of 0.1% is made [fr

  3. Environmental radioactivity monitoring around the Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Sasaki, K.; Hareyama, H.; Takeishi, M.

    2009-01-01

    Japan Nuclear Fuel Limited has carried out environmental monitoring in order to check that the dose of radiation to which the public is exposed around the Rokkasho Reprocessing Plant (RRP) is much lower than the annual dose limit. The monitoring is mainly carried out according to 'the program decided by the Nuclear Safety Commission (NSC) of Japan' and 'the program decided by the Aomori Prefectural Government.' In this report, we present information on the monitoring according to the NSC program, that is the point of view of selection of the monitoring items for dose assessment, the point of view of the dose assessment from the monitoring results, etc. Also, we report on estimation of the effects from the facilities on the monitoring results obtained and dose assessment of the public during Active testing of RRP. (author)

  4. 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

  5. Aspects of remote maintenance in an FRG reprocessing plant from the manufacturer's viewpoint

    International Nuclear Information System (INIS)

    Zeitzchel, G.; Tennie, M.; Saal, G.

    1986-01-01

    In April 1986 a consortium led by Kraftwerk Union AG was commissioned by the German society for nuclear fuel reprocessing (DWK) to build the first West German commercial reprocessing plant for spent fuel assemblies. The main result of the planning efforts regarding remote maintenance operations inside the main process building was the introduction of FEMO technology (FEMO is an acronym based on German for remote handling modular technique). According to this technology the two cells in which the actual reprocessing (which is based on the PUREX technique) takes place are provided with frames to accommodate the process components (tanks, pumps, agitators, etc.), each frame together with the components which it supports forming one module. The two cells are inaccessible and windowless. For handling operations each cell is equipped with an overhead crane and a crane-like manipulator carrier system (MTS) with power manipulator. Viewing of the operations from outside the cells is made possible by television (TV) cameras installed at the crane, the MTS, and the manipulator. This paper addresses some examples of problems that still need to be solved in connection with FEMO handling. In particular, the need for close cooperation between the equipment operator, the component designer, the process engineer, the planning engineer, and the licensing authorities will be demonstrated

  6. Aerosol and iodine removal system for the dissolver off-gas in a large fuel reprocessing plant

    International Nuclear Information System (INIS)

    Furrer, J.; Wilhelm, J.G.; Jannakos, K.

    1979-01-01

    A newly developed filter combination for the dissolver off-gas in a reprocessing plant with a throughput of 1400 t/y of heavy metal is presented and single filter components are described. The design principle chosen provides for remote handling and direct disposal in waste drums of 200 l volume. The optimization of housings and filter units is studied on true scale components in the simulated dissolver off-gas of a test facility named PASSAT. This facility will be described. PASSAT will be also used for final testing of the SORPTEX process which is under development. Its concept is included in the paper. The design and function of the new multiway sorption filter providing for complete loading of the iodine sorption material and maintaining continuously high decontamznation factors will also be given. Removal efficiencies measured for aerosols and iodine in an existing reprocessing plant are indicated

  7. Spent fuel and HLW transportation the French experience

    International Nuclear Information System (INIS)

    Giraud, J.P.; Charles, J.L.

    1995-01-01

    With 53 nuclear power plants in operation at EDF and a fuel cycle with recycling policy of the valuable materials, COGEMA is faced with the transport of a wide range of radioactive materials. In this framework, the transport activity is a key link in closing the fuel cycle. COGEMA has developed a comprehensive Transport Organization System dealing with all the sectors of the fuel cycle. The paper will describe the status of transportation of spent fuel and HLW in France and the experience gathered. The Transport Organization System clearly defines the role of all actors where COGEMA, acting as the general coordinator, specifies the tasks to be performed and brings technical and commercial support to its various subcontractors: TRANSNUCLEAIRE, specialized in casks engineering and transport operations, supplies packaging and performs transport operations, LEMARECHAL and CELESTIN operate transport by truck in the Vicinity of the nuclear sites while French Railways are in charge of spent fuel transport by train. HLW issued from the French nuclear program is stored for 30 years in an intermediate storage installation located at the La Hague reprocessing plant. Ultimately, these canisters will be transported to the disposal site. COGEMA has set up a comprehensive transport organization covering all operational aspects including adapted procedures, maintenance programs and personnel qualification

  8. Measuring process solutions in a reprocessing plant to 0.1%

    International Nuclear Information System (INIS)

    Crawford, J.M.; Ehinger, M.H.; Ellis, J.H.

    1980-03-01

    Measurement of SNM in reprocessing plant solutions involves two major problems; measurement of bulk solution quantities and analysis of highly radioactive samples. It has been shown at the BNFP that bulk measurements can be made routinely under operating conditions to less than 0.1% total uncertainty. Two specific advances in measurement technology have been largely responsible for this improved performance. The quartz bourdon tube electromanometer replaces the fluid manometer for differential pressure measurements. The vibrating tube densimeter provides accurate measurement of density in lab samples. These instruments, coupled with a rigorous measurement and quality control procedures, are the means to achieve better than 0.1% performance

  9. Process control of an HTGR fuel reprocessing cold pilot plant

    International Nuclear Information System (INIS)

    Rode, J.S.

    1976-10-01

    Development of engineering-scale systems for a large-scale HTGR fuel reprocessing demonstration facility is currently underway in a cold pilot plant. These systems include two fluidized-bed burners, which remove the graphite (carbon) matrix from the crushed HTGR fuel by high temperature (900 0 C) oxidation. The burners are controlled by a digital process controller with an all analog input/output interface which has been in use since March, 1976. The advantages of such a control system to a pilot plant operation can be summarized as follows: (1) Control loop functions and configurations can be changed easily; (2) control constants, alarm limits, output limits, and scaling constants can be changed easily; (3) calculation of data and/or interface with a computerized information retrieval system during operation are available; (4) diagnosis of process control problems is facilitated; and (5) control panel/room space is saved

  10. Remote repair of the dissolvers in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Otani, Yosikuni

    1985-01-01

    In the Tokai fuel reprocessing plant, there occurred failures (pinholes) in two dissolver tanks successively in 1982 and 1983. These dissolvers are set under high radiation field, not permitting access of the personnel. So, repair works were carried out after development of the remotely operated repair system. For repair of the failed dissolver tanks, after tests and studies, the means was employed of grinding off the wall surface to small depth and then forming over it a corrosion resistant sealing layer by padding welding. The repair system which enabled the repair and the inspection in the cell by remote operation consisted of six devices including polishing, welding, dye penetration test, etc. Repair works on the dissolvers took two months and a half from September 1983. (Mori, K.)

  11. The reprocessing plant as a problem of international law

    International Nuclear Information System (INIS)

    Guendling, L.

    1987-01-01

    The planned construction of the reprocessing plant creates problems with regard to transfrontier environmental protection, due to the potential hazards involved, and these problems institute obligations of the Federal Republic of Germany under contractual law and under customary international law. Particularly under customary international neighbour law the F.R.G. is obliged to prevent and abstain from transfrontier activities entailing environmental effects with considerable damaging potential in the neighbouring states, which also includes the duty of providing for protection against accidents. It is, however, a clear fact that the states decided the peaceful uses of atomic energy to be admissible, and accept the risk of possible catastrophic damage. The interpretation of existing international laws has to take this fact into account. (orig./HSCH) [de

  12. 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)

  13. Inspection activities of other strategic points (OSPs) at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Kaifuki, Yukinobu; Ebata, Takashi; Nakano, Sadayuki; Fujimaki, Kazunori

    2008-01-01

    At Rokkasho Reprocessing Plant (RRP), Active Test (AT) using actual spent fuels for the final confirmation of the equipment and the system has been performed since March 31, 2006 toward the commercial operation. The safeguards inspection during AT is required in the same manner as commercial operation condition because plutonium is handled. In RRP automated verification systems are established by using unattended verification systems including a number of process monitoring systems along with main plutonium handling process from the spent fuel storage until the MOX product storages. Even under the modernized safeguards, inspection activities at Other Strategic Points (OSPs) are required to confirm plant status in accordance with requirements of the IAEA safeguards criteria. This paper presents procedures and inspection activities at OSPs which has been implemented in RRP since start of AT. (author)

  14. PIPEX - A model of a design concept for reprocessing plants with improved containment and surveillance features

    International Nuclear Information System (INIS)

    1979-03-01

    This paper explains that the PIPEX concept is essentially a reprocessing plant using the PUREX process but with in-built improved containment and surveillance features resulting in increased health protection and environmental safety as well as higher resistance to diversion of fissile material. The paper gives a general description of the design and operating philosophy of such a plant and goes on to examine the safeguards and safety principles and implications

  15. Specification of an Expert system for the control of extraction units in reprocessing plants

    International Nuclear Information System (INIS)

    Jorda, A.; Charon, E.; Coppens, P.; Romet, J.L.

    1986-01-01

    Industrial operation of extraction units in reprocessing plants is very complex because the great number of chemical and hydraulic parameters to take into account. This complexity associated to the impossibility to see inside the active enclosures make difficult the operation processes, diagnosis and corrections. Management of parameters by an expert system will increase productivity and safety of solvent extraction in pulsed columns [fr

  16. Report on the FR Germany: US technical workshop on near-real-time material accounting for reprocessing plants

    International Nuclear Information System (INIS)

    Weh, R.; Hakkila, E.A.; Canty, M.J.

