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Sample records for cogema

  1. 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

  2. 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

  3. 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

  4. 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.)

  5. 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

  6. 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)

  7. 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

  8. 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.

  9. 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.).

  10. 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)

  11. 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.)

  12. 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.)

  13. 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

  14. 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.)

  15. 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.)

  16. 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

  17. 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.)

  18. 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

  19. 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

  20. 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)

  1. 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)

  2. 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)

  3. 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

  4. 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

  5. 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

  6. 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.)

  7. 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.)

  8. 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.)

  9. 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)

  10. 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)

  11. 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)

  12. 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

  13. Human and technical factors in the doses reduction and optimization at Cogema/Marcoule

    International Nuclear Information System (INIS)

    Bourgogne, J.L.

    1998-01-01

    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.)

  14. Atom medicine. The history of health at work at the Cea and at the Cogema

    International Nuclear Information System (INIS)

    Lefebvre, V.

    2005-01-01

    This work aims to inform any people interested in the origins and the development of the medical surveillance of workers exposed to ionizing radiations by relating the history and experience of medical services and biological and medical analysis laboratories of the Cea and Cogema. (N.C.)

  15. Uranium mining and milling by Cogema environmental impact compared to 1 mSv limit

    International Nuclear Information System (INIS)

    Bernhard, S.; Daroussin, J.L.; Pfiffelmann, J.P.

    1996-01-01

    CEA then COGEMA have been operating mines and mills in France since 1948. Total production nears 70000 t of U in the concentrate which were contained in some 85 millions tons of ores (pulp and heap leaching). Many sites are now undergoing remediation and impact on the environment has always been a great concern. (author)

  16. 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

  17. 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

  18. 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)

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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)

  4. 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

  5. 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.)

  6. 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.)

  7. 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)

  8. 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.

  9. 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.)

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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)

  15. COGEMA: Geological exploitation and supervision concerning the open pits of the Herault Division

    International Nuclear Information System (INIS)

    Delorme, D.

    1989-01-01

    Cogema mines since 1974 near Lodeve (Herault) the uranium deposits located in the eastern part of the Permian basin of Lodeve. These mining operations are carried out open cast and underground by the Herault Mining Division. The methods used for mining the deposit underground at Mas Lavayre in the most important uranium mine of Western Europe were previously described. The object of the present article is to describe the methods applied to mine the deposits by open cast working, for which it is essential in view of the complex geometry of the mineralizations to have a high-quality geological supervision to ensure a good selective recovery of the ore. 9 figs., 9 refs [fr

  16. 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)

  17. 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)

  18. Decree No. 81-300 of 31 March 1981 authorising the Atomic Energy Commission and COGEMA to intervene in the field of ores and fossile substances

    International Nuclear Information System (INIS)

    1981-01-01

    This Decree was made to enable COGEMA to diversify its activities in the mining sector. It was therefore necessary to amend both the Decree of 26 December 1975 authorizing the Atomic Energy Commission (CEA) to set up the COGEMA and the Decree of 29 September 1970 relating to the CEA, in view of the specific nature of the duties entrusted to this body by the latter Decree. (NEA) [fr

  19. 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)

  20. Analysis of the mortality among Cogema workers monitored for external radiation exposure

    International Nuclear Information System (INIS)

    Metz-Flamant, C.; Hitz, M.; Samson, E.; Rogel, A.; Telle-Lamberton, M.; Tirmarche, M.; Caer, S.; Quesne, B.

    2006-01-01

    The present study follows 9287 Cogema workers exposed to low level of ionizing radiation from the beginning of employment to the end of 1994. This paper presents analyses of the mortality of Cogema workers monitored for external radiation exposure and the relation between their mortality and their cumulative external radiation dose. Workers were followed up for an average of 13 years. The percentage of subjects lost to follow up was less than 1%. during the follow-up period, 441 deaths occurred. The mean cumulative dose among the whole cohort was 19.4 mSv. As expected, the mortality of the cohort was lower than that of the French national population. The healthy worker effect is often observed in other nuclear workers studies. Part of the healthy worker effect is explained by a proportion of unemployed persons in general population, with a higher mortality rate. All causes S.M.R. increased with calendar period and duration of employment. this increase was not significant for all cancers S.M.R. by duration of employment. This could illustrate the decrease of the initial selection at employment with time. A significant increase in risk was observed for all cancers excluding leukemia mortality with increase of radiation dose in the 15-country study. Significant excess of leukemia by cumulative radiation exposure was observed in the 3-country study and was borderline significant in the 15-country study and in the UK National register for radiation workers study. A positive trend, not statistically significant, by level of external doses was observed in our study for all cancers and leukemia excluding chronic lymphatic leukemia mortality, but the analyses lack of statistical power. A significant trend was observed only for non-Hodgkin lymphoma death, but considering the large number of statistic tests computed, this result must be carefully interpreted. A borderline significant trend was observed for lung cancer death, a significant increase risk of lung cancer death

  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, 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)

  2. Anticipation of the needs linked with new generation reactors: COGEMA Logistics casks developments

    Energy Technology Data Exchange (ETDEWEB)

    Issard, H.; Grygiel, J.M. [COGEMA LOGISTICS SA, 1 rue des Herons BP 302, Montigny-le-Bretonneux, 78054 Saint Quentin en Yvelines (France)

    2006-07-01

    assigning the level of performance of the cask to be used. To accompany the 'nuclear renaissance' and the related fuel design and fuel management evolution, it is crucial to anticipate the associated needs in terms of cask development notably for the spent fuel management. It is the reason why an ambitious R and D program has been set up at COGEMA Logistics. It aims at proposing innovative solutions oriented by the trends guiding this 'renaissance': the proposed systems have indeed to accommodate Spent Fuel Assemblies (SFAs) characterized by ever increasing burn-ups, fissile isotopes contents, and total inventory. Flexibility may potentially mean quick evacuation of UO{sub 2} or MOX spent fuel with high thermal power to be dealt with. As described in the present paper, these evolutions directly guide the R and D actions on thermal and structural analysis, criticality and containment. The approach shall also include predictable licensing processes in an ever-demanding regulatory environment. The paper has the following structure: I. Evolutionary casks for evolving needs; II COGEMA Logistics R and D on evolutionary packagings; 1- The objectives of COGEMA Logistics R and D on evolutionary packagings; 2- Which R and D actions are currently implemented to anticipate evolving needs?; 2-1 Building an R and D program; 2-2 High performance design solutions for subcriticality; 2-3 Solutions for thermal and structural management; 2-4 Solution for enhanced shielding design; 2-5 Solutions for double containment systems; 2-6 Solutions for shock absorbers; 3- Examples of packaging developments; III Conclusion. To summarize, COGEMA Logistics is actively involved in Research and Development to accompany the improvement brought by Areva in fuel design and management linked either to extensive programs of nuclear plant life extension or to new constructions, such as Areva's European Pressurized Reactor. These evolutions coupled with needs for ever higher flexibility

  3. Anticipation of the needs linked with new generation reactors: COGEMA Logistics casks developments

    International Nuclear Information System (INIS)

    Issard, H.; Grygiel, J.M.

    2006-01-01

    to be used. To accompany the 'nuclear renaissance' and the related fuel design and fuel management evolution, it is crucial to anticipate the associated needs in terms of cask development notably for the spent fuel management. It is the reason why an ambitious R and D program has been set up at COGEMA Logistics. It aims at proposing innovative solutions oriented by the trends guiding this 'renaissance': the proposed systems have indeed to accommodate Spent Fuel Assemblies (SFAs) characterized by ever increasing burn-ups, fissile isotopes contents, and total inventory. Flexibility may potentially mean quick evacuation of UO 2 or MOX spent fuel with high thermal power to be dealt with. As described in the present paper, these evolutions directly guide the R and D actions on thermal and structural analysis, criticality and containment. The approach shall also include predictable licensing processes in an ever-demanding regulatory environment. The paper has the following structure: I. Evolutionary casks for evolving needs; II COGEMA Logistics R and D on evolutionary packagings; 1- The objectives of COGEMA Logistics R and D on evolutionary packagings; 2- Which R and D actions are currently implemented to anticipate evolving needs?; 2-1 Building an R and D program; 2-2 High performance design solutions for subcriticality; 2-3 Solutions for thermal and structural management; 2-4 Solution for enhanced shielding design; 2-5 Solutions for double containment systems; 2-6 Solutions for shock absorbers; 3- Examples of packaging developments; III Conclusion. To summarize, COGEMA Logistics is actively involved in Research and Development to accompany the improvement brought by Areva in fuel design and management linked either to extensive programs of nuclear plant life extension or to new constructions, such as Areva's European Pressurized Reactor. These evolutions coupled with needs for ever higher flexibility in terms of spent fuel management clearly guide the packaging

  4. One year's experience by COGEMA logistics of application of the new modal regulations

    International Nuclear Information System (INIS)

    Malesys, P.

    2002-01-01

    International transport of radioactive materials is regulated by international and regional modal regulations that apply to all dangerous goods. The requirements for radioactive materials in the modal regulations are based on those of the 'Regulations for the Safe Transport of Radioactive Material' set forth by the International Atomic Energy Agency (IAEA). The last edition of the IAEA regulations was published in 1996 (TS-R-1 (ST-1, Revised)), then incorporated in the modal regulations, and finally implemented, with various transitional periods throughout 2001. As a final result, since 1 January 2002 it has been mandatory, for all modes, to perform transports in accordance with the 1996 edition of the IAEA transport regulations. In the mean time, all the international and regional regulations have also been reformatted, and each of them has now adopted the unified format of the United Nations 'Recommendations on the Transport of Dangerous Goods - Model Regulations', often referred to as the Orange Book. This paper presents the experience of COGEMA Logistics with the application of this new set of regulations to design of packages, transport operations, and administrative matters. Both the advantages provided by these new regulations and the difficulties which were (and are still being) met are presented. (author)

  5. 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)

  6. Evaluation of the long duration efficiency of the ECC storage facility of Cogema La Hague plant

    International Nuclear Information System (INIS)

    Baganz, C.; Bouland, P.; Breton, E.

    2004-01-01

    The ECC facility of Cogema La Hague has been designed in view of the storage of 24000 CSD-C type containers produced by the ACC facility. It comprises a reception and unloading unit, and a modular storage unit (alveoles). The safety of the facility is based on: a controlled ventilation (low pressurization rooms, controlled atmosphere, heat and toxic gases evacuation), a construction ensuring the static confinement, the sub-criticality and the radiological protection, and the possibility of natural ventilation of the alveoles (earthquake-dimensioned equipments). On the basis of these safety functions, the conformability of the facility with respect to long duration has been analyzed considering three aspects of the facility: the infrastructure, the waste packages and the ventilation system. In normal operation, a foreseeable service life of at least 100 years is established: simpleness and accessibility of ventilation systems, no significant corrosion of packages, durability of the reinforced concrete structure. The demonstration of a service life greater than 100 years would require the improvement of our knowledge about concretes in terms of experience feedback. The behaviour of the facility in terms of loss of technical mastery has been considered too. The scenario retained for this situation is the prolonged stoppage (several months or years) of the nuclear ventilation after a 100 years of disposal. After this period of time, both the thermal power and the hydrogen generation from waste packages will have significantly diminished, allowing a loss of technical mastery era of several years with no impact on concretes integrity. However, during long situations of non-controlled atmosphere, the corrosion behaviour of stainless steels is not predictable. (J.S.)