    1986-01-01

    A technical workshop on the subject of near-real-time material accounting in an industrial scale reprocessing plant was held. Organized within the context of the US DOE - FR German Ministry of Research and Technology (BMFT) agreement in the field of international safeguards, the workshop was initiated by the Deutsche Gesellschaft fur Wiederaufarbeitung von Kernbrennstoffen, responsible for the construction and operation of a planned industrial scale reprocessing plant in the FR Germany. The workshop's objective was to establish the current state of the art for near-real-time accounting and to bring out a common understanding and consensus among experts from both countries which seve as a basis for the definition of problems still to be solved. A summary of the workshop presentations, preliminary conclusions drawn by the experts attending as well as some implications for the application of dynamic balancing are given

  17. Development of process simulation code for reprocessing plant and process analysis for solvent degradation and solvent washing waste

    International Nuclear Information System (INIS)

    Tsukada, Tsuyoshi; Takahashi, Keiki

    1999-01-01

    We developed a process simulation code for an entire nuclear fuel reprocessing plant. The code can be used on a PC. Almost all of the equipment in the reprocessing plant is included in the code and the mass balance model of each item of equipment is based on the distribution factors of flow-out streams. All models are connected between the outlet flow and the inlet flow according to the process flow sheet. We estimated the amount of DBP from TBP degradation in the entire process by using the developed code. Most of the DBP is generated in the Pu refining process by the effect of α radiation from Pu, which is extracted in a solvent. On the other hand, very little of DBP is generated in the U refining process. We therefore propose simplification of the solvent washing process and volume reduction of the alkali washing waste in the U refining process. The first Japanese commercial reprocessing plant is currently under construction at Rokkasho Mura, Recently, for the sake of process simplification, the original process design has been changed. Using our code, we analyzed the original process and the simplified process. According our results, the volume of alkali waste solution in the low-level liquid treatment process will be reduced by half in the simplified process. (author)

  18. Information dossier. Return of vitrified wastes from France to Belgium; Dossier d'information. Retour de dechets vitrifies depuis la France vers la Belgique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-02-01

    Synatom, a daughter company of Electrabel and Tractebel, is in charge of the fuel management of Belgium nuclear power plants. Contracts were signed with Cogema (France) in the 70's for the reprocessing/recycling of spent fuels. The ultimate residual wastes are vitrified at Cogema-La Hague and sent back to Belgium by rail and road transports. This information dossier presents: the power production in Belgium, the management of the fuel cycle in Belgium (recycling, interim storage of spent fuels at Tihange and Doel sites, political choices, financing), the vitrification process (quality assurance, safety), the transport of vitrified wastes from France to Belgium (handling, packaging, TN 28 VT container, regulations, safety evaluation), interim storage, long-term disposal. (J.S.)

  19. The use of process information for verification of inventory in solvent extraction contactors in near-real-time accounting for reprocessing plants

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Barnes, J.W.; Hafer, J.F.

    1988-01-01

    Near-real-time accounting is being studied as a technique for improving the timeliness of accounting in nuclear fuel reprocessing plants. A major criticism of near-real-time accounting is perceived disclosure of proprietary data for IAEA verification, particularly in verifying the inventory of solvent extraction contractors. This study indicates that the contribution of uncertainties in estimating the inventory of pulsed columns or mixer settlers may be insignificant compared to uncertainties in measured throughput and measurable inventory for most reprocessing plants, and verification may not be a serious problem. Verification can become a problem for plants with low throughput and low inventory in tasks if contactor inventory variations or uncertainties are greater than --25%. Each plant must be evaluated with respect to its specific inventory and throughput characteristics

  20. Application of active neutronic interrogation method to the line analysis in reprocessing plant

    International Nuclear Information System (INIS)

    Passard, C.

    1993-01-01

    In a reprocessing plant of irradiated spent fuels, the knowledge in real time (line analysis) of uranium and plutonium quantities present in solutions is an extremely important parameter to control the proceeding and for the apparatus safety. The active neutronic analysis give a nondestructive non intrusive and quick measure to know the concentrations. This method consists in inducing fissions in nuclides with a neutron source and then to detect the particles which come from

  1. 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

  2. Summary of the function and the safety design of the Tokai Reprocessing Utility Center

    International Nuclear Information System (INIS)

    Yanai, Chisato; Yamazaki, Toshihiko; Tomita, Tsuneo; Horii, Shinichi; Uryu, Mituru; Ishiguro, Nobuharu; Kobayashi, Kentarou

    1998-01-01

    The Tokai Reprocessing Utility Center is a new facility to replace the utilities to the Tokai Reprocessing Plant such as the emergency power supply, compressed air, etc. which are scattered about the site and have became superannuated. The Facility building has a base-isolation system that is a strongly resistant to earthquake. After completion, the center will supply utilities to the Main Plant, the Central Building, the Auxiliary Active Facility, etc. of the Tokai Reprocessing Plant. This document outlines the function and the safety design of the Tokai Reprocessing Utility Center. (author)

  3. 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

  4. Computer aided process control equipment at the Karlsruhe reprocessing pilot plant, WAK

    International Nuclear Information System (INIS)

    Winter, R.; Finsterwalder, L.; Gutzeit, G.; Reif, J.; Stollenwerk, A.H.; Weinbrecht, E.; Weishaupt, M.

    1991-01-01

    A computer aided process control system has been installed at the Karlsruhe Spent Fuel Reprocessing Plant, WAK. All necessary process control data of the first extraction cycle is collected via a data collection system and is displayed in suitable ways on a screen for the operator in charge of the unit. To aid verification of displayed data, various measurements are associated to each other using balance type process modeling. Thus, deviation of flowsheet conditions and malfunctioning of measuring equipment are easily detected. (orig.) [de

  5. Explosion risks linked to red oils in the spent fuels reprocessing plants

    International Nuclear Information System (INIS)

    2008-06-01

    This paper presents the risk of explosion associated with reactions between tributyl phosphate (TBP) and its degradation products and nitrates from nitric acid or associated with heavy metals (uranium and plutonium); These reactions may lead to the formation of unstable compounds known as 'red oils'. The feedback explosions linked to the formation of such compounds occurring in spent fuel reprocessing plants round the world, is briefly discussed. The main measures to control these risks, implemented in French factories concerned are also presented. (N.C.)

  6. Present and future potential of krypton-85 for the detection of clandestine reprocessing plants for treaty verification.

    Science.gov (United States)

    Schoeppner, Michael; Glaser, Alexander

    2016-10-01

    Burnup calculations are applied to determine the amount of krypton-85 that is produced during the irradiation of nuclear fuel. Since krypton-85 is most likely released into the atmosphere during reprocessing to separate plutonium, atmospheric transport modeling is used to calculate the worldwide distribution of krypton-85 concentrations stemming from emissions from declared reprocessing plants. The results are the basis for scenarios in which emissions from clandestine reprocessing facilities have to be detected against various background levels. It is concluded that today's background imposes heavily on the ability to detect small and medium plutonium separation rates; only high separation rates of 1 SQ per week and higher have a chance to be detected with feasible outlay. A fixed network of monitoring stations seems too costly; instead the high number of samples that are required rather calls for mobile sampling procedures, where air samples are collected at random locations over the world and are analyzed in regional laboratories for their krypton-85 concentration. Further, it is argued that krypton-85 emissions from declared reprocessing activities have to be significantly lowered to enable a worldwide verification of the absence of even smaller clandestine reprocessing. For each scenario the number of samples that have to be taken for probable detection is calculated. Copyright © 2016 Elsevier Ltd. All rights reserved.

  7. 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.

  8. 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

  9. 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

  10. Development of off-gas filters for reprocessing plants. Development and construction of an off-gas filter system for large reprocessing plants. Off-gas section of the resolver test stand of the IHCh

    International Nuclear Information System (INIS)

    Furrer, J.; Kaempffer, R.; Wilhelm, J.G.; Pfauter, C.; Jannakos, K.; Apenberg, W.; Lange, W.; Mendel, W.; Potgeter, G.; Zabel, G.

    1976-01-01

    The test of the highly impregnated iodine sorption material AC 6,120 was continued in the laboratory under simulated conditions of a 1,500 t/a uranium reprocessing plant. The influence of NO in nitrogen as the carrier gas on the removal efficiency of the sorption material has been especially examined. Several experiments on the removal efficiency of iodine sorption by the material AC 6,120 were carried out in the original off-gas of the French processing plant SAP Marcoule while the filter system was installed on the one side directly behind the dissolver and on the other side behind the iodine desorption columm. The first iodine filter developed at LAF II was installed in the off-gas line of the dissolver in the Karlsruhe reprocessing plant. The filter system for the dissolver off-gas handling test rig of the IHCh was specified and ordered with an engineering firm. The conception of the prototype off-gas filter system was selected and a lock and transport system allowing to replace filters was designed and subjected for testing. Five alternative solutions were set up in order to find the appropriate filter concept. The method of selection based on the evaluation of performance criteria. According to the selected solution a filter drum was designed and constructed. The lock of the filter system has been designed and realized. Preliminary tests have been made. (orig.) [de

  11. 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

  12. 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

  13. The minimization of radioactive releases to the sea from the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Sugiyama, T.; Yoshikawa, K.; Ishii, T.

    1996-01-01

    The Tokai Reprocessing Plant (TRP) started hot operation in September 1977. The total amount of about 790 tU of spent fuel, generated in Japan, has been successfully reprocessed as of December 1994. Low-level liquid wastes have been treated safely with the low-level waste treatment process. The design of TRP was based on foreign technology. In the early stage of designing, the radioactivity released to the sea was estimated at approximately 2.6 TBq/day (70 Ci/day) for beta activity (except for tritium). Later, PNC added an evaporator to the process to reduce the level down to 1/100, i.e. 9.6 TBq/year (260 Ci/year) or 2.6 x 10 -2 TBq/day (0.7 Ci/day). In addition, under the supervision of the government, PNC started R and D to further decrease the radioactivity released to the sea in terms of ALARA. Aiming at reducing the activity from 9.6 TBq/year (260 Ci/year) to 1/10 of that value (i.e. 26 Ci/year), the release reduction technology development facility was added. This facility was incorporated into the low-level waste treatment process in 1980, before starting the regular operation of TRP. Since the fuel reprocessing commenced, total radioactivity discharged to the sea has been 1.9 x 10 -2 TBq (0.51 Ci) for beta activity, as of December 1994. Before incorporating the release reduction technology development facility, the yearly level was 3.7 x 10 -3 - 7.4 x 10 -3 TBq (0.1 - 0.2 Ci). After incorporation of the facility, radioactivity released to the sea was greatly decreased to non-detection levels in recent years, in spite of increasing annual reprocessing amounts. Although serious equipment failures have occurred such as the acid recovery evaporator and the dissolvers, there was no influence on radioactivity released to the sea. (author)

  14. 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

  15. Process pump operating problems and equipment failures, F-Canyon Reprocessing Facility, Savannah River Plant

    International Nuclear Information System (INIS)

    Durant, W.S.; Starks, J.B.; Galloway, W.D.

    1987-02-01

    A compilation of operating problems and equipment failures associated with the process pumps in the Savannah River Plant F-Canyon Fuel Reprocessing Facility is presented. These data have been collected over the 30-year operation of the facility. An analysis of the failure rates of the pumps is also presented. A brief description of the pumps and the data bank from which the information was sorted is also included

  16. Preliminary concepts: coordinated safeguards for materials management in a thorium--uranium fuel reprocessing plant

    International Nuclear Information System (INIS)

    Hakkila, E.A.; Barnes, J.W.; Dayem, H.A.; Dietz, R.J.; Shipley, J.P.

    1978-10-01

    This report addresses preliminary concepts for coordinated safeguards materials management in a typical generic thorium--uranium-fueled light-water reactor (LWR) fuels reprocessing plant. The reference facility is designed to recover thorium and uranium from first-generation (denatured 235 U) startup fuels, first-recycle and equilibrium (denatured 233 U) thorium--uranium LWR fuels, and to recover the plutonium generated in the 238 U denaturant as well. 12 figures, 3 tables

  17. Reprocessing of spent nuclear fuel

    International Nuclear Information System (INIS)

    Kidd, S.

    2008-01-01

    The closed fuel cycle is the most sustainable approach for nuclear energy, as it reduces recourse to natural uranium resources and optimises waste management. The advantages and disadvantages of used nuclear fuel reprocessing have been debated since the dawn of the nuclear era. There is a range of issues involved, notably the sound management of wastes, the conservation of resources, economics, hazards of radioactive materials and potential proliferation of nuclear weapons. In recent years, the reprocessing advocates win, demonstrated by the apparent change in position of the USA under the Global Nuclear Energy Partnership (GNEP) program. A great deal of reprocessing has been going on since the fourties, originally for military purposes, to recover plutonium for weapons. So far, some 80000 tonnes of used fuel from commercial power reactors has been reprocessed. The article indicates the reprocessing activities and plants in the United Kigdom, France, India, Russia and USA. The aspect of plutonium that raises the ire of nuclear opponents is its alleged proliferation risk. Opponents of the use of MOX fuels state that such fuels represent a proliferation risk because the plutonium in the fuel is said to be 'weapon-use-able'. The reprocessing of used fuel should not give rise to any particular public concern and offers a number of potential benefits in terms of optimising both the use of natural resources and waste management.

  18. Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

    International Nuclear Information System (INIS)

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

    1985-07-01

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

  19. Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1985-07-01

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

  20. Possibilities of tritium removal from waste waters of pressurized water reactors and fuel reprocessing plants

    International Nuclear Information System (INIS)

    Ribnikar, S.V.; Pupezin, J.D.

    1975-01-01

    Starting from parameters known for heavy water production processes, a parallel was made with separation of tritium from water. The quantity in common is the total cascade flow. The most efficient processes appear to be hydrogen sulfide, water exchange, hydrogen- and water distillation. Prospects of application of new processes are discussed briefly. Problems concerning detritiation of pressurized water reactors and large fuel reprocessing plants are analyzed. Detritiation of the former should not present problems. With the latter, economical detritiation can be achieved only after some plant flow patterns are changed. (U.S.)

  1. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Susan Stacy; Julie Braun

    2006-12-01

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

  3. French experience and prospects in the reprocessing of fast breeder reactor fuels

    International Nuclear Information System (INIS)

    Megy, J.

    1983-06-01

    Experience acquired in France in the field of reprocessing spent fuels from fast breeder reactors is recalled. Emphasis is put on characteristics and quantities of spent fuels reprocessed in La Hague and Marcoule facilities. Then reprocessing developments with the realisation of the new pilot plant TOR at Marcoule, new equipments and study of industrial reprocessing units are reviewed [fr

  4. Tritium control by water recycle in a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Hall, N.E.; Ward, G.N.

    1975-06-01

    A preliminary study was made of the use of water recycle within a reprocessing plant to control the escape of tritium and to consolidate it for disposal. Tritium distribution was evaluated in the leacher, high-level, and low-level systems for seven different flowsheet conditions. Tritium retention efficiency was also evaluated for these flowsheet conditions. Impact of tritiated water recycle on the plant design and operation is assessed. It is concluded that tritium control by water recycle is feasible. Achievement of satisfactory retention efficiencies and economic volumes of solidified tritium waste will require extension of existing technology and development of new technology. Evaluation of potential abnormal conditions indicate that releases from upsets need not be excessive. Some increase in occupational exposure will occur because of the pervasiveness, persistence, and ease of uptake of tritiated water vapor. Incentives for tritium control by water recycle may prove marginal if this increased exposure to plant personnel is significant compared to the small reduction in exposure to the general public. Recommendations are presented for further studies

  5. Final report, Task 3: possible uses of the Nuclear Fuel Services, Inc. reprocessing plant at West Valley, New York

    International Nuclear Information System (INIS)

    1978-01-01

    The West Valley Plant could readily be used for work on reprocessing of alternative fuels, spiking, coprocessing (including CIVEX), waste solidification, and the recovery of radioactive gases. The plant could be easily modified for any scale between small-scale experimental work to production-scale demonstration, involving virtually any combination of fissile/fertile fuel materials that might be used in the future. The use of this plant for the contemplated experimental work would involve lower capital costs than the use of other facilities at DOE sites, except possibly for spiking of recovered products; the operating costs would be no greater than at other sites. The work on reprocessing of alternative fuels and coprocessing could commence within about one year; on recovery of radioactive gases, in 3 to 5 years; on spiking, in 4 years; and on waste solidification demonstration, in about 5 years. The contemplated work could be begun at this plant at least as early as at Barnwell, although work on spiking of recovered products could probably be started in existing hot cells earlier than at West Valley

  6. Initiating events study of the first extraction cycle process in a model reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Renze; Zhang, Jian Gang; Zhuang, Dajie; Feng, Zong Yang [China Institute for Radiation Protection, Taiyuan (China)

    2016-06-15

    Definition and grouping of initiating events (IEs) are important basics for probabilistic safety assessment (PSA). An IE in a spent fuel reprocessing plant (SFRP) is an event that probably leads to the release of dangerous material to jeopardize workers, public and environment. The main difference between SFRPs and nuclear power plants (NPPs) is that hazard materials spread diffusely in a SFRP and radioactive material is just one kind of hazard material. Since the research on IEs for NPPs is in-depth around the world, there are several general methods to identify IEs: reference of lists in existence, review of experience feedback, qualitative analysis method, and deductive analysis method. While failure mode and effect analysis (FMEA) is an important qualitative analysis method, master logic diagram (MLD) method is the deductive analysis method. IE identification in SFRPs should be consulted with the experience of NPPs, however the differences between SFRPs and NPPs should be considered seriously. The plutonium uranium reduction extraction (Purex) process is adopted by the technics in a model reprocessing plant. The first extraction cycle (FEC) is the pivotal process in the Purex process. Whether the FEC can function safely and steadily would directly influence the production process of the whole plant-production quality. Important facilities of the FEC are installed in the equipment cells (ECs). In this work, IEs in the FEC process were identified and categorized by FMEA and MLD two methods, based on the fact that ECs are containments in the plant. The results show that only two ECs in the FEC do not need to be concerned particularly with safety problems, and criticality, fire and red oil explosion are IEs which should be emphatically analyzed. The results are accordant with the references.

  7. Meeting the safeguards challenges of a commercial reprocessing plant

    International Nuclear Information System (INIS)

    Johnson, S.J.; Chesnay, B.; Pearsall, C.; Takeda, S.; Tomikawa, H.; Fujimaki, K.; Iwamoto, T.