  7. 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

  8. 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

  9. Reliability of the spent fuel identification for flask loading procedure used by COGEMA for fuel transport to La Hague

    International Nuclear Information System (INIS)

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

    1991-01-01

    The Spent Fuel Identification for Flask Loading (SFIFL) procedure designed by COGEMA is analysed and its reliability calculated. The reliability of the procedure is defined as the probability of transporting only approved fuel elements for a given number of shipments. The procedure describes a non-coherent system. A non-coherent system is the one in which two successive failures could result in a success, from the system mission point of view. A technique that describes the system with the help of its maximal cuts (states) is used for calculations. A maximal cut contains more than one failure which can split into two cuts (sub-states). Cuts splitting will enable us to analyse, in a systematic way, non-coherent systems with independent basic components. (author)

  10. Reliability of the spent fuel identification for flask loading procedure used by COGEMA for fuel transport to La Hague

    International Nuclear Information System (INIS)

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

    1990-01-01

    The Spent Fuel Identification for Flask Loading, SFIFL, procedure designed by COGEMA is analysed and its reliability is calculated. The reliability of the procedure is defined as the probability of transporting only approved fuel elements for a given number of shipments. The procedure describes a non-coherent system. A non-coherent system is the one in which two successive failures could result in a success, from the system mission point of view. A technique that describes the system with the help of its maximal cuts (states), is used for calculations. A maximal cut contains more than one failure can split into two cuts, (sub-states). Cuts splitting will enable us to analyse, in a systematic way, non-coherent systems with independent basic components. (author)

  11. 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.)

  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. 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

  14. 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.

  15. AREVA in Gabon. Inquiry report on the situation of workers of the COMUF, Gabonese subsidy of the AREVA-COGEMA group

    International Nuclear Information System (INIS)

    2007-01-01

    After a recall of the development of uranium mining activities by the COMUF Company which is now a subsidy company of the AREVA-COGEMA group, and a presentation of the inquiry, this document reports the inquiry performed in Gabon about the medical issue (with notably inadequate security measures) and about the environmental issue related to the site rehabilitation. It also reports the analysis of questionnaires sent to ex-workers in Gabon, as well as of testimonies obtained from expatriates who are suffering from health problems. The report discusses the possibilities to take legal actions for different reasons: unintentional injuries and homicide, endangering the life of others, or inexcusable error. In conclusion the report outlines that the risk was known, that there was no information about it, and that people were deliberately maintained in ignorance

  16. Radioecological surveillance 2001-2003 of marine environment of the dismantling workings of the old pipe of releases in sea Cogema la Hague (Anse des Moulinets)

    International Nuclear Information System (INIS)

    2005-02-01

    In order to watch the environment of the construction site of dismantling of the former pipe of releases in sea of Cogema-La Hague, the special and permanent commission of Information near the establishment Cogema of La Hague (C.S.P.I.) asked the association for the radiation monitoring in the West (A.C.R.O.) to realize a specific campaign of measures, on the basis of a protocol accepted by the C.S.P.I.. During the three years of the building work, two significant increases of the concentration in 137 Cs in the marine flora with at most, 9.3 Bq/kg dry, are noticed so be it ten times the concentration that could be measured before the building work begins. We note a net improvement of the situation after the works. The 137 Cs tends finally to disappear. For the sedimentary masses and the sands of beaches, it is outlined no increase of the contamination in 137 Cs (during the works and in posteriori) which translates in a irrefutable way contributions of the construction site. Let us remind this subject that the level of contamination of sands of the Moulinets cove by the named radionuclides is the most important of the coasts of La Hague and that a such report supposes that local events are behind. In conclusion, the campaign of measures of the ambient gamma radiation realized in August, 2004, that is three months after works, consolidates the hypothesis that the works did not generate particular radiological situation susceptible to increase the external risk of irradiation in the Moulinets cove. (N.C.)

  17. Year 2003. GRNC's appreciation of the dose estimates presented in the annual environmental monitoring report of Cogema-La-Hague facility. Detailed reports; Annee 2003. Appreciation par le GRNC de l'estimation des doses presentee dans le rapport annuel de surveillance de l'environnement de COGEMA-LA-HAGUE. Rapports detailles

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-06-15

    The 'Groupe Radioecologie Nord Cotentin' (GRNC) has carried out a very thorough evaluation of the assessment of doses due to discharges from the Cap de la Hague nuclear site carried out by COGEMA, the site operators. The group has looked at all aspects of the assessment methods and data to ensure that they agree with the results presented in the 2003 annual environmental report of the operator. The computer tool, ACADIE, developed to assess the doses, has been used by the GRNC members to carry out their own calculations. This document comprises the detailed report of the GRNC and its synthesis. The detailed report includes: 1 - critical analysis of the 2003 source term, the data transmitted by Cogema (presentation of the July 6, 2005 meeting, status of atmospheric effluents, status of liquid effluents at sea, fuel data), the history of liquid and gaseous effluents between 1966 and 2003; 2 - detailed comparison between model and measurements; 3 - ACADIE users manual, doses calculated by the GRNC during its third mission (year 2003). (J.S.)

  18. The radiological impact of 50 years of uranium mining in France. The necessity of a site satisfying restructuring by Cogema-Areva

    International Nuclear Information System (INIS)

    2005-01-01

    In a first text, the author briefly describes the radioprotection risks related to uranium mining, gives an overview of the characteristics of extraction residues in uranium extraction factories. Then, after having presented the case of the Limousin region in France, he outlines the high level of contamination of the environment of the mining sites, recalls the extraction process and discusses the careless use of the extracted radioactive rocks and materials. He outlines the insufficient management and processing of liquid effluents, the risk associated with the dispersal of contaminated scrap metals and of radioactive ores. He also discusses air contamination due to dusts and radioactive gases. He comments the issue of long term storage of uranium mining residues. He outlines the responsibility of the Administration and comments the trial against Cogema which took place in 2005. He outlines how restructuring of all the concerned sites is a challenging issue for our future. A second text in English describes radiological hazards from uranium mining (uranium by-products, radiological situation before and during extraction, long term contamination after mines closure, problems posed by tailing disposal)

  19. TN trademark FLEX: a new generation of fluorocarbon o-rings developed by COGEMA logistics with enhanced characteristics at low temperature (-40 C)

    International Nuclear Information System (INIS)

    Issard, H.; Andre, R.

    2004-01-01

    Three main types of elastomers are used for the sealing of radioactive material transport casks with elastomeric gaskets: EPDM, fluorocarbons type Viton registered (standard designation: FKM) and silicon rubbers. Each rubber has specific characteristics in terms of temperature range, permeability, coefficient of expansion.. For the casks where high temperatures can be reached (200 C in continuous using), FKM gaskets are generally used. The problem is that this type of gasket does not guarantee the leaktightness at -40 C, which is a regulatory requirement. Two solutions are generally used: to specify a minimum heat load or a minimum ambient temperature. The direct consequence is that it is impossible to get B(U) approvals on the new concepts when FKM gaskets are used but only B(M) approvals, which generate significant additional justification costs (multiple submittals of Safety Analysis Reports, calculation of the minimum heat load or of the minimum ambient temperature..). Thus, it is important to develop gaskets with the same performance as FKM gaskets at high temperature but with enhanced performance at low temperature (and mainly, which guarantee the leaktightness at -40 C). COGEMA LOGISTICS has qualified a new generation of fluorocarbon O-rings (TN trademark FLEX gaskets) which can be used in continuous service on a -47 C/+200 C temperature range. TN trademark FLEX gaskets will be implemented on new casks designs

  20. Year 2004. GRNC's appreciation of the dose estimates presented in the annual environmental monitoring report of Cogema-La-Hague facility. Second GRNC viewpoint. Detailed report; Annee 2004. Appreciation par le GRNC de l'estimation des doses presentee dans le rapport annuel de surveillance de l'environnement de Cogema-La-Hague. Deuxieme avis du GRNC. Rapport detaille

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The 'Groupe Radioecologie Nord Cotentin' (GRNC) has carried out a very thorough evaluation of the assessment of doses due to discharges from the Cap de la Hague nuclear site carried out by COGEMA, the site operators. The group has looked at all aspects of the assessment methods and data to ensure that they agree with the results presented in the 2004 annual environmental report of the operator. The computer tool, ACADIE, developed to assess the doses, has been used by the GRNC members to carry out their own calculations. This document comprises the detailed report of the GRNC and its synthesis. The detailed report includes: 1 - critical analysis of the 2004 source term, the data transmitted by Cogema (status of atmospheric effluents, status of liquid effluents at sea, fuel data), the history of liquid and gaseous effluents between 1966 and 2004; 2 - detailed comparison between model and 2004 measurements; 3 - detail of the 2004 efficient dose calculations. (J.S.)

  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. Remarks on the Cogema-Areva project of storage of contaminated sludge and sediments on the Bellezane site (Haute-Vienne). Investigation performed by the CRIIRAD laboratory on its own funds

    International Nuclear Information System (INIS)

    2006-06-01

    As sediments of several lakes are contaminated by uranium mines which are located upstream, and which have been exploited in the past by the Cogema (now Areva NC), this company asked for an authorization to use an old pit in Bellezane to deposit clearing sludge from water processing plants and from the clearing of ponds. This document describes the different problems raised by this project. It outlines that the site is not waterproof and that its legal status is not correct. It also reports and comments the radiological contamination of waters and soils due to site effluents, the chemical contamination of waters, and the existence of solid radioactive wastes at the vicinity of this site

  3. 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 yield of the operation and its simplicity were the main reasons for this choice. Nowadays, our catalytic hydrogenation process is used in all the commercial reprocessing plants worldwide: THORP at Sellafield, UP3 and UP2 800 at La Hague, and RRP at Rokkasho-Mura. In this process, uranyl nitrate is reduced to uranous nitrate by hydrogen in presence of a platinum based catalyst. Most of the plants implement the reaction in the same kind of reactor: 'co-current, up-flow and fixed-bed reactor'. For UP2 800 at La Hague, started in 1994, a new kind of reactor allowing a higher capacity has been developed. In this reactor, the catalyst bed is not fixed but circulating (fluidized bed). The aim of the paper is to describe both reactor technology implemented in La Hague (fixed bed and fluidized bed), to show their performance in terms of capacity and yield and to compare their operating and maintenance principles. (authors)

  4. 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.)