    2004-01-01

    Never before has the IAEA taken on such a large challenge as implementing a safeguards system at a commercial reprocessing plant. The challenges lay in a wide range of areas. This paper will present an overview of how specific challenges are being met in: Providing an initial and continuing design verification approach that maintains continuity of knowledge for the life-time of the plant; Providing a robust safeguards approach, including added assurance measures to confirm the operational conditions of the facility; Providing verification systems with the highest sensitivity and reliability, while also being cost efficient; Providing timely and accurate analytical laboratory results; Providing sufficient authentication to joint-use, unattended verification systems to assure that independent conclusions can be reached; Providing a comprehensive integrated software system that allows for remote inspector data handling and evaluation and thus reducing inspection effort. A primary prerequisite to developing and implementing a safeguards approach of this magnitude is the transparent and interactive cooperation of the State and the operator. The JNFL Project has been a model example of this cooperation. This cooperation has been in the areas of system security, operational modifications, schedule adjustments, technical development and financial support. (author)

  8. Authentication of reprocessing plant safeguards data through correlation analysis

    International Nuclear Information System (INIS)

    Burr, T.L.; Wangen, L.E.; Mullen, M.F.

    1995-04-01

    This report investigates the feasibility and benefits of two new approaches to the analysis of safeguards data from reprocessing plants. Both approaches involve some level of plant modeling. All models involve some form of mass balance, either applied in the usual way that leads to material balances for individual process vessels at discrete times or applied by accounting for pipe flow rates that leads to material balances for individual process vessels at continuous times. In the first case, material balances are computed after each tank-to-tank transfer. In the second case, material balances can be computed at any desired time. The two approaches can be described as follows. The first approach considers the application of a new multivariate sequential test. The test statistic is a scalar, but the monitored residual is a vector. The second approach considers the application of recent nonlinear time series methods for the purpose of empirically building a model for the expected magnitude of a material balance or other scalar variable. Although the report restricts attention to monitoring scalar time series, the methodology can be extended to vector time series

  9. Research and development of FBR fuel reprocessing in PNC

    International Nuclear Information System (INIS)

    Hoshino, T.

    1976-05-01

    The research program of the PNC for FBR fuel reprocessing in Japan is discussed. The general characteristics of FBR fuel reprocessing are pointed out and a comparison with LWR fuel is made. The R and D program is based on reprocessing using the aqueous Purex process. So far, some preliminary steps of the research program have been carried out, these include solvent extraction test, off-gas treatment test, voloxidation process study, solidification test of high-level liquid waste, and study of the dissolution behaviour of irradiated mixed oxide fuel. By the end of the 1980s, a pilot plant for FBR fuel reprocessing will be completed. For the design of the pilot plant, further research will be carried out in the following fields: head-end techniques; voloxidation process; dissolution and extraction techniques; waste treatment techniques. A time schedule for the different steps of the program is included

  10. Dynamic behaviour of solvent contactors in fuel reprocessing plants- an analysis

    Energy Technology Data Exchange (ETDEWEB)

    Raju, R P; Siddiqui, H R [Nuclear Waste Management Group, Bhabha Atomic Research Centre, Mumbai (India); Murthy, K K; Kansra, V P [Fuel Reprocessing Group, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    Fuel reprocessing plants carry out separation of useful fissile and fertile materials from spent nuclear fuels by isolating highly radioactive fission products using solvent extraction method. In the fuel reprocessing step of nuclear fuel cycle, optimisation of process parameters in the PUREX flowsheet design is of great importance particularly on account of the need to realize high degree of recovery of fissile and fertile materials and to ensure proper control on concentrations of fissile element in process streams for avoidance of criticality. In counter-current solvent contactors of PUREX flowsheet there are a variety of processes conditions which may cause plutonium accumulations that requires attention to ascertain safe Pu concentrations within the contactors. A study was carried out using the PUREX process mathematical model Solvent Extraction Program Having Interacting Solutes (SEPHIS) for pulsed solvent contactors in PREFRE-1, Tarapur and PREFRE-2, Kalpakkam flowsheets for optimising the process parameters in plutonium purification cycles. The study was extended to predict the behaviour of contactors handling plutonium bearing solutions under certain anticipated deviations in the process parameters. Modifications wherever necessary were carried out to the original SEPHIS code. This paper discusses the results obtained during this analysis. (author). 2 figs., 2 tabs.

  11. Engineering and service activities in the Cogema group

    International Nuclear Information System (INIS)

    1998-03-01

    This short document presents the engineering and service daughter companies of the Cogema group: SGN (nuclear engineering, fuel cycle, wastes and spent fuels management, decontamination and dismantling); Euriware group (advice, expertise and information systems in nuclear, pharmacy, petroleum, automotive and steel making industries); Game group (industrial maintenance in nuclear, chemistry, petroleum, automotive and steel making industries); Eurisys Mesures (nuclear measurements, instrumentation, radiation protection and nuclear imaging); SICN (mechanics); STMI and Socodei (nuclear cleansing and management of low level radioactive wastes); Krebs/Speichim (chemical engineering, divisions of SGN and Technip). (J.S.)

  12. Cogema's world-wide experience in prospecting and surveying uranium deposits

    International Nuclear Information System (INIS)

    Berville, M.; Faure, D.

    1985-01-01

    Having briefly outlined the history of uranium prospection in France, the authors describe COGEMA's prospection operations at home and abroad and analyse the methods applied according to different contexts (granitic and metamorphic rocks, ''sub-discordant'' deposits, sedimentary deposits, prospection in detail of a qualified zone); at the same time they show how technology has developed, particularly in the fields of geophysics and radiometry [fr

  13. Disposal of Kr-85 separated from the dissolver off-gas of a reprocessing plant for LWR fuels

    International Nuclear Information System (INIS)

    Nommensen, O.

    1981-08-01

    The principle of the radiation protection to keep the radiation load of the population as low as possible requires the development of methods for retaining the radionuclide Krypton 85 seperated off the dissolver waste gas of future reprocessing plants for LWR-nuclear fuel elements. In a recommendation of the RSK the long-termed storage of the Kr-85 in a pressure gas bottle and the marine disposal we considered to be disposal methods low in risk. The present work develops a concept for both of the disposal methods and demonstrates their technical feasibility. The comparison of the cost estimations effected for both of the disposal methods shows that the costs related with the marine disposal of the pressure gas bottles amounting to 1.90 DM/kg of reprocessed U fall by the factor 10 below the costs that result from the surface storage of the bottles. In both cases was referred to a reprocessing capacity of 1400 t U/a corresponding to 50 GW installed nuclear power, thereby accumulating approximately 629 PBq (17 MCi) Kr-85 per year. Both concepts project the seperated radioactive inert gas to be filled in pressure gas bottles in a low temperature rectification plant. Each of the 85 bottles to be filled per year contains 7.4 PBq (200 kCi) Kr-85. (orig./HP) [de

  14. THORP's markets begin to crumble

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    British Nuclear Fuels Ltd's (BNFL) new thermal oxide reprocessing plant, THORP, is due to come on line in 1992. THORP has contracts to cover the first 10 years of its operation (1992-2002) with the plant reprocessing about 600-700 tonnes of spent fuel a year. The largest contract is from Japanese utilities (2,300t), United Kingdom business amounts to one third (1,850t) and German utilities have contracted for 760t. Much smaller contracts are also held with Switzerland, Italy, Spain, Sweden and the Netherlands. However, future contracts may be affected by a change in policy away from reprocessing to long term storage of spent fuel elements. Such a change is being considered by Scottish Nuclear Ltd. Japan may transfer its business to its own plant planned for operation by 1998. Other countries are discontinuing their nuclear power programmes and will not need reprocessing facilities in the future. Only Germany has signed contracts beyond 2002 and some of these have gone to Cogema's new plant. Thus it may be difficult for THORP to find enough business in the longer term future. (U.K.)

  15. 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

  16. A study of safeguards approach for the area of plutonium evaporator in a large scale reprocessing plant

    International Nuclear Information System (INIS)

    Sakai, Hirotada; Ikawa, Koji

    1994-01-01

    A preliminary study on a safeguards approach for the chemical processing area in a large scale reprocessing plant has been carried out. In this approach, plutonium inventory at the plutonium evaporator will not be taken, but containment and surveillance (C/S) measures will be applied to ensure the integrity of an area specifically defined to include the plutonium evaporator. The plutonium evaporator area consists of the evaporator itself and two accounting points, i.e., one before the plutonium evaporator and the other after the plutonium evaporator. For newly defined accounting points, two alternative measurement methods, i.e., accounting vessels with high accuracy and flow meters, were examined. Conditions to provide the integrity of the plutonium evaporator area were also examined as well as other technical aspects associated with this approach. The results showed that an appropriate combination of NRTA and C/S measures would be essential to realize a cost effective safeguards approach to be applied for a large scale reprocessing plant. (author)

  17. Conclusion of the I.C.T. benchmark exercise

    International Nuclear Information System (INIS)

    Giacometti, A.

    1991-01-01

    The ICT Benchmark exercise made within the RIV working group of ESARDA on reprocessing data supplied by COGEMA for 53 routines reprocessing input batches made of 110 irradiated fuel assemblies from KWO Nuclear Power Plant was finally evaluated. The conclusions are: all seven different ICT methods applied verified the operator data on plutonium within about one percent; anomalies intentionally introduced to the operator data were detected in 90% of the cases; the nature of the introduced anomalies, which were unknown to the participants, was completely resolved for the safeguards relevant cases; the false alarm rate was in a few percent range. The ICT Benchmark results shows that this technique is capable of detecting and resolving anomalies in the reprocessing input data to the order of a percent

  18. Dose evaluation for the public around the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Takeishi, Minoru; Furuta, Sadaaki; Miyabe, Kenjiro; Shinohara, Kunihiko

    2007-01-01

    The dose evaluations for the public around the Tokai Reprocessing Plant (TRP) have been carried out by using the mathematical models, because the effects on the environmental radiation due to the operation of the TRP are too small to separate from the background level. The models were developed by the site-specific investigations of the environment and reviewed in several times based on the latest scientific knowledge. The maximum annual effective dose through the whole period of the operation of the TRP was evaluated as 1.4 μSv with the data of the discharge monitoring and the meteorological observation in 1992. The evaluated doses revealed to be kept as far below the annual dose limit for the public as 1 mSv. (author)

  19. 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

  20. Treatment of solid waste highly contaminated by alpha emitters

    International Nuclear Information System (INIS)

    Madic, C.; Breschet, C.; Vigreaux, B.