  5. Use of polyurethane resins for sealing test boreholes at Cogema Vendee

    International Nuclear Information System (INIS)

    Tourscher, M.

    1989-01-01

    The mining division is briefly described. The main problem for mining development is an important flow rate of water at a pressure of 0 to 10 bars through exploratory boreholes. Use of polyurethane resin reacting with water was retained but taking account of flow rate and pressure a new method was developed using a polyamide sleeve, allowing reaction and expansion before dilution by flowing water. Cost is estimated at 4683 FF/borehole [fr

  6. Optimization of mining methods for steep vein uranium ore deposits of French COGEMA company

    International Nuclear Information System (INIS)

    Caleix, C.

    1985-01-01

    The Compagnie Generale des Matieres Nucleaires is currently exploiting several steep vein uranium deposits in France. The upper parts are exploited using the open-cast method, in the lower parts underground mining is used. The veins with a thickness of several meters fill faults caused by tectonic activity. With regard to the low strength of the rocks, wooden supports are used or fills. In the course of the past 25 years several mining methods have been tried of which overhand stoping was selected with an oblique ramp driven in the ore, this mainly for securing operating safety and the profitability of selective exploitation. In overburdens with a low bearing capacity the method of underhand benching in slices was used with a concrete fill and later underhand benching in slices with concrete reinforcing plates. Overhand stoping is being tried with fill and electric self-propelled machines left in the stope and mechanized driving of raises by full profile drilling. (B.S.)

  7. 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)

  8. Installation of Radiometric Sorting throughout the Cogema-Simo Mining Complex at Lodeve. [Uranium ores

    Energy Technology Data Exchange (ETDEWEB)

    Grenier, J.; Winter, J.M.; Deville, P.

    1986-06-01

    The ores of Lodeve present no physical characteristics which permit an elimination of the lowest grade fractions, with the exception of the radioactivity and the radium which accompanies the uranium. The mine therefore turned to radiometric pebble-by-pebble sorting on a machine model M 17 of Ore Sorters who have a monopoly of this type of equipment; this permits an operation over a size range from 25 to 160 mm. Sampling of the deposit investigation of pebble samples, construction of the sorting plant and commissioning are described.

  9. Development of the ''measurement and sorting'' device for bituminized waste drums at Cogema Marcoule

    International Nuclear Information System (INIS)

    Chabalier, B.; Artaud, J.L.; Perot, B.; Passard, C.; Romeyer Dherbey, J.; Raoux, A.; Misraki, J.

    2000-01-01

    This programme is included in the scope of a specific task to retrieve bituminized waste drums stored on the Marcoule site. The objective is to define a non-destructive nuclear measurement facility that makes it possible to: - sort the packages stored on the site according to the radiological acceptance criteria for the waste packages in the surface storage facility, - establish the β and α activities of the packages to be stored in the surface storage facility, - estimate the activity of the packages that will be stored in the ''Entreposage Intermediaire Polyvalent'' (multiple purpose intermediate storage) built on the Marcoule site. A measurement facility, with measurement times compatible with the industrial flow of retrieval of the waste drums was studied, developed and will be validated. It features gamma spectrometry measurements and neutron measurement devices, associated to an imaging device by photonic transmission and an expert system. Studies associated to the definition of this facility mainly concern: - the imaging station: it enables to know up to what height the packages are filled, the actual density of the matrix, and to detect lacks of homogeneity. These data are required for a correct analysis of the neutron or gamma measurements and to minimise uncertainties, - the interpretation of active neutron measurement signals: a simultaneous detection of the prompt and delayed neutrons makes it possible to differentiate the masses of U-235 and of Pu-239 present in the packages, - the reduction of the detection limits: to that end, an ''asti-Compton'' detector was defined providing a gain on the detection limits at low energies according to the type of GeHP semi-conductor detector. - the expert system which performs the interpretation and coupling of measured data with data coming from the waste production files in order to determine the activity of the β γ, pure β and α radionuclides at 300 years. The validation program that will be conducted on a real size prototype makes it possible to demonstrate the performances of the proposed methods and devices. The implementation of these methods or devices makes it possible to reduce the influence of dominant parameters in the calculation of the uncertainty associated to the establishment of the radiological activity contained in the packages of irradiating waste. (authors)

  10. Evaluation of carbon-14 (C14) levels of terrestrial and marine food products of the environment of the site of Cogema La Hague

    International Nuclear Information System (INIS)

    2006-04-01

    This evaluation has for object to inform about the levels in carbon 14 in the environment of the factories of La Hague. Two sectors were differentiated on one hand the terrestrial environment, and on the other hand the marine environment. The investigations concerned first and foremost food products stemming as the vegetable culture (vegetables) or individual breeding (milk, eggs) but also foodstuffs stemming from the local agriculture (cereal). In touch with the second sector, the marine environment, the sampling concerned the accessible products of the sea by all and those locally marketed (fishes, molluscs, shellfishes). The different results are presented in tables. (N.C.)

  11. The data acquisition system for the management of nuclear materials involved in the fabrication of MOX fuel at the Cogema plant in Cadarache

    International Nuclear Information System (INIS)

    Crousilles, M.; Beche, M.; Dalverny, G.

    2001-01-01

    This article presents the follow-up system of all the nuclear materials that are involved in the industrial process of MOX fuel fabrication. This system, called Concerto, allows the management of MOX fabrication but also of any nuclear material transfer and of the stockpile of nuclear materials with taking into account their own specificity such as the risk of criticality. Operators that intervene on the different steps of the fabrication process, supply Concerto with information so Concerto can be considered as a near real-time system providing and recording the localization, the composition, the weight, the container,... of any batch of nuclear materials. Concerto complies with the requirements of quality assurance but also of nuclear safety by forbidding any transfer whenever the maximal authorized quantity would be exceeded. (A.C.)

  12. Evaluation of carbon-14 (C{sup 14}) levels of terrestrial and marine food products of the environment of the site of Cogema La Hague; Evaluation des niveaux de carbone-14 ({sup 14}C) des denrees alimentaires terrestres et marines de l'environnement du site de COGEMA - La Hague

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-15

    This evaluation has for object to inform about the levels in carbon 14 in the environment of the factories of La Hague. Two sectors were differentiated on one hand the terrestrial environment, and on the other hand the marine environment. The investigations concerned first and foremost food products stemming as the vegetable culture (vegetables) or individual breeding (milk, eggs) but also foodstuffs stemming from the local agriculture (cereal). In touch with the second sector, the marine environment, the sampling concerned the accessible products of the sea by all and those locally marketed (fishes, molluscs, shellfishes). The different results are presented in tables. (N.C.)

  13. Evaluation of health risks related to the operation of the AREVA sites of the Tricastin platform: Georges Besse plants I and II, SOCATRI, COGEMA Pierrelatte and COMURHEX (first level approach) Assessment of health studies. Final report

    International Nuclear Information System (INIS)

    Mandin, C.

    2006-03-01

    This document reports the study of health risks related to the chemical toxicity of species related to the operation of several AREVA installations in Tricastin. A qualitative and quantitative inventory of the species released in the atmosphere and in waters is based on data supplied by the operator. A selection of health tracers has lead to a global investigation of nitrogen oxides, sulphur dioxide, fluorine, uranium, arsenic, hexavalent chromium, mercury and nickel. The hazard associated with each of these species has been characterized. Different exposure ways have been considered: inhalation, soil ingestion, by vegetable, fruit and crop ingestion, ingestion of meat, milk and eggs produced by local breeding, fish ingestion, and ingestion of water sampled from the Tricastin aquifer. Atmospheric concentrations, soil deposits, surface soil layer concentrations, and other concentrations (in meat, milk, eggs, crops, vegetables, fruits, and drinking water) have been either modelled or measured. Different exposure scenarios have been defined, and the different risks (carcinogen or not) have been assessed

  14. Functioning of the Cartogam portable gamma camera in a photon counting mode (this development is performed at CEA in the framework of the B01-05 common interest program between CEA and COGEMA

    International Nuclear Information System (INIS)

    Gal, O.; Dessus, B.; Laine, F.; Jean, F.; Leveque, C.

    2001-01-01

    The CARTOGAM portable gamma camera, which is particularly compact (15 Kg in mass, including the shield, 8 cm in diameter), has been developed for gamma imaging applications in nuclear facilities. The detector is composed of a CsI(Tl) scintillator, an image intensifier and a CCD matrix. The ordinary mode for image acquisition with such a detector is an integrating mode: signal accumulated in the CCD pixels is read at the end of the exposure time, or even periodically with a summation in a PC memory. The main sources of noise in that mode are the photo-cathode thermo-electronic emission and the CCD leaking pixels. We have developed an alternative acquisition mode based on a morphological processing of the elementary images at the video frequency (25 images/s). In that mode, gamma events are individually identified and the noise due to isolated thermo-electrons or white pixels is (almost) completely removed, thus leading to an important gain in camera sensitivity. We present here experimental results obtained in this photon counting mode concerning SNR, spatial resolution, saturation limit in dose rate, sensitivity and comparison with the integrating mode. We present also a short analysis of the problem of measuring the SNR in practice in such images. (author)

  15. Logistics of the research reactor fuel cycle: AREVA solutions

    International Nuclear Information System (INIS)

    Ohayon, David; Halle, Laurent; Naigeon, Philippe; Falgoux, Jean-Louis; Franck Obadia, Franck; Auziere, Philippe

    2005-01-01

    The AREVA Group Companies offer comprehensive solutions for the entire fuel cycle of Research Reactors comply with IAEA standards. CERCA and Cogema Logistics have developed a full partnership in the front end cycle. In the field of uranium CERCA and Cogema Logistics have the long term experience of the shipment from Russia, USA to the CERCA plant.. Since 1960, CERCA has manufactured over 300,000 fuel plates and 15,000 fuel elements of more than 70 designs. These fuel elements have been delivered to 40 research reactors in 20 countries. For the Back-End stage, Cogema and Cogema Logistics propose customised solutions and services for international shipments. Cogema Logistics has developed a new generation of packaging to meet the various needs and requirements of the Laboratories and Research Reactors all over the world, and complex regulatory framework. Comprehensive assistance dedicated, services, technical studies, packaging and transport systems are provided by AREVA for every step of research reactor fuel cycle. (author)

  16. Case law and administrative decisions

    International Nuclear Information System (INIS)

    Anon.

    2004-01-01

    Two points are related in case law: the judgement of the appeal court of Limoges regarding the dumping of radioactive waste by Cogema, and the judgement of the slovak constitutional court on Greenpeace claim. (N.C.)

  17. 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.)

  18. Lessons learned from decontaminating and decommissioning fuel cycle facilities in France

    International Nuclear Information System (INIS)

    Bordier, Jean-Claude; Dalcorso, J. P.; Nokhamzon, Jean-Guy

    2000-01-01

    This paper draws on 20 years of experience and lessons learned by COGEMA and the CEA during the decontamination and decommissioning (DandD) of its nuclear fuel cycle facilities. COGEMA and the CEA have developed a wealth of knowledge on issues such as assessing decommissioning alternatives, selecting appropriate technical procedures on the basis of thorough site characterization, and developing waste management and disposal procedures. (author)

  19. CRISTAL V1: Criticality package for burn up credit calculations

    International Nuclear Information System (INIS)

    Gomit, Jean-Michel; Cousinou, Patrick; Gantenbein, Francoise; Diop, Cheikh; Fernandez de Grado, Guy; Mijuin, Dominique; Grouiller, Jean-Paul; Marc, Andre; Toubon, Herve

    2003-01-01

    The first version of the CRISTAL package, created and validated as part of a joint project between IRSN, COGEMA and CEA, was delivered to users in November 1999. This fruitful cooperation between IRSN, COGEMA and CEA has been pursued until 2003 with the development and the validation of the package CRISTAL V1, whose main objectives are to improve the criticality safety studies including the Burn up Credit effect. (author)

  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. Annual report 2000

    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 2000: presentation of TOPCO, boards of directors, profile, main consolidated data, year 2000 highlights, group activities (mining-chemistry, enrichment, reprocessing-recycling, engineering, services, sustainable development, health and safety, quality policy, human resources, R and D, communication), organization chart of the consolidated Cogema group, financial statements, directory. (J.S.)

  2. 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.)

  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. Annual report 2000; Rapport annuel 2000

    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 2000: presentation of TOPCO, boards of directors, profile, main consolidated data, year 2000 highlights, group activities (mining-chemistry, enrichment, reprocessing-recycling, engineering, services, sustainable development, health and safety, quality policy, human resources, R and D, communication), organization chart of the consolidated Cogema group, financial statements, directory. (J.S.)

  5. 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.)

  6. 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.

  7. 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)

  8. Reshaping transport operations to overcome new challenges

    Energy Technology Data Exchange (ETDEWEB)

    Harari, F.; Blachet, L. [COGEMA Logistics, (AREVA Group) (France)

    2004-07-01

    After more than 30 years of Spent Fuel Nuclear Fuel (SFN) and High Level Waste (HLW) casks shipments to and from the COGEMA reprocessing factories in LA HAGUE, COGEMA LOGISTICS has demonstrated a unique outstanding performance in transportation for the benefit of its international customers and has integrated all feed-back from past successful operations. While maintaining the highest safety and security records, the last 5 years have been a major challenge to overcome the increase in transport throughputs, regulatory requirements, specific customer demands and new environmental approach (both COGEMA-La Hague and COGEMA LOGISTICS have been certified ISO14001 since 2003). Improvements in procedures, equipments, controls, inspection and organization have been undertaken. Additional important logistics means such as cranes, lifting devices, spreaders were put in operations in the dedicated workshop of our road and maritime facilities as well as in our rail terminals. Thus COGEMA LOGISTICS has developed and improved important logistics means in the Cherbourg area for the loading and unloading operations of heavy casks (i.e. whose weight is between 25 and 120 tons) among three modes of freight (road, railway or maritime transportation). In Valognes, which is currently the most important railway terminal in the world for the transfer of nuclear materials, about 1200 transfers of heavy casks were performed in 2003. New transport equipment and assets were integrated successfully to answer the new requirements for the best interest of our customers. This paper will provide information about equipments and management system developed to overcome these challenges.

  9. Reshaping transport operations to overcome new challenges

    International Nuclear Information System (INIS)

    Harari, F.; Blachet, L.

    2004-01-01

    After more than 30 years of Spent Fuel Nuclear Fuel (SFN) and High Level Waste (HLW) casks shipments to and from the COGEMA reprocessing factories in LA HAGUE, COGEMA LOGISTICS has demonstrated a unique outstanding performance in transportation for the benefit of its international customers and has integrated all feed-back from past successful operations. While maintaining the highest safety and security records, the last 5 years have been a major challenge to overcome the increase in transport throughputs, regulatory requirements, specific customer demands and new environmental approach (both COGEMA-La Hague and COGEMA LOGISTICS have been certified ISO14001 since 2003). Improvements in procedures, equipments, controls, inspection and organization have been undertaken. Additional important logistics means such as cranes, lifting devices, spreaders were put in operations in the dedicated workshop of our road and maritime facilities as well as in our rail terminals. Thus COGEMA LOGISTICS has developed and improved important logistics means in the Cherbourg area for the loading and unloading operations of heavy casks (i.e. whose weight is between 25 and 120 tons) among three modes of freight (road, railway or maritime transportation). In Valognes, which is currently the most important railway terminal in the world for the transfer of nuclear materials, about 1200 transfers of heavy casks were performed in 2003. New transport equipment and assets were integrated successfully to answer the new requirements for the best interest of our customers. This paper will provide information about equipments and management system developed to overcome these challenges

  10. 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

  11. 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)

  12. Waste treatment at the La Hague and Marcoule sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema`s plants.

  13. 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)

  14. 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.)

  15. The fuel of nuclear reactors

    International Nuclear Information System (INIS)

    1995-03-01

    This booklet is a presentation of the different steps of the preparation of nuclear fuels performed by Cogema. The documents starts with a presentation of the different French reactor types: graphite moderated reactors, PWRs using MOX fuel, fast breeder reactors and research reactors. The second part describes the fuel manufacturing process: conditioning of nuclear materials and fabrication of fuel assemblies. The third part lists the different companies involved in the French nuclear fuel industry while part 4 gives a short presentation of the two Cogema's fuel fabrication plants at Cadarache and Marcoule. Part 5 and 6 concern the quality assurance, the safety and reliability aspects of fuel elements and the R and D programs. The last part presents some aspects of the environmental and personnel protection performed by Cogema. (J.S.)

  16. 12 Flasktransport of vitrified High Level Waste (HLW)

    Energy Technology Data Exchange (ETDEWEB)

    Verdier, A.; Lancelot, J. [COGEMA Logistics (AREVA Group) (France); Gisbertz, A.; Graf, W. [GNS (Germany); Bartagnon, O. [COGEMA (AREVA Group) (France)

    2004-07-01

    The return of HLW to Germany has started in 1996 with the first attribution of 28 glass canisters to German utilities by COGEMA. After several transports comprising 1, 2 and 6 flasks per shipment German and French Authorities requested to transport 12 flasks in a single shipment. The first of these 12-flask-transports was performed with the type CASTOR {sup registered} HAW 20/28 CG flask in 2002 and the second followed in 2003. COGEMA LOGISTICS is responsible for the overall transport assigned by GNS (Gesellschaft fuer Nuklear-Service mbH) being itself entrusted by the German utilities with the return of reprocessing residues.

  17. 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.)

  18. 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.)

  19. Spent fuels transportation coming from Australia

    International Nuclear Information System (INIS)

    2002-01-01

    Maritime transportation of spent fuels from Australia to France fits into the contract between COGEMA and ANSTO, signed in 1999. This document proposes nine information cards in this domain: HIFAR a key tool of the nuclear, scientific and technological australian program; a presentation of the ANSTO Australian Nuclear Science and Technology Organization; the HIFAR spent fuel management problem; the COGEMA expertise in favor of the research reactor spent fuel; the spent fuel reprocessing at La Hague; the transports management; the transport safety (2 cards); the regulatory framework of the transports. (A.L.B.)

  20. Spent fuels transportation coming from Australia; Transport de combustible use en provenance d'Australie

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    Maritime transportation of spent fuels from Australia to France fits into the contract between COGEMA and ANSTO, signed in 1999. This document proposes nine information cards in this domain: HIFAR a key tool of the nuclear, scientific and technological australian program; a presentation of the ANSTO Australian Nuclear Science and Technology Organization; the HIFAR spent fuel management problem; the COGEMA expertise in favor of the research reactor spent fuel; the spent fuel reprocessing at La Hague; the transports management; the transport safety (2 cards); the regulatory framework of the transports. (A.L.B.)

  1. 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)

  2. The reorganization of the nuclear sector in France

    International Nuclear Information System (INIS)

    2001-05-01

    In November 2000, the French ministry of economy, finances and industry presented a project of reorganization of the overall French nuclear sector which aims at grouping together the activities of CEA-Industrie, Cogema and Framatome in a single huge industrial group. This group will comprise two main poles, a purely nuclear one around Cogema and Framatome, and a pole devoted to new technologies with the connector activities of Framatome and the shares of CEA-Industrie in STMicroelectronics. This new group should make a funded turnover of 10 billions of euros with a net result (share of the group) of 500 millions of euros. It will employ 45000 people. (J.S.)

  3. Design of the MOX fuel fabrication facility

    International Nuclear Information System (INIS)

    Johnson, J.V.; Brabazon, E.J.

    2001-01-01

    A consortium of Duke Engineering and Services, Inc., COGEMA, Inc. and Stone and Webster (DCS) are designing a mixed oxide fuel fabrication facility (MFFF) for the U.S. Department of Energy (DOE) to convert surplus plutonium to mixed oxide (MOX) fuel to be irradiated in commercial nuclear power plants based on the proven European technology of COGEMA and BELGONUCLEAIRE. This paper describes the MFFF processes, and how the proven MOX fuel fabrication technology is being adapted as required to comply with U.S. requirements. (author)

  4. Design of the MOX fuel fabrication facility

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, J.V. [MFFF Technical Manager, U.S. dept. of Energy, Washington, DC (United States); Brabazon, E.J. [MFFF Engineering Manager, Duke Cogema Stone and Webster, Charlotte, NC (United States)

    2001-07-01

    A consortium of Duke Engineering and Services, Inc., COGEMA, Inc. and Stone and Webster (DCS) are designing a mixed oxide fuel fabrication facility (MFFF) for the U.S. Department of Energy (DOE) to convert surplus plutonium to mixed oxide (MOX) fuel to be irradiated in commercial nuclear power plants based on the proven European technology of COGEMA and BELGONUCLEAIRE. This paper describes the MFFF processes, and how the proven MOX fuel fabrication technology is being adapted as required to comply with U.S. requirements. (author)

  5. NHC's contribution to cleanup of the Hanford Site

    International Nuclear Information System (INIS)

    Chauve, H.D.