    1990-01-01

    In the recent years, efforts have been made in order to reduce the amount of alpha emitters essentially plutonium isotopes present in the solid wastes produced either during research experiments on fuel reprocessing, done in the Radiochemistry building in the centre d'etudes nuclearires de FONTENAY-AUX-ROSES (CEA, FRANCE), or in the MARCOULE reprocessing plant (COGEMA, FRANCE). The goals defined for the treatments of these different wastes were: to reduce their α and β, γ, contamination levels. and to recover the plutonium, an highly valuable material, and to minimize its quantity to be discharged with the wastes. To achieve these goals leaching processes using electrogenerated Ag (II (a very aggressive agent for PuO 2 )) in nitric acid solutions, were developed and several facilities were designed and built to operate the processes: ELISE and PROLIXE facilities: PILOT ASHES FACILITY for delete, the treatment of plutonium contaminated ashes (COGEMA, MARCOULE). A brief description of the process and of the different facilities will be presented in this paper; the main results obtained in ELISE and PROLIXE are also summarized

  1. Review of thorium fuel reprocessing experience

    International Nuclear Information System (INIS)

    Brooksbank, R.E.; McDuffee, W.T.; Rainey, R.H.

    1978-01-01

    The review reveals that experience in the reprocessing of irradiated thorium materials is limited. Plants that have processed thorium-based fuels were not optimized for the operations. Previous demonstrations of several viable flowsheets provide a sound technological base for the development of optimum reprocessing methods and facilities. In addition to the resource benefit by using thorium, recent nonproliferation thrusts have rejuvenated an interest in thorium reprocessing. Extensive radiation is generated as the result of 232 U-contamination produced in the 233 U, resulting in the remote operation and fabrication operations and increased fuel cycle costs. Development of the denatured thorium flowsheet, which is currently of interest because of nonproliferation concerns, represents a difficult technological challenge

  2. Development of remote fuel pushing system in Reprocessing Plant, Tarapur

    International Nuclear Information System (INIS)

    Chandra, Munish; Coelho, G.; Kodilkar, S.S.; Mishra, A.K.; Bajpai, D.D.; Nair, M.K.T.

    1990-01-01

    Power Reactor Fuel Reprocessing Plant (PREFRE), Tarapur has been processing spent fuel arising from Pressurized Heavy Water Reactors for quite some time. The process adopted in the plant is purex process with chopleach head end treatment. The head end treatment involves loading of ten spent fuel bundles in the charging cask at a time in the fuel bay and aligning the cask with the transfer port and subsequently pushing all the ten bundles together into the fuel magazine. At present the fuel is pushed into the magazine manually. Since the ten bundles weigh approximately 200 Kg. and involves pushing of 9.4 meters length, the operation is carried out using stainless steel screwed pipes, in steps of five lengths. The entire operation requires a large number of trained skilled workers and is found to be tedious. To solve this problem a hydraulic cum pneumatic fuel pushing system has been designed, fabricated, tested and is in the process of installation in the fuel handling area. This paper describes various requirements, constraints and dimensional details arising in the incorporation of such a system to be back fitted in an existing plant, though many of these constraints can be avoided in future plants. Further, complete sequence of operations, technical specifications regarding the telescopic hydraulic power pack and associated controls incorporated in the system are highlighted. (author). 2 figs

  3. Dynamic analysis and response spectra for the main process building of a reprocessing plant

    International Nuclear Information System (INIS)

    Hilpert, H.J.; Henkel, F.O.

    1988-01-01

    This paper deals with the determination of the floor response spectra for the main process building of the planned reprocessing plant due to the special loading conditions of earthquake, airplane crash and blast. With these spectra the stress and strain of the components and their bearing forces which react on the building can be calculated. Some special problems depending on the length of the building are not yet answered and will be discussed later. (orig.)

  4. The use of neptunium-239 to assess neptunium distribution throughout a nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Mair, M.A.; Savage, D.J.; Prentice, P.C.

    1989-08-01

    A radiometric technique has been devised to use the gamma emission from the neptunium-239 daughter of americium-243 to estimate neptunium distribution in a plant reprocessing irradiated plutonium based fuels. Three trials were undertaken with samples from the Prototype Fast Reactor at Dounreay. The trials have confirmed the previous chemical measurements and the usefulness of this technique to highlight the effect of altered flowsheet conditions. (author)

  5. 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)

  6. Summary of typical routine maintenance activities at Tokai Reprocessing Plant. Supplement (March, 2002)

    International Nuclear Information System (INIS)

    2002-03-01

    Typical maintenance activities, such as replacement of worn out parts and cleaning of filter elements, routinely performed during steady operation are summarized. [The Summary of Typical Routine Maintenance Activities at Tokai Reprocessing Plant] (JNC TN 8450 2001-006) was already prepared in September, 2001. The purpose of this summary is to give elementary understanding on these activities to people who are responsible for explanation them to the public. At this time, the same kind of summary is prepared as a supplement of the previous one. (author)

  7. Radioecological studies on plutonium and iodine-129 in the surroundings of the Karlsruhe reprocessing plant

    International Nuclear Information System (INIS)

    Schuettelkopf, H.; Pimpl, M.

    1982-01-01

    Plutonium and 129 I are emitted from the Karlsruhe Reprocessing Plant (WAK) together with exhaust air and liquid effluents. Plutonium dispersion in the environment was used to calculate the dispersion factors, to determine the rates of deposition on grass and of the total deposition rates, to measure the distribution at depth of plutonium in the soil and to evaluate the contamination of plants and animals in the environment of the Karlsruhe Reprocessing Plant. The plutonium emissions with the liquid effluents were studied to deepen understanding of the process of sedimentation in a river system. Sediments, water samples, aerosols and living organisms from the Altrhein were examined. Factors of transfer to various organisms living in the Altrhein were measured. Most of the 129 I release from WAK goes via the exhaust air: this even applies after installation of an iodine filter into the exhaust air stack. The 129 I contamination of the environmental air, the soil, thyroids and milk was measured. Regarding the milk/air concentration ratio, a mean value of 210 was determined with a scattering range of 50 to 1480. Soil contamination was studied very thoroughly. Iodine-129 is transported into lower soil layers at a very slow rate only, if at all. The contamination of the soil with 129 I remained largely constant during the three years of investigations. The low rates of deposition of 0.02 to 0.05 cm/s indicate that 129 I is released to the environmental air again from plants undergoing the process of rotting. (author)

  8. 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

  9. Cancer mortality of nuclear workers of CEA and COGEMA from 1969 to 1986

    International Nuclear Information System (INIS)

    Tirmarche, M.; Raphalen, A.; Allin, F.; Le Guen, P.

    1992-01-01

    Cancer mortality of the nuclear workers of CEA and COGEMA has been collected by the occupational health services of both firms from 1969 to 1986. The data are related only to the workers who died when in activity. Only very few workers left CEA and COGEMA before retirement so we consider this mortality survey as describing correctly the cancer mortality for the age groups less than 60-65 years old. Compared to the national mortality of same sex, age and calendar period, by the method of indirect standardization, the only excess observed was in the female population, linked to breast cancer mortality. The male population demonstrated a high healthy worker effect, even for cancer mortality. This study has now to be completed by an typical epidemiological cohort study in order to test cancer mortality after retirement and to discuss a possible relation with occupational exposure. (author)

  10. 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

  11. 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

  12. A welcoming approach to winning support [public relations policy at the Sellafield Reprocessing Plant

    International Nuclear Information System (INIS)

    Harding, C.G.F.

    1988-01-01

    The public relations policy of British Nuclear Fuels with respect to the Sellafield reprocessing centre is described. Key factors in reassuring the public on the safety of the plant have been the opening of an exhibition centre and a widely advertised open invitation to visit Sellafield together with a commitment to an open information policy and the promotion of understanding through the use of less technical language. An improvement in public confidence in Sellafield is reported. (U.K.)

  13. Operational experience of gaseous effluent treatment at the Eurochemic reprocessing plant

    International Nuclear Information System (INIS)

    Osipenco, A.; Detilleux, E.

    1977-01-01

    The EUROCHEMIC fuel reprocessing plant applies the PUREX flow sheet. Two particular features of the plant influence gaseous and liquid effluents: chemical decanning and the ability to process a wide range of fuels, uranium metal or oxide, having an initial enrichment typical of power reactors (up to 5%) or material testing reactors (up to 93%). The ventilation circuits, treatment plant and monitoring equipment for gaseous releases are briefly described. No retention facilities for rare gases, tritium, or carbon-14 are provided. The releases are monitored for krypton-85, iodine-131, alpha and beta-gamma aerosols and tritium. Between 1966 and 1974 the plant processes about 200 tonnes of power reactor fuel, from which about 0.7 tonnes of plutonium and 1.5 tonnes of highly enriched uranium were separated. The most important points in the operation of the gas cleaning equipment are indicated: efficiency, operational reliability, incidents, etc.. Actual discharges as measured are compared with the limits set in the operation licence. Using the atmospheric diffusion coefficients, the dose commitment is estimated. The low level liquid effluents are passed, after neutralization, to the treatment plant of the Belgian nuclear center CEN/SCK. However, if the activity exceeds the limit set by the CEN/SCK, the effluents are concentrated by evaporation and stored on the EUROCHEMIC site. (orig.) [de

  14. Production from new uranium mines a Cogema resources Saskatchewan perspective

    International Nuclear Information System (INIS)

    Pollock, B.