    1998-01-01

    The one billion dollars per year Project Hanford Management Contract (PHMC), managed by Fluor Daniel Hanford, calls for cleanup of the Hanford Site for the Department of Energy. Project Hanford comprises four major subprojects, each managed by a different major contractor. Numatec Hanford Corporation (NHC) is a fifth major subcontractor which provides energy and technology to each of the Hanford projects. NHC draws on the experience and capabilities of its parent companies, COGEMA and SGN, and relies on local support from its sister Company in Richland, COGEMA Engineering Corporation, to bring the best commercial practices and new technology to the Project

  6. 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)

  7. French uranium mining sites remediation

    International Nuclear Information System (INIS)

    Roche, M.

    2002-01-01

    Following a presentation of the COGEMA's general policy for the remediation of uranium mining sites and the regulatory requirements, the current phases of site remediation operations are described. Specific operations for underground mines, open pits, milling facilities and confining the milled residues to meet long term public health concerns are detailed and discussed in relation to the communication strategies to show and explain the actions of COGEMA. A brief review of the current remediation situation at the various French facilities is finally presented. (author)

  8. 12 Flasktransport of vitrified High Level Waste (HLW)

    International Nuclear Information System (INIS)

    Verdier, A.; Lancelot, J.; Gisbertz, A.; Graf, W.; Bartagnon, O.

    2004-01-01

    The return of HLW to Germany has started in 1996 with the first attribution of 28 glass canisters to German utilities by COGEMA. After several transports comprising 1, 2 and 6 flasks per shipment German and French Authorities requested to transport 12 flasks in a single shipment. The first of these 12-flask-transports was performed with the type CASTOR registered HAW 20/28 CG flask in 2002 and the second followed in 2003. COGEMA LOGISTICS is responsible for the overall transport assigned by GNS (Gesellschaft fuer Nuklear-Service mbH) being itself entrusted by the German utilities with the return of reprocessing residues

  9. Development of a new glove for glove boxes with high level performances

    International Nuclear Information System (INIS)

    Jerome Blancher; Jean-Marc Poirier

    2006-01-01

    This paper describes the results of a joint technological program of COGEMA and MAPA to develop a new generation of glove for glove boxes. The mechanical strength of this glove is twice as high as the best characteristics of gloves available on the market. This new generation of product has both a higher level of performance and better ergonomics. (authors)

  10. 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

  11. Dismantling of transuranic contaminated facilities

    International Nuclear Information System (INIS)

    Roux, P.

    1985-01-01

    The dismantling of transuranic contaminated facilities raises specific problems. A large part of these problems relates to the management of the waste resulting from dismantling. From the experience gained in the different centers CEA and COGEMA it appears that there are industrial solutions in the group CEA and that an engineering company such as SGN can export them [fr

  12. The French approach for management of depleted uranium a constantly improved technology

    International Nuclear Information System (INIS)

    Hartmann, D.; Le Motais, B.; Duperret, B.

    2001-01-01

    COGEMA provides uranium enrichment services to the nuclear industry worldwide. To meet general French safety requirements related to environmental protection issues, COGEMA has developed, as an extension of the enrichment operation, a facility to convert DUF 6 into a stable, fluorine-free compound. After 5 years demonstration of the process on a pilot plant, COGEMA placed a facility in industrial operation in 1984 to convert DUF 6 into stable oxide U 3 O 8 ; a second facility was commissioned in 1993, doubling the capacity. Since the beginning of its industrial de-fluorination operations, COGEMA has ever been concerned to make its technology as reliable and as cost effective as possible. Accordingly, an improvement work has been constantly under way which already benefited to the construction of the second facility, completed in 1993. This paper will give an overview of the improvement work performed over the years, relating not only to the technology (optimizing the de-fluorination output, reducing the corrosion inside the kilns, improving the uranium oxide powder compaction factor,...), but also to the process itself (hydrodynamic modeling of the process reactions inside the kiln) and maintenance issues (systematic monitoring of filters plugging, recycling of cartridge filters,...). (authors)

  13. Practical threshold limit values in a conversion plant

    International Nuclear Information System (INIS)

    Faron, R.

    1996-01-01

    Comurhex in a subsidiary of the Cogema group, and its business is the conversion to hexafluoride of the uranium contained in a variety of mining concentrates of differing origins. This report gives an example of the evaluation of the health aspects of a conversion plant. (author). 11 figs

  14. 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

  15. 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)

  16. The Assystem firm turns to chemistry and pharmacy

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    Controlling at 38% by Cogema and at 30% by the 'Dominique Louis' holding company, the Assystem firm makes nowadays use of its abilities for the chemistry and pharmacy sectors. The rehabilitation of the hazard studies in the chemical industry is more than never a topical question. (O.M.)

  17. 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.)

  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. Order of 24 July 1992 on the licensing of liquid radioactive effluent releases from the large nuclear installation called Atalante at the nuclear research centre in the Rhone valley on the Marcoule nuclear site

    International Nuclear Information System (INIS)

    1992-01-01

    This Order fixes the annual authorized limits and procedures for the transfer from Atalante to the Cogema establishment also at Marcoule of the low-level liquid effluents for treatment. It also specifies the measures for their control and surveillance. (NEA)

  20. The manufacture of plutonium fuels for light water reactors

    International Nuclear Information System (INIS)

    Lebastard, G.

    1985-01-01

    This paper describes the agreement concluded between COGEMA and BELGONUCLEAIRE, reflected in the creation of the COMMOX group which has been made reponsible for promoting and marketing plutonium fuel rods for light water reactors. One then analyses the main aspects of manufacturing this type of fuel and the resources deployed. Finally one indicates the sales prospects scheduled to meet requirements (MELOX plant) [fr

  1. Toward full MOX core design

    International Nuclear Information System (INIS)

    Rouviere, G.; Guillet, J.L.; Bruna, G.B.; Pelet, J.

    1999-01-01

    This paper presents a selection of the main preliminary results of a study program sponsored by COGEMA and currently carried out by FRAMATOME. The objective of this study is to investigate the feasibility of full MOX core loading in a French 1300 MWe PWR, a recent and widespread standard nuclear power plant. The investigation includes core nuclear design, thermal hydraulic and systems aspects. (authors)

  2. The French approach for management of depleted uranium a constantly improved technology

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann, D; Le Motais, B; Duperret, B [Cogema, 78 - Velizy Villacoublay (France)

    2001-07-01

    COGEMA provides uranium enrichment services to the nuclear industry worldwide. To meet general French safety requirements related to environmental protection issues, COGEMA has developed, as an extension of the enrichment operation, a facility to convert DUF{sub 6} into a stable, fluorine-free compound. After 5 years demonstration of the process on a pilot plant, COGEMA placed a facility in industrial operation in 1984 to convert DUF{sub 6} into stable oxide U{sub 3}O{sub 8}; a second facility was commissioned in 1993, doubling the capacity. Since the beginning of its industrial de-fluorination operations, COGEMA has ever been concerned to make its technology as reliable and as cost effective as possible. Accordingly, an improvement work has been constantly under way which already benefited to the construction of the second facility, completed in 1993. This paper will give an overview of the improvement work performed over the years, relating not only to the technology (optimizing the de-fluorination output, reducing the corrosion inside the kilns, improving the uranium oxide powder compaction factor,...), but also to the process itself (hydrodynamic modeling of the process reactions inside the kiln) and maintenance issues (systematic monitoring of filters plugging, recycling of cartridge filters,...). (authors)

  3. Wigner effect in graphite stack: G2 and G3 reactors

    International Nuclear Information System (INIS)

    Artozoul, M.; L'Homme, M.

    1982-11-01

    This text describes work carried out between 1978 and 1980 by a COGEMA/CEA team responsible for a report on the feasibility, effectiveness and possible hazards likely to be encountered in the nuclear annealing of G2 and in changing the operating conditions of G3 [fr

  4. Industrial organization. The government draws a new french nuclear landscape

    International Nuclear Information System (INIS)

    Foucher, N.

    2000-01-01

    This paper presents and explains the new nuclear industry. In order to rationalize Cogema and Framatome are going to be grouped in an holding called Topco with a nuclear pole and an electronic and new technologies pole. Framatome will be split in two parts and its connector technology subsidiary will be introduced on Change. (A.L.B.)

  5. Development of a new glove for glove boxes with high level performances

    Energy Technology Data Exchange (ETDEWEB)

    Jerome Blancher [AREVA/COGEMA Recycling Business Unit, BP 94176 - 30204 Bagnols-sur-Ceze Cedex (France); Jean-Marc Poirier [MAPA SPONTEX, BP 190 - 92205 Neuilly sur Seine Cedex (France)

    2006-07-01

    This paper describes the results of a joint technological program of COGEMA and MAPA to develop a new generation of glove for glove boxes. The mechanical strength of this glove is twice as high as the best characteristics of gloves available on the market. This new generation of product has both a higher level of performance and better ergonomics. (authors)

  6. La Hague Continuous Improvement Program: Enhancement of the Vitrification Throughput

    International Nuclear Information System (INIS)

    Petitjean, V.; De Vera, R.; Hollebecque, J.F.; Tronche, E.; Flament, T.; Pereira Mendes, F.; Prod'homme, A.

    2006-01-01

    The vitrification of high-level liquid waste produced from nuclear fuel reprocessing has been carried out industrially for over 25 years by AREVA/COGEMA, with two main objectives: containment of the long lived fission products and reduction of the final volume of waste. At the 'La Hague' plant, in the 'R7' and 'T7' facilities, vitrified waste is obtained by first evaporating and calcining the nitric acid feed solution-containing fission products in calciners. The product-named calcinate- is then fed together with glass frit into induction-heated metallic melters to produce the so-called R7/T7 glass, well known for its excellent containment properties. Both facilities are equipped with three processing lines. In the near future the increase of the fuel burn-up will influence the amount of fission product solutions to be processed at R7/T7. As a consequence, in order to prepare these changes, it is necessary to feed the calciner at higher flow-rates. Consistent and medium-term R and D programs led by CEA (French Atomic Energy Commission, the AREVA/COGEMA's R and D and R and T provider), AREVA/COGEMA (Industrial Operator) and AREVA/SGN (AREVA/COGEMA's Engineering), and associated to the industrial feed back of AREVA/COGEMA operations, have allowed continuous improvement of the process since 1998: - The efficiency and limitation of the equipment have been studied and solutions for technological improvements have been proposed whenever necessary, - The increase of the feeding flow-rate has been implemented on the improved CEA test rig (so called PEV, Evolutional Prototype of Vitrification) and adapted by AREVA/SGN for the La Hague plant using their modeling studies; the results obtained during this test confirmed the technological and industrial feasibility of the improvements achieved, - After all necessary improved equipments have been implemented in R7/T7 facilities, and a specific campaign has been performed on the R7 facility by AREVA/COGEMA. The flow-rate to the

  7. From Russian weapons grade plutonium to MOX fuel

    International Nuclear Information System (INIS)

    Braehler, G.; Kudriavtsev, E.G.; Seyve, C.