    2001-01-01

    The province of Saskatchewan is best known for the large flat tracts of land in the south that are primarily used for agricultural purposes. Less well known is the fact that the northern part of the province hosts the richest uranium mines in the world. In fact, to use a petroleum analogy, Saskatchewan has been referred to as the 'Saudi Arabia' of the uranium producing countries. The mining industry in Saskatchewan is a flourishing, high technology industry and supplies approximately one-third of the annual world primary production of uranium. The purpose of this paper is to examine the uranium mining industry in Saskatchewan and why this province stands alone as the dominant uranium producer in the world and will maintain that position into the foreseeable future. As well, an overview of the significant role played by COGEMA Resources in developing the Saskatchewan uranium industry will be undertaken. This company whose roots date back almost 40 years in the province, now holds significant interests in all four of the mines currently producing uranium. With investments of over one billion dollars (U.S.) in this province, COGEMA has established itself as a long-term player in the Saskatchewan Uranium Industry. (author)

  15. Reprocessing and public opinion. Analysis of 30 years of relations between Marcoule and its environment

    International Nuclear Information System (INIS)

    Michel, P.M.

    1987-01-01

    The construction of the Marcoule nuclear center in the Rhone Valley was a part of the industrial development of this region. A large hydraulic power plant and two facilities for metal electrochemical processing were already operating in this country. The nuclear center and the Cogema nuclear plants allowed 3800 employments. This good social impact added to many operation years without accident and a good communication policy with school and media make that there is no nuclear controversy in this area [fr

  16. Safety demonstration test on solvent fire in fuel reprocessing plant

    International Nuclear Information System (INIS)

    Nishio, Gunji; Hashimoto, Kazuichiro

    1989-03-01

    This report summarizes a fundamental of results obtained in the Reprocessing Plant Safety Demonstration Test Program which was performed under the contract between the Science and Technology Agency of Japan and the Japan Atomic Energy Research Institute. In this test program, a solvent fire was hypothesized, and such data were obtained as fire behavior, smoke behavior and integrity of exhaust filters in the ventilation system. Through the test results, it was confirmed that under the fire condition in hypothetical accident, the integrity of the cell and the cell ventilation system were maintained, and the safety function of the exhaust filters was maintained against the smoke loading. Analytical results by EVENT code agreed well with the present test data on the thermofluid flow in a cell ventilation system. (author)

  17. 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)

  18. 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

  19. Preliminary field tests of near-real-time materials accountancy system at the Tokai Reprocessing Plant (TASK F)

    International Nuclear Information System (INIS)

    Tsutsumi, Masayori; Sawahata, Toshio; Sugiyama, Toshihide; Tanaka, Kazuhiko; Suyama, Naohiro

    1982-01-01

    A study of applying the proposed near-real-time material accountancy model to the Tokai Reprocessing Plant, PNC (Power Reactor and Nuclear Fuel Development Corp.), showed that the model was feasible and effective to meet the IAEA (International Atomic Energy Agency) safeguards criteria in terms of detection timeliness and sensitivity. This study using the computer simulation technique is shown in this paper. In order to investigate the applicability of the model to the actual plant, the field test was carried out on the process in the material balance area (MBA) which covers the area from the input accountability vessel (IAV) to the product accountability vessel (PAV), in cooperation with JAERI. The key measuring points for dynamic physical inventory counts (D-PIT) are shown. The results of test evaluation are as follows: For timely detection, it will be able to evaluate an abnoumal accountancy in process by using the MUFd (material unaccounted for) obtained by the D-PIT about once every week. Therefore, this seems to satisfy the timely detection of IAEA safeguards criteria. As for detection, sensitivity and verification procedures, in order to clarify these criteria for a large scale reprocessing plant, further research and development will be required. In addition, since the field test was carried out along with normal plant operation, additional man-power problem was also considered. (Wakatsuki, Y.)

  20. Reduced waste arise in a reprocessing plant by the use of remote control

    International Nuclear Information System (INIS)

    Issel, W.A.

    1988-01-01

    This paper discusses how the increasing use of remote controlled processes, which is unavoidable with respect to work in hostile environment and which after serious further development and experience may improve plant production rate lead to another benefit in handling nuclear material, the benefit of reducing waste production and by this the avoidance of radioactive dispersal. The example of reprocessing of spent fuel is shown, what consequences and what improvements can be expected in the waste management by remote handling and maintenance instead of direct intervention by men

  1. Transformative monitoring approaches for reprocessing.

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin B.

    2011-09-01

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

  2. Benchmark data for a large reprocessing plant for evaluation of advanced data analysis algorithms and safeguards system design

    International Nuclear Information System (INIS)

    Burr, T.L.; Coulter, C.A.; Wangen, L.E.

    1998-02-01

    This report describes the simulation and analysis of solution level and density (L,D) in all key main process tanks in a large reprocessing plant. In addition, initial provisions were made to include temperature (T) data in the analysis at a later time. FacSim, a simulation program developed at Los Alamos, was used to generate simulated process operating data for the Rokkasho Reprocessing Plant (RRP) that is now under construction in Japan. Both normal facility operation and more than thirty abrupt diversion scenarios were modeled over 25-day periods of simulated operation beginning with clean startup of the facility. The simulation tracked uranium, plutonium (both +3 and +4 oxidation states), HNO 3 diluent, and tributyl phosphate from the input accountability vessel to the plutonium output accountability vessel, with the status of each process vessel and many pipes recorded at intervals of approximately four minutes. These data were used to determine solution volume and density values in each process vessel as a function of time

  3. Corrosion evaluation of uranyl nitrate solution evaporator and denitrator in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Yamanaka, Atsushi; Hashimoto, Kowa; Uchida, Toyomi; Shirato, Yoji; Isozaki, Toshihiko; Nakamura, Yoshinobu

    2011-01-01

    The Tokai reprocessing plant (TRP) adopted the PUREX method in 1977 and has reprocessed spent nuclear fuel of 1140 tHM (tons of heavy metals) since then. The reprocessing equipment suffers from various corrosion phenomena because of high nitric acidity, solution ion concentrations, such as uranium, plutonium, and fission products, and temperature. Therefore, considering corrosion performance in such a severe environment, stainless steels, titanium steel, and so forth were employed as corrosion resistant materials. The severity of the corrosive environment depends on the nitric acid concentration and the temperature of the solution, and uranium in the solution reportedly does not significantly affect the corrosion of stainless steels and controls the corrosion rates of titanium steel. The TRP equipment that handles uranyl nitrate solution operates at a low nitric acid concentration and has not experienced corrosion problems until now. However, there is a report that corrosion rates of some stainless steels increase in proportion to rising uranium concentrations. The equipment that handles the uranyl nitrate solution in the TRP includes the evaporators, which concentrate uranyl nitrate to a maximum concentration of about 1000 gU/L (grams of uranium per liter), and the denitrator, where uranyl nitrate is converted to UO 3 powder at about 320degC. These equipments are therefore required to grasp the degree of the progress of corrosion to handle high-temperature and high-concentration uranyl nitrate. The evaluation of this equipment on the basis of thickness measurement confirmed only minor corrosion and indicated that the equipment would be fully adequate for future operation. (author)

  4. 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

  5. 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)

  6. Study on the combustion behavior of radiolytically generated hydrogen explosion in small scale annular vessels at the reprocessing plant

    International Nuclear Information System (INIS)

    Kudo, Tatsuya; Tamauchi, Yoshikazu; Arai, Nobuyuki; Dai, Wenbin; Sakaihara, Motohiro; Kanehira, Osamu

    2017-01-01

    Hydrogen is generated by radiolysis of water, etc. in process vessels in reprocessing plant. Usually, the hydrogen is scavenged by compressed air into vessels to prevent hydrogen explosion. When an earthquake beyond design based occurs, for example, the compressed air may stop and the hydrogen starts accumulating in the vessels, and under this condition, an ignition source might set off hydrogen explosion. Therefore, the explosion derived by the radiolytically generated hydrogen is designated as one of severe accidents on Rokkasho Reprocessing Plant in new regulatory requirements. It is important to understand the combustion behavior of hydrogen explosion inside a vessel for consideration of safety measures against the severe accident, because the influences of detonation are not considered in the design basis of vessels. Especially, the investigations about the combustion behavior which considered influence of interior obstacles inside the vessel are not performed yet. In order to investigate the combustion behavior comprehensively, explosion experiment, combustion analysis and structural analysis are carried out using the representative vessels (small scale annular vessel, small scale plate vessel, large scale annular vessel and large scale cylindrical vessel) selected from Rokkasho Reprocessing Plant. In this paper, the results of experiments and analysis of small scale annular vessel (as one of representative vessel, imitated a pulsed column in the reprocessing plant) are reported. As imitated vessels, three vessels are manufactured with different interior obstacle arrangements as follows, A) cylindrical obstacles are faithfully reproduced and are arranged based on the actual vessel, B) cylindrical obstacles are arranged more densely than the actual vessel, and C) there are no obstacles inside the vessel. Experiments of hydrogen explosion are performed under condition of stoichiometric hydrogen-air ratio (premixed hydrogen-air is used). As a result of

  7. Mox fuels recycling

    International Nuclear Information System (INIS)

    Gay, A.

    1998-01-01

    This paper will firstly emphasis that the first recycling of plutonium is already an industrial reality in France thanks to the high degree of performance of La Hague and MELOX COGEMA's plants. Secondly, recycling of spent Mixed OXide fuel, as a complete MOX fuel cycle, will be demonstrated through the ability of the existing plants and services which have been designed to proceed with such fuels. Each step of the MOX fuel cycle concept will be presented: transportation, reception and storage at La Hague and steps of spent MOX fuel reprocessing. (author)

  8. Safety demonstration tests of air-ventilation system for the postulated explosive burning in a cell of fuel-reprocessing plant

    International Nuclear Information System (INIS)

    Takada, Junichi; Suzuki, Motoe; Tukamoto, Michio; Koike, Tadao; Nishio, Gunji

    1995-03-01

    Safety demonstration tests of an explosive burning in a cell in the reprocessing plant has been carried out in JAERI under the auspices of the Science and Technology Agency, to evaluate the safety of an air-ventilation system during the hypothetical explosion. The postulated explosive burning of organic solvent mixed with nitric acid was simulated by solid explosives. The demonstration test was performed using an industrial scale experimental facility simulating to the ventilation system of the large scale reprocessing plant in JAPAN. Propagations of pressure, temperature, and gas velocity through cells and ducts in the ventilation system were measured during the explosive burning under deflagration. Experimental data in this report can be used to evaluate the transport phenomena of radioactive materials in the ventilation system during the explosion, and also to verify computer code CELVA for the safety analysis of ventilation system in the event of explosion accidents. (author)

  9. Aerosols released from solvent fire accidents in reprocessing plants

    International Nuclear Information System (INIS)

    Jordan, S.; Lindner, W.

    1985-01-01

    Thermodynamic, aerosol characterizing and radiological data of solvent fires in reprocessing plants have been established in experiments. These are the main results: Depending on the ventilation in the containment, kerosene-TBP mixtures burn at a rate up to 120 kg/m 2 h. The aqueous phase of inorganic-organic mixtures might be released during the fire. The gaseous reaction products contain unburnable acidic compounds. Solvents with TBP-nitrate complex shows higher (up to 25%) burning rates than pure solvents (kerosene-TBP). The nitrate complex decomposes violently at about 130 0 C with a release of acid and unburnable gases. Up to 20% of the burned kerosene-TBP solvents are released during the fire in the form of soot particles, phosphoric acid and TBP decomposition products. The particles have an aerodynamic mass median diameter of about 0.5 μm and up to 1.5% of the uranium fixed in the TBP-nitrate complex is released during solvent fires. (orig.)

  10. 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

  11. Fast reactor fuel reprocessing plant D1206: disassembly cave window 4 replacement

    International Nuclear Information System (INIS)

    Sutherland, H.G.; Beckitt, S.; Potts, A.B.

    1996-01-01

    At UKAEA's fast reactor reprocessing plant at Dounreay, the containment glass on the zinc bromide cave viewing window tank failed after 13 years active use. External shielding was fitted and the window tank subsequently drained to make it safe. Fuel cropping operations carried out behind the window were resited to enable cave work to continue whilst a project team made arrangements and plans to replace the damaged window. Because of the complexity of the task and high (alpha, beta, gamma and neutron) radiation levels in excess of 500 Sv/hr a rehearsal facility was built to develop the remote handling techniques to be employed in the task. (UK)

  12. Start-up of commercial high level waste vitrification facilities at La Hague

    International Nuclear Information System (INIS)

    Sombret, C.; Jouan, A.; Fournier, W.; Alexandre, D.; Leroy, L.

    1991-01-01

    The paper describes industial experience gained in France for vitrification of fission products generated by spent fuel reprocessing. The continuous vitrification process developed by CEA, SGN and COGEMA is outlined and Marcoule Vitrification Facility (AVM), with output results since start-up of hot operation in June 1978, briefly presented. Vitrification of high-level liquid waste has now entered an industrial phase at La Hague with R7 and T7 facilities. R7 and T7 have each been designed to process FP solutions generated by reprocessing LWR fuel with an initial enrichment of 3.5% and a discharge burn-up of 33,000 MWd/t. R7 active operations began on June, 1989. This facility is now vitrifying the backlog of fission products resulting from the existing UP2 reprocessing plant, which is being currently extended. Scheduled to start early in 1992, T7 will vitrify the fission products, dissolution fines and sodium-rich solutions issuing from UP3 plant

  13. Capability of minor nuclide confinement in fuel reprocessing

    International Nuclear Information System (INIS)

    Fujine, Sachio; Uchiyama, Gunzo; Mineo, Hideaki; Kihara, Takehiro; Asakura, Toshihide

    1999-01-01

    Experiment with spent fuels has started with the small scale reprocessing facility in NUCEF-BECKY αγ cell. Primary purpose of the experiment is to study the capability of long-lived nuclide confinement both in the PUREX flow sheet applied to the large scale reprocessing plant and also in the PARC (Partitioning Conundrum key process) flow sheet which is our proposal as a simplified reprocessing of one cycle extraction system. Our interests in the experiment are the behaviors of minor long-lived nuclides and the behaviors of the heterogeneous substances, such as sedimentation in the dissolver, organic cruds in the extraction banks. The significance of those behaviors will be assessed from the standpoint of the process safety of reprocessing for high burn-up fuels and MOX fuels. (author)

  14. In-depth analysis of accidental criticality in a reprocessing plant

    International Nuclear Information System (INIS)

    Thomas, W.; Gmal, B.

    1989-01-01

    An in-depth-analysis including probabilistic considerations has been performed for a potential criticality excursion in two large vessels in a planned reprocessing plant. Criticality safety of these components is based on limitation of uranium and plutonium concentration. The main intention of this study was to investigate the potential and probable magnitude of a criticality in greater detail and to detect possible weaknesses of criticality safety provisions. The results of the analysis show, that the calculated probability of less than 5 · 10 -4 /a a for a criticality excursion in the most relevant rework tank may be further reduced. The peak power rework tank may be further reduced by design modifications. The peak power and total fissions of the critical excursion as assessed in a preceding analysis for licensing are conservative by factors of 10 and 4, respectively

  15. Human and technical factors in the doses reduction and optimization at Cogema/Marcoule; Facteurs techniques et humains dans la reduction et l'optimisation des doses a Cogema/Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    Bourgogne, J.L. [Cogema, 30 - Marcoule (France)

    1998-07-01

    In the case of Cogema/Marcoule, the constant decrease of radiation doses is attributed to three factors: technical with a surveillance system and doses optimization, relational with the promotion of confidence in teams of radiation protection services as an acceptation factor of radiation protection techniques and psychological with an evolution of minds towards the ALARA approach. (N.C.)

  16. 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

  17. 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

  18. Suggestions of radiation protection instruments in ships used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants

    International Nuclear Information System (INIS)

    Warenmo, G.

    1979-01-01

    Some radiation protection measures are necessary in ships which will be used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants in order to protect the crew from unnecessarily high radiation doses and to ensure that not allowable values occur. Such measures are discussed in this report as well as suitable radiation protection instruments for such ships. (E.R.)

  19. Studies in the dissolver off-gas system for a spent FBR fuel reprocessing plant

    International Nuclear Information System (INIS)

    Heinrich, E.; Huefner, R.; Weirich, F.

    1982-01-01

    Investigations of possible modifications of the process steps of a dissolver off-gas (DOG) system for a spent FBR fuel reprocessing plant are reported. The following operations are discussed: iodine removal from the fuel solution; behaviour of NOsub(x) and iodine in nitric acid off-gas scrubbers at different temperatures and nitric acid concentrations; iodine desorption from the scrub acid; selective absorption of noble gases in refrigerant-12; cold traps. The combination of suitable procedures to produce a total DOG system is described. (U.K.)

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

    International Nuclear Information System (INIS)

    Numao, Teruhiko; Nakayashiki, Hiroshi; Arai, Nobuyuki; Miura, Susumu; Takahashi, Yoshiharu; Nakamura, Hironobu; Tanaka, Izumi

    2007-01-01

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

  1. Report from the production and exchanges commission about the resolution proposal (no 2937) of Mr Noel Mamere which aims at creating an inquiry commission relative to the existence and storage of ultimate nuclear wastes at the Hague plant, in violation of the law from December 30, 1991, and under the liabilities of Cogema

    International Nuclear Information System (INIS)

    Bono, M.

    2001-04-01

    This document presents the motives of the French production and exchanges commission for the rejection of the proposal from the French 'green' deputy Noel Mamere about the creation of an inquiry commission which would aim at verifying the illegal storage of irradiated MOX fuels from German nuclear facilities at the Cogema La Hague plant. (J.S.)

  2. 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

  3. 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)

  4. ERDA activities related to reprocessing and plutonium recycle

    International Nuclear Information System (INIS)

    Spurgeon, D.R.