    1997-01-01

    The April 1996, G7 Moscow Summit on nuclear matters provided a political framework for one of the most current significant challenges: ensuring a consistent answer to the weapons grade fissile material disposition issue resulting from the disarmament effort engaged by both the USA and Russia. International technical assessments have showed that the transformation of Weapons grade Plutonium in MOX fuel is a very efficient, safe, non proliferant and economically effective solution. In this regard, COGEMA and SIEMENS, have set up a consistent technical program properly addressing incineration of weapons grade plutonium in MOX fuels. The leading point of this program would be the construction of a Weapons grade Plutonium dedicated MOX fabrication plant in Russia. Such a plant would be based on the COGEMA-SIEMENS industrial capabilities and experience. This facility would be operated by MINATOM which is the partner for COGEMA-SIEMENS. MINATOM is in charge of coordination of the activity of the Russian research and construction institutes. The project take in account international standards for non-proliferation, safety and waste management. France and Germany officials reasserted this position during their last bilateral summits held in Fribourg in February and in Dijon in June 1996. MINATOM and the whole Russian nuclear community have already expressed their interest to cooperate with COGEMA-SIEMENS in the MOX field. This follows governmental-level agreements signed in 1992 by French, German and Russian officials. For years, Russia has been dealing with research and development on MOX fabrication and utilization. So, the COGEMA-SIEMENS MOX proposal gives a realistic answer to the management of weapons grade plutonium with regard to the technical, industrial, cost and schedule factors. (author)

  8. Needs of anticipation for transport operations

    International Nuclear Information System (INIS)

    Galtier, J.

    2005-01-01

    COGEMA LOGISTICS (formerly Transnucleaire) has designed and manufactured several thousands of casks, and owns fleet of more than 4000 casks. Benefiting from more than 40 years of experience in cask shipment COGEMA LOGISTICS has demonstrated an outstanding performance in transportation and has integrated all feed back from past successful operations in current ones. Early anticipation of needs, i.e. at preliminary design step, is of major importance from a technical point of view (capacity, interface, handling means, licensing), and also in terms of political and public acceptance issues from the design step. This paper will highlight for each step required for the implementation of an optimal transport and storage system: Decision to proceed (including political aspects)-Design of casks to be used (including operational interface)-Licensing process-Manufacturing process-Transport plan, Public Acceptance-Loading Operations-Transport-Maintenance operations. (authors)

  9. Uranium industry update

    International Nuclear Information System (INIS)

    Poissonnet, M.

    1994-01-01

    Canada is the world's largest producer of uranium. With stockpiles becoming depleted, new sources of production will soon be needed. Production in Ontario was expected to cease in 1996, leaving decommissioning as the main activity there. Present production in Canada is almost entirely from the Athabasca basin in Saskatchewan, and mainly from three mines, Key Lake and Rabbit Lake (both owned by Cameco and Uranerz), and Cluff Lake (owned by Cogema). Following hearings in 1993, extensions to Cluff Lake and Rabbit Lake, and a new project at McClean Lake (by Minatco) received environmental approval, while the Midwest project as presented by Denison was rejected, but Cogema was revising it (at the time of the conference). An environmental impact statement for Cigar Lake was due to be submitted to the Assessment panel in October 1994. The author regrets that discussion of 'natural analogues' has created confusion between uranium mining and nuclear waste disposal in the public mind. 2 ills

  10. 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.)

  11. Waste treatment at the La Hague and Marcoule sites

    International Nuclear Information System (INIS)

    1995-04-01

    In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema's plants

  12. 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.

  13. Technical ability of new MTR high-density fuel alloys regarding the whole fuel cycle

    International Nuclear Information System (INIS)

    Durand, J.P.; Maugard, B.; Gay, A.

    1998-01-01

    The development of new fuel alloys could provide a good opportunity to improve drastically the fuel cycle on the neutronic performances and the reprocessing point of view. Nevertheless, those parameters can only be considered if the fuel manufacture feasibility has been previously demonstrated. As a matter of fact, a MTR work group involving French partners (CEA, CERCA, COGEMA) has been set up in order to evaluate the technical ability of new fuels considering the whole fuel cycle. In this paper CERCA is presenting the preliminary results of UMo and UNbZr fuel plate manufacture, CEA is comparing to U 3 Si 2 the neutronic performances of fuels such as UMo, UN, UNbZr, while COGEMA is dealing with the reprocessing feasibility. (author)

  14. Treatment of plutonium contaminated ashes by electrogenerated Ag(II): a new, simple and efficient process

    International Nuclear Information System (INIS)

    Madic, C.; Saulze, J.L.; Bourges, J.; Lecomte, M.; Koehly, G.

    1990-01-01

    Incineration is a very attractive technique for managing plutonium contaminated solid wastes, allowing for large volume and mass reduction factors. After waste incineration, the plutonium is concentrated in the ashes and an efficient method must be designed for its recovery. To achieve this goal, a process based on the dissolution of plutonium in nitric solution under the agressive action of electrogenerated Ag(II) was developed. This process is very simple, requiring very few steps. Plutonium recovery yields up to 98% can be obtained and, in addition, the plutonium bearing solutions generated by the treatment can be processed by the PUREX technique for plutonium recovery. This process constitutes the basis for the development of industrial facilities: 1) a pilot facility is being built in MARCOULE (COGEMA, UP1 plant), to treat active ash in 1990; 2) an industrial facility will be built in the MELOX plant under construction at MARCOULE (COGEMA plant)

  15. Studies on uranium ore processing

    International Nuclear Information System (INIS)

    Kim, C.H.; Park, S.W.; Lim, J.K.; Chung, M.K.

    1981-01-01

    Chemical and chemical engineering techniques of the uranium ore processing established by France COGEMA (Compagnie Generale des Matieres Nucleaires) have been comprehensively reviewed in preparation for successful test operation of the pilot plant to be completed by the end of 1981. It was found that the amount of sulfuric acid (75 Kg/t, ore) and sodium chlorate (2.5 Kg/t, ore) recommended by COGEMA should be increased up to 100 Kg/t, ore and 10 Kg/t, ore respectively to obtain satisfactory leach of uranium for some ore samples produced at the different pits of Goesan uranium mine. Conditions of the other processes such as solvent extraction, stripping, and precipitation of yellow cake were generally agreed with the results of intensive studies done by this laboratory

  16. The Canadian Nuclear Safety Commission regulatory process for decommissioning a uranium mining facility

    International Nuclear Information System (INIS)

    Scissons, K.; Schryer, D.M.; Goulden, W.; Natomagan, C.

    2002-01-01

    The Canadian Nuclear Safety Commission (CNSC) regulates uranium mining in Canada. The CNSC regulatory process requires that a licence applicant plan for and commit to future decommissioning before irrevocable decisions are made, and throughout the life of a uranium mine. These requirements include conceptual decommissioning plans and the provision of financial assurances to ensure the availability of funds for decommissioning activities. When an application for decommissioning is submitted to the CNSC, an environmental assessment is required prior to initiating the licensing process. A case study is presented for COGEMA Resources Inc. (COGEMA), who is entering the decommissioning phase with the CNSC for the Cluff Lake uranium mine. As part of the licensing process, CNSC multidisciplinary staff assesses the decommissioning plan, associated costs, and the environmental assessment. When the CNSC is satisfied that all of its requirements are met, a decommissioning licence may be issued. (author)

  17. Inventory of chemical releases of nuclear installations in the North-Cotentin; Inventaire des rejets chimiques des installations nucleaires du Nord-Cotentin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-15

    The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

  18. TNTM85 and TNTM81 transports / storage flasks: An optimized solution for vitrified residues

    International Nuclear Information System (INIS)

    Sicard, D.; Verdier, A.; Dyck, P.

    2006-01-01

    By analyzing the evolution of burnup of spent fuel to be reprocessed, the high activity vitrified residues would not be transported in the existing flask designs. Therefore COGEMA LOGISTICS decided in the late nineties to develop a design with optimized capacity able to store and transport the most active and hottest canisters. The TN TM 85 flask shall permit in the near future in Germany the storage and the transport of the highest vitrified residues defining a thermal power of 56 kW. The challenge for the TN TM 85 flask design was that the geometry entry data were very restrictive and were combined with a fairly wide range set by COGEMA Specification 300AQ16 relative to vitrified residue canister. In addition, the cask had to fit as much as possible in the existing procedures for the TN TM 28 cask and TS 28 V cask, all along the logistics chain of loading, unloading, transport and maintenance. (authors)

  19. BWR spent fuel transport and storage system for KKL: TN trademark 52L, TN trademark 97L, TN trademark 24 BHL

    International Nuclear Information System (INIS)

    Sicard, D.; Verdier, A.; Monsigny, P.A.

    2004-01-01

    The LEIBSTADT (KKL) nuclear power plant in Switzerland has opted to ship spent fuel to a central facility called ZWILAG for interim storage. In the mid-nineties, COGEMA LOGISTICS was contracted by KKL for the supply of the TN trademark a52L and TN trademark 97L transport and storage casks for BWR fuel types. In 2003, KKL also ordered from COGEMA LOGISTICS the supply of six TNae24 BHL transport and storage casks. This paper shows how all the three cask designs have responded to the KKL needs to ship and store BWR spent fuel. In addition, it highlights the already significant operational feedback of the TN trademark 52L and TN trademark 97L casks by the KKL and ZWILAG operators

  20. Inventory of chemical releases of nuclear installations in the North-Cotentin

    International Nuclear Information System (INIS)

    2002-05-01

    The nuclear installations concerned by this study are Cogema La Hague, the Flamanville nuclear power plant, the Manche plant and the National Navy of Cherbourg.The objective followed by the ' source term ' work group has consisted in counting and examining the whole of existing measures relative to the releases of chemical substances in the liquid and gaseous effluents. Then because of the lack of measures for the operation first years of installations, the work group has estimated the order of magnitude of these chemical releases (essentially for Cogema La Hague). This report presents a review of the literature looking at the background levels of chemicals in different environmental compartments: air, soil, plants and animals products. these values have been summarized here to be available for comparisons with concentrations input by the North Cotentin nuclear installations, calculated by the G.R.N.C. (radioecology group of Nord Cotentin)

  1. Spent fuel transport and storage system for NOK: The TN52L, TN97L, TN24 BHL and TN24 GB casks

    International Nuclear Information System (INIS)

    Wattez, L.; Verdier, A.; Monsigny, P.-A.

    2007-01-01

    NOK nuclear power plants in Switzerland, LEIBSTADT (KKL) BWR nuclear power plant and BEZNAU (KKB) PWR nuclear power plant have opted to ship spent fuel to a central facility called ZWILAG for interim storage. In the mid-nineties, COGEMA LOGISTICS was contracted by KKL for the supply of the TN52L and TN97L transport and storage casks for BWR fuel types. In 2003, KKL also ordered from COGEMA LOGISTICS the supply of six TN24 BHL transport and storage casks. This paper shows how all the three cask designs have responded to the KKL needs to ship and store BWR spent fuel. In addition, it highlights the already significant operational feedback of the TN52L and TN97L casks by the KKL and ZWILAG operators. In 2004, NOK also ordered three TN24 GB transport and storage casks for PWR fuel types. These casks are presently being manufactured. (author)

  2. Transportation and disposal of low-and medium level waste using fiber reinforced concrete overpacks

    International Nuclear Information System (INIS)

    Pech, R.; Verdier, A.

    1993-01-01

    A multiple-year research effort by Cogema culminated in the development of a new process to immobilize nuclear waste in concrete overpacks reinforced with metal fibers. The fiber concrete overpacks satisfy all French safety requirements relating to waste immobilization and disposal, and have been certified by Andra, the national radioactive waste management agency. This presentation will cover the use of the fiber-reinforced concrete overpack for disposal and transportation, and will discuss their fabrication. (J.P.N.)

  3. Back-end of the research reactor fuel cycle

    International Nuclear Information System (INIS)

    Gruber, Gehard J.

    1996-01-01

    This paper outlines the status of topics and issues related to: (1) Research Reactor Spent Nuclear Fuel Return to the U.S., including policy, shipments and ports of entry, management sites, fees, storage technologies, contracts, actual shipment, and legal process, (2) UKAEA: MTR Spent Nuclear Fuel Reprocessing, (3) COGEMA: MTR Spent Nuclear Fuel Reprocessing, and (4) Intermediate Storage + Direct Disposal for Research Reactors. (author)

  4. French and International experience on the dialogue around industrial sites; Experience francaise et internationales sur la concertation autour des sites industriels

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, Th [Centre d' Etude sur l' Evaluation de la Protection dans le Domaine Nucleaire, CEPN, 92 - Fontenay aux Roses (France); Heriard Dubreuil, G; Gadbois, S [Mutadis, 94 - Vitry (France); Oudiz, A [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Remond Gouilloud, M [Paris-6 Univ. Sorbonne, 75 (France)

    2002-12-15

    This report presents the results of a research work about 'the stakes of the dialogue around the follow up of nuclear and non nuclear industrial installations'. It used the experience of the North Cotentin radioecology group where expertise has been implemented in order to evaluate the impact on health of the releases of the Cogema La Hague plant. This report is the fruit of an interdisciplinary group ( experts of activities with risks, radiation protection, regulation in environment). (N.C.)

  5. Recent developments: Industry briefs

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    Recent nuclear industry briefs are presented. These briefs include: Swiss voters reject phaseout; EdF confirms order for Civaux 1; NDP surprise victor in Ontario; Czechoslovakia joins Foratom; Poland abandons Zarnowiec; Cogema's UP3 facility operationa; Wismut to clsoe mining operations; court rules in favor of US government in Yucca Mountain waste site; Italian government ratifies ENEL reactor shutdowns; and Seabrook enters commercial operation

  6. 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

  7. 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

  8. Application of data-processing to the technical and economical management of the plants of Simo

    International Nuclear Information System (INIS)

    Chastagner, F.

    1988-01-01

    The firm Simo is entrusted with the processing of the uranium ores extracted from the mines of Cogema in France, in its three plants. The paper describes the conception and the functioning of the information system. Among the advantages contributed by the system, the coherence between the technical follow-up and the economical follow-up constitutes one of the principal progressive features [fr

  9. Interim dry storage system technologies and innovations VARNA 2002

    International Nuclear Information System (INIS)

    Chollet, P.; Guenon, Y.

    2002-01-01

    The main concepts of the TN24 Family and NUHOMS System are explained in the paper. It is discussed how the NPPs specific requirements and economics trends contributes to the growing families of interim dry storage systems delivered under COGEMA LOGICTICS license. It is concluded that modular solutions are currently dominating because they are derived from main concepts evolved over time, benefited from both the transport aspects with internationally recognised stringent regulations, and various specific ISFSI requirements and economic trends

  10. The CEA in mutation redefines its strategy

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    The French atomic energy commission has redefined its medium- and long-term plan which fixes its strategy for the ten coming years. A. Bugat, general director of the CEA briefly presents the new missions of the CEA: budget and investments, cooperation with universities, place of fundamental research, activities in fuel cells and photovoltaic energy, cooperation with EdF, Areva and Cogema in civil nuclear research. Short paper. (J.S.)

  11. Memento. Maritime transport of MOX fuels from Europe to Japan

    International Nuclear Information System (INIS)

    1999-07-01

    The maritime transport of MOX fuels from Europe to Japan represents the last of the 3 steps of transport of the nuclear fuel reprocessing-recycling program settled between ORC (Japan), BNFL (UK) and Cogema (France). This document summarizes the different aspects of this program: the companies concerned, the physical protection measures, the US-Japan agreements (accompanying warship), the in-depth safety, the handling of MOX fuels (containers and ships), and the Japan MOX fuel needs. (J.S.)

  12. Areva: a future to be prepared; Areva: un avenir a preparer

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The Areva group was created on September 3, 2001 from the fusion of the activities of CEA-Industrie, Framatome and Cogema. It is today one of the first world actor of the nuclear sector, of the sector of new technologies and of the sector of connectors engineering. This paper recalls the factors that led to a reorganization of the French nuclear sector and to the creation of the Areva group. It briefly summarizes the forthcoming missions of Areva. (J.S.)

  13. Uranium mining in Saskatchewan

    International Nuclear Information System (INIS)

    Scales, M.

    2006-01-01

    The mines of northern Saskatchewan make Canada the worlds leading uranium producer in Canada supplied 29% of global demand, or 11.60 million tonnes of the metal in 2004. Here are two bright ideas - how to mine an orebody by neither pit nor underground method, and how to mine high-grade ore without miners - that Cogema and Cameco are pursuing in the Athabasca Basin

  14. The permission of transport of irradiated nuclear fuel elements

    International Nuclear Information System (INIS)

    Klomberg, T.J.M.

    2000-01-01

    In July and October 2000 the Dutch government granted permits for the transportation of irradiated nuclear fuel elements. The environmental organization Greenpeace objected against the permit, but that was rejected by the Dutch Council of State. A brief overview is given of the judgements and the state-of-the-art with respect to the transportation of the elements from Dutch reactors and storage facilities in Petten, Dodewaard and Borssele to Cogema in La Hague, France and BNFL in Sellafield, England

  15. Areva's privatization uncertainties

    International Nuclear Information System (INIS)

    Jemain, A.

    2004-01-01

    The French nuclear public group Areva (the fusion of CEA-Industrie, Framatome and Cogema companies) will actively prepare its privatization and stock exchange introduction before the end of the first half of 2005, in order to re-launch its acquisitions and associations policy. However, the advantages of this privatization with a preponderant public share-holding will depend on the intentions of the French government. Short paper. (J.S.)

  16. State and localisation of the nuclear wastes in France. Index established by the ANDRA observatory

    International Nuclear Information System (INIS)

    1999-01-01

    This index is the seventh edition of the the national index on nuclear wastes state and localisation. Its purpose is to index the sites where people could find radioactive wastes in France (great industry as EDF or Cogema but also little producers, national defense sites and research laboratories) and the sealed sources distributors. Law texts concerning the radioactive wastes and general information on nuclear elements or radioactivity are also provided. (A.L.B.)

  17. French and International experience on the dialogue around industrial sites

    International Nuclear Information System (INIS)

    Schneider, Th.; Heriard Dubreuil, G.; Gadbois, S.; Oudiz, A.; Remond Gouilloud, M.

    2002-12-01

    This report presents the results of a research work about 'the stakes of the dialogue around the follow up of nuclear and non nuclear industrial installations'. It used the experience of the North Cotentin radioecology group where expertise has been implemented in order to evaluate the impact on health of the releases of the Cogema La Hague plant. This report is the fruit of an interdisciplinary group ( experts of activities with risks, radiation protection, regulation in environment). (N.C.)

  18. Design, development and production of the TNF-XI new powder package

    International Nuclear Information System (INIS)

    Naigeon, P.; Brut, S.; Fujiwara, T.; Cohen, M.E.

    2004-01-01

    The TNF-XI was jointly developed by COGEMA LOGISTICS of France and Nuclear Fuel Industries, Ltd. (NFI) of Japan. The design and development of this package were started in 2000 and it was first used in 2003. The package design was based on the COGEMA LOGISTICS TN trademark UO2 package, which is cylindrical. To optimize the use of space and to facilitate operations, the TNF-XI incorporates four cavities. Each cavity is similar to one TN trademark U02. The overall shape of the package is approximately a one-meter cube, which allows it to be easily arranged and stacked in a transport container. It has a total weight of nearly 1 metric ton when loaded with 300 kg of uraniferous oxide material. The powder (or pellets) is placed inside NFI pails, and three pails are placed inside each cavity. The test results and analyses were documented in the French, Japanese, and United States 'Safety Analysis Reports' in order to get approvals in these countries. Additionally, the French license was validated in other countries. The 'Safety Analysis Reports' were prepared by COGEMA LOGISTICS in France, NFI in Japan and PACKAGING TECHNOLOGY, Inc. in the USA. In order to transform the TNF-XI design into a fleet of 800 packagings, a successful mass production process had to be developed and put into place by COGEMA LOGISTICS and the fabricator MECAGEST. Adopting mass production methods was challenging - not only because of the large quantity of packages, but also because of the rate of production (50 units per month minimum), quality requirements and the need to keep low packaging costs. This resulted in a significant challenge for mass producing the packaging: what was needed was a robust, efficient, and well-organized process. During the development of the manufacturing process, we also worked on shortening the learning curve

  19. News from the fuel elements industry

    International Nuclear Information System (INIS)

    Racine, R.; Delannay, M.; Dehon, C.; Jouan, J.; Beuneche, M.

    1981-01-01

    This article deals successively with: the re-structuring of the PWR fuel industry in France, with the setting up of Fragema and Cogema Framatome Combustible; Fragema products, from standard fuel assembly to the development of a new advanced fuel assembly; Framatome's experience with PWR fuel; fuel performances in the light of requirements imposed by network needs follow-up; devices developed by Fragema for on-site analysis of irradiated fuel [fr

  20. Dismantling of the rooms 82 to 100 at Marcoule

    International Nuclear Information System (INIS)

    Fiol, A.

    1988-01-01

    The dismantling of the rooms 82 to 100 at Marcoule is up to now, the most important decommissioning operation. The COGEMA Marcoule had the responsibility of studying and organizing the operation. On the works site the work was performed by STMI. The construction of a complete nuclear waste processing system was necessary, to protect against Pu contamination. Moreover, the efficiency of the work, was improved by the development and use of large special cutting tools [fr

  1. Management of the acceptance process of RTR aluminide type spent fuel

    International Nuclear Information System (INIS)

    Auziere, P.; Thomasson, J.