    1977-01-01

    ERDA has redirected its program in support of the LWR fuel cycle from one emphasizing the commercialization of existing fuel cycle technology to a broader based assessment of alternative fuel cycle concepts with the emphasis on safeguardability and avoidance of proliferation risks. As part of this program, ERDA will evaluate a number of possible technical and institutional options to reduce proliferation risks. ERDA will continue its current program of LWR fuel reprocessing R and D with added emphasis on improved safeguards capability as well as the applicability of conventional reprocessing technology to large multinational plants. These activities and supporting design studies will provide the basis for a decision regarding the design of an optimized system for the management of spent LWR fuel. Such a system would provide a model for the development of future domestic and foreign facilities and programs. A recently completed ERDA study of the benefits of LWR reprocessing and recycle would also be expected to be factored into such a decision. The study concluded that based on currently available data, recycle of uranium and plutonium in LWR's is attractive from the standpoint of economics and resource utilization relative to the discarding of spent fuel. The LWR reprocessing/recycle picture today is clouded by several unresolved policy issues. These include the need for adequate spent fuel storage capacity for both domestic and foreign reactors; the possibility of foreign reprocessing of U.S. produced fuel; the possibility of the disposal of foreign fuel in the U.S.; the possible need to dispose of wastes generated by multinational reprocessing plants; and finally, determination of the optimum balance between recycling recovered plutonium and saving it for the breeder

  5. Floor response spectra of the main process building of a reprocessing plant against earthquake, airplane crash and blast

    International Nuclear Information System (INIS)

    Hilpert, H.J.

    1987-01-01

    In the general concept of the planned reprocessing plant for spent fuel elements, the main process building has the central function. This building will be designed to withstand earthquake, airplane crash and blast. This report deals with the stress on components and systems due to vibration of the building, the floor response spectra

  6. Conception and development of a computer-aided design for a spent fuel reprocessing plant

    International Nuclear Information System (INIS)

    Blayrac, M.

    1989-06-01

    A spent fuel reprocessing plant is composed of connected equipments. The aim of this study is the creation of schemes representing the different workshops of the plant and the calculation of linkage characteristics (flux) from a graphic description of functional structures. The program, written in FORTRAN 77, based on mass, flow rate and energy conservation, uses a module library each corresponding to an elementary operation of chemical engineering. Verification is necessary for result quality and accuracy. The important number of parameters and variables used in the program, requires a diagnosis accelerating research of errors for correction. Knowledges used in these last operations are qualitative (knowledge of experts) and quantitative (results of calculations) for the development of an expert system written in D-PROLOG [fr

  7. Bitumen and cement solidifications of LL and ML liquid radwaste. The SGN experience

    International Nuclear Information System (INIS)

    Tchemitcheff, E.; Roux, P.

    1993-01-01

    The presentation is focused on the thin-film evaporator technology and the experience gained in the field of the NPPs and research centers on radwaste conditioning. As early as 1970, SGN was licensed by the CEA for the bituminization of LL and ML radwaste. With the support of EDF and COGEMA, SGN has been performing in depth research on cement solidification of borated concentrates and ion exchange resins generated by reactors or reprocessing plant since 1983

  8. 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.

  9. Thorium base fuels reprocessing at the L.P.R. (Radiochemical Processes Laboratory) experimental plant

    International Nuclear Information System (INIS)

    Almagro, J.C.; Dupetit, G.A.; Deandreis, R.A.

    1987-01-01

    The availability of the LPR (Radiochemical Processes Laboratory) plant offers the possibility to demonstrate and create the necessary technological basis for thorium fuels reprocessing. To this purpose, the solvents extraction technique is used, employing TBP (at 30%) as solvent. The process is named THOREX, a one-cycle acid, which permits an adequate separation of Th 232 and U 233 components and fission products. For thorium oxide elements dissolution, the 'chopp-leach' process (installed at LPR) is used, employing a NO 3 H 13N, 0.05M FH and 0.1M Al (NO 3 ) 3 , as solvent. To adapt the pilot plant to the flow-sheet requirements proposed, minor modifications must be carried out in the interconnection of the existing decanting mixers. The input of the plant has been calculated by Origin Code modified for irradiations in reactors of the HWR type. (Author)

  10. 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)

  11. Consolidated fuel reprocessing program. Developments for the future in reprocessing

    International Nuclear Information System (INIS)

    Burch, W.D.

    1982-01-01

    The future reprocessing developments focus on three major areas: (1) the retention of gaseous fission products to reduce off-site doses to very low values; (2) the initial steps of breakdown, shearing, and dissolution of breeder fuels; and (3) advanced facility and equipment concepts, which are expected to lead to a reliable, cost-effective, totally remotely operated and maintained plant. Work in the first area - removal of fission gases (the most important of which is 85 Kr) - is largely completed through tracer and bench-scale engineering equipment. Efforts are now mainly devoted to breeder fuels and advanced remote concepts. A facility, the Integrated Equipment Test Facility, which will be used to carry out much of this work, is nearing completion in Oak Ridge. In it a large, simulated, remote reprocessing cell will house a disassembly-shear machine for either breeder or LWR fuels, a rotary continuous dissolver, a solvent extraction cycle utilizing a new generation of centrifugal contactors, and related equipment

  12. Simulation and analysis of plutonium reprocessing plant data

    International Nuclear Information System (INIS)

    Burr, T.; Coulter, A.; Wangen, L.

    1996-01-01

    It will be difficult for large-throughput reprocessing plants to meet International Atomic Energy Agency (IAEA) detection goals for protracted diversion of plutonium by materials accounting alone. Therefore, the IAEA is considering supplementing traditional material balance analysis with analysis of solution monitoring data (frequent snapshots of such solution parameters as level, density, and temperature for all major process vessels). Analysis of solution monitoring data will enhance safeguards by improving anomaly detection and resolution, maintaining continuity of knowledge, and validating and improving measurement error models. However, there are costs associated with accessing and analyzing the data. To minimize these costs, analysis methods should be as complete as possible simple to implement, and require little human effort. As a step toward that goal, the authors have implemented simple analysis methods for use in an off-line situation. These methods use solution level to recognize major tank activities, such as tank-to-tank transfers and sampling. In this paper, the authors describe their application to realistic simulated data (the methods were developed by using both real and simulated data), and they present some quantifiable benefits of solution monitoring

  13. Annual report 1999; Rapport annuel 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This report presents the activities of the Cogema group, its reports on management and its financial situation for the year 1999: boards of directors, executive committee and steering committee, main consolidated data, year 1999 highlights, group activities (mining-chemistry, enrichment, reprocessing-recycling and associated transport operations, engineering, services to industry), organization chart of the consolidated Cogema group, financial statements, directory. (J.S.)

  14. Annual report 1999

    International Nuclear Information System (INIS)

    2002-01-01

    This report presents the activities of the Cogema group, its reports on management and its financial situation for the year 1999: boards of directors, executive committee and steering committee, main consolidated data, year 1999 highlights, group activities (mining-chemistry, enrichment, reprocessing-recycling and associated transport operations, engineering, services to industry), organization chart of the consolidated Cogema group, financial statements, directory. (J.S.)

  15. 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

  16. 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

  17. 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)

  18. Development of support system for maintenance and administration of reprocessing plant equipment

    International Nuclear Information System (INIS)

    Iwasaki, Syogo; Taniguchi, Takayuki; Shiraishi, Yoshihiko; Isaka, Kazuo

    1998-01-01

    Each year, maintenance work is carried out for about 10,000 pieces of equipment, including mechanical devices, electric equipment and instruments, at the Tokai Reprocessing Plant. Ninety percent of such maintenance work is preventive maintenance. In order to manage the information about the maintenance work, a computer support system was developed between 1985 and 1992. Twenty-seven thousand pieces of equipment and 180,000 maintenance histories have already been registered in the system. The system has been used for planning inspections and replacement of equipment as well as checking their maintenance histories. Actual usage of the system has shown that some auxiliary functions need to be added. The system will therefore be improved and extended. (author)

  19. Guideline for design and construction radiation monitoring equipments for Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Miyabe, Kenjiro; Ninomiya, Kazushige; Jin, Kazumi; Morifuji, Masayuki; Nemoto, Kazuhiko; Sato, Akira; Kawai, Keiichi

    1999-12-01

    Various kind of radiation monitoring equipment are used in radiation controlled area at each facility of Tokai reprocessing plant. These equipments have been designed and constructed based on the users requirements, and permitted by governmental regulation office. And, design has been carried out in consideration of the adoption of the new technology and our operational experience. Then, it has been used effectively for the radiation control of the facilities. This report summarizes the technical requirements that should be taken into consideration in the design and installation of radiation monitoring equipments. These requirements are fundamentally applicable when the equipments of the new facilities will be designed or the present instruments will be replaced. (author)

  20. Decommissioning and dismantling of the reprocessing plant Karlsruhe

    International Nuclear Information System (INIS)

    Eiben, K.; Fritz, P.

    1995-01-01

    Reprocessing activities were discontinued in late 1990. The facility was drained and rinsed, and 80 m3 of HLWC have since been stored in special tanks, awaiting vitrification. Decommissioning work is scheduled to proceed in six phases. The reprocessing areas of the facility will be prepared for release from radiological control and dismantled in the first phase. The remaining facilities can be deregulated, and storage tanks dismantled, only after termination of phase 1. The goal of the following phase is clearance from radiological control of all controlled areas, and the last phase is to cover dismantling of all buildings and restoration of a green field site. The overall costs of these activities are estimated to amount to DM 1.657 million. The article explains the contents of the first permits for decommissioning as well as the documents prepared for planning of work and licence application. (orig./HP) [de