    2002-01-01

    A wide range of Research Test Reactor aluminide type spent fuel is already received for treatment conditioning at the La Hague reprocessing complex. Such a diversity calls for an utmost attention to be paid to all safety-related systems and technical aspects, to all regulatory and administrative constraints. Despite of such multiple data inputs and rigid constraints, a close cooperation between the Research Reactor operator and COGEMA enables to reach adequate and cost effective solutions also relevant to spent fuel having had an uneven history. The acceptance process is primarily based on the client descriptive data and status declaration issued by the Research Reactor (RR) operator under QA. This acceptance process is a key step, to be keenly scheduled as it is directly interactive with the RR evacuation plans and the La Hague industrial plant program. It is also governed by the reviews conducted by the French Safety Authority and generally translated into operational authorisations. Concerned by maintaining high safety standards, reliable and proven operational levels of its nuclear services performed in the La Hague facilities COGEMA includes, all through this acceptance process, the operating, regulatory and administrative requirements. This paper sets forth an overview of the approach implemented in the COGEMA organisation for the management of the acceptance process of RTR aluminide type spent fuel. (author)

  2. Well drilling by rotary percussive drill above ground

    International Nuclear Information System (INIS)

    Sabatier, G.

    1987-01-01

    Originally, the Well Drilling Section of Cogema used only the diamond core drilling technique. The appearance of independent rotation for compressed air rock drills has led to the use and to the development of this drilling system, as a drill core is not indispensable, when the material of the search is radioactive. During the last few years, hydraulic drills have replaced the compressed air drills and have resulted in a very marked improvement: - of the penetration rates; - of the depth achieved. The Well Drilling Section of Cogema has to drill about 400 km per year with rock drills above ground and holds also the record for depth achieved with this technique, i.e. 400 m in granite. In France, the costs of these types of drilling are for the same depth of the order of one-quarter of the core drilling and half of the drilling with a down-the-hole drill. Cogema has greatly developed the types of well logging which now permits the extension of this type of drilling to the search for other materials than uranium [fr

  3. Focusing on the environment

    International Nuclear Information System (INIS)

    Jourdin, C.M. du; Lacroix, D.

    2004-01-01

    Safety of our packages and operations is our first concern to ensure protection for people and the environment. Environmental impact generated by COGEMA LOGISTICS activities is also covered by an environmental management approach. This systematical environmental management approach starts with the design phase of new products and processes and meets several objectives: -to reduce the environmental impact of our direct activities by optimizing the maintenance, management and storage of our fleet, -to inform and develop awareness among our suppliers and incite them to join us in this approach. We favor the development of partnerships with our suppliers so as to work together to improve our products and services. As part of AREVA's policy of sustainable development, COGEMA LOGISTICS has decided to expand the management system at the environment using the ISO 14001 model. The associated ISO certification was obtained in February 2003 for all our activities and locations. In this context and beyond the compliance with regulations, COGEMA LOGISTICS undertakes to prevent all types of pollution and continuously improve environmental performance, together with customers, authorities, suppliers and local partners

  4. Ultrasonic Examination of Double-Shell Tank 241-AY-101 Examination Completed August 2003

    International Nuclear Information System (INIS)

    Pardini, Allan F.; Posakony, Gerald J.

    2003-01-01

    COGEMA Engineering Corporation (COGEMA), under a contract from CH2M Hill Hanford Group (CH2M Hill), has performed an ultrasonic nondestructive examination of selected portions of Double-Shell Tank 241-AY-101. The purpose of this examination was to provide information that could be used to evaluate the integrity of the wall of the secondary tank. The requirements for the ultrasonic examination of Tank 241-AY-101 were to detect, characterize (identify, size, and locate), and record measurements made of any wall thinning or pitting that might be present in the wall of the secondary tank. Any measurements that exceed the requirements set forth in the Engineering Task Plan (ETP), RPP--11832 (Jensen 2002) and summarized on page 1 of this document, are reported to CH2M Hill and the Pacific Northwest National Laboratory (PNNL) for further evaluation. Under the contract with CH2M Hill, all data is to be recorded on disk and paper copies of all measurements are provided to PNNL for third-party evaluation. PNNL is responsible for preparing a report that describes the results of the COGEMA ultrasonic examinations

  5. Focusing on the environment

    Energy Technology Data Exchange (ETDEWEB)

    Jourdin, C.M. du; Lacroix, D. [COGEMA Logistics (AREVA Group) (France)

    2004-07-01

    Safety of our packages and operations is our first concern to ensure protection for people and the environment. Environmental impact generated by COGEMA LOGISTICS activities is also covered by an environmental management approach. This systematical environmental management approach starts with the design phase of new products and processes and meets several objectives: -to reduce the environmental impact of our direct activities by optimizing the maintenance, management and storage of our fleet, -to inform and develop awareness among our suppliers and incite them to join us in this approach. We favor the development of partnerships with our suppliers so as to work together to improve our products and services. As part of AREVA's policy of sustainable development, COGEMA LOGISTICS has decided to expand the management system at the environment using the ISO 14001 model. The associated ISO certification was obtained in February 2003 for all our activities and locations. In this context and beyond the compliance with regulations, COGEMA LOGISTICS undertakes to prevent all types of pollution and continuously improve environmental performance, together with customers, authorities, suppliers and local partners.

  6. MOX fuel fabrication, in reactor performance and improvement

    International Nuclear Information System (INIS)

    Vliet, J. van; Deramaix, P.; Nigon, J.L.; Fournier, W.

    1998-01-01

    In Europe, MOX fuel for light water reactors (LWRs) has first been manufactured in Belgium and Germany. Belgonucleaire (BN) loaded the first MOX assembly in the BR3 Pressurised Water Reactor (PWR) in 1963. In June 1998, more than 750 tHM LWR MOX fuel assemblies were manufactured on a industrial scale in Europe without any particular difficulty relating to fuel fabrication, reactor operation or fuel behaviour. So, today plutonium recycling through MOX fuel is a mature industry, with successful operational experience and large-scale fabrication plants. In this field, COGEMA and BELGONUCLEAIRE are the main actors by operating simultaneously three complete multidesign fuel production plants: MELOX plant (in Marcoule), CADARACHE plant and P0 plant (in Dessel, Belgium). Present MOX production capacity available to COGEMA and BN fits 175 tHM per year and is to be extended to reach about 325 tHM in the year 2000. This will represent 75% of the total MOX fabrication capacity in Europe. The industrial mastery and the high production level in MOX fabrication assured by high technology processes confer to these companies a large expertise for Pu recycling. This allows COGEMA and BN to be major actors in Pu-based fuels in the coming second nuclear era with advanced fuel cycles. (author)

  7. Burn-up measurements coupling gamma spectrometry and neutron measurement

    Energy Technology Data Exchange (ETDEWEB)

    Toubon, H.; Pin, P. [AREVA/CANBERRA, 1 rue des Herons, 78182 St Quentin-en-Yvelines Cedex (France); Lebrun, A. [IAEA, Wagramer Strasse 5, PO Box 100, Vienna (Austria); Oriol, L.; Saurel, N. [CEA Cadarache, 13108 Saint Paul Lez Durance Cedex (France); Gain, T. [AREVA/COGEMA Reprocessing Business Unit, La Hague, 50444 Beaumont Hague Cedex (France)

    2006-07-01

    The need to apply for burn-up credit arises with the increase of the initial enrichment of nuclear fuel. When burn-up credit is used in criticality safety studies, it is often necessary to confirm it by measurement. For the last 10 years, CANBERRA has manufactured the PYTHON system for such measurements. However, the method used in the PYTHON itself uses certain reactor data to arrive at burn-up estimates. Based on R and D led by CEA and COGEMA in the framework of burn-up measurement for burn-up credit and safeguards applications, CANBERRA is developing the next generation of burn-up measurement device. This new product, named SMOPY, is able to measure burn-up of any kind of irradiated fuel assembly with a combination of gamma spectrometry and passive neutron measurements. The measurement data is used as input to the CESAR depletion code, which has been developed and qualified by CEA and COGEMA for burn-up credit determinations. In this paper, we explain the complementary nature of the gamma and neutron measurements. In addition, we draw on our previous experience from PYTHON system and from COGEMA La Hague to show what types of evaluations are required to qualify the SMOPY system, to estimate its uncertainties, and to detect discrepancies in the fuel data given by the reactor plant to characterize the irradiated fuel assembly. (authors)

  8. Ultrasonic Examination of Double-Shell Tank 241-AP-104. Examination Completed August 2004

    International Nuclear Information System (INIS)

    Pardini, Allan F.; Posakony, Gerald J.

    2004-01-01

    COGEMA Engineering Corporation (COGEMA), under a contract from CH2M Hill Hanford Group (CH2M Hill), has performed an ultrasonic nondestructive examination of selected portions of Double-Shell Tank 241-AP-104. The purpose of this examination was to provide information that could be used to evaluate the integrity of the wall of the primary tank. The requirements for the ultrasonic examination of Tank 241-AP-104 were to detect, characterize (identify, size, and locate), and record measurements made of any wall thinning, pitting, or cracks that might be present in the wall of the primary tank. Any measurements that exceed the requirements set forth in the Engineering Task Plan (ETP), RPP-17750 (Jensen 2003) and summarized on page 1 of this document, are reported to CH2M Hill and the Pacific Northwest National Laboratory (PNNL) for further evaluation. Under the contract with CH2M Hill, all data is to be recorded on disk and paper copies of all measurements are provided to PNNL for third-party evaluation. PNNL is responsible for preparing a report that describes the results of the COGEMA ultrasonic examinations

  9. Ultrasonic Examination of Double-Shell Tank 241-SY-103. Examination completed February 2004

    International Nuclear Information System (INIS)

    Pardini, Allan F.; Posakony, Gerald J.

    2004-01-01

    COGEMA Engineering Corporation (COGEMA), under a contract from CH2M Hill Hanford Group (CH2M Hill), has performed an ultrasonic nondestructive examination of selected portions of Double-Shell Tank 241-SY-103. The purpose of this examination was to provide information that could be used to evaluate the integrity of the wall of the primary tank. The requirements for the ultrasonic examination of Tank 241-SY-103 were to detect, characterize (identify, size, and locate), and record measurements made of any wall thinning, pitting, or cracks that might be present in the wall of the primary tank. Any measurements that exceed the requirements set forth in the Engineering Task Plan (ETP), RPP-17750 (Jensen 2003) and summarized on page 1 of this document, are reported to CH2M Hill and the Pacific Northwest National Laboratory (PNNL) for further evaluation. Under the contract with CH2M Hill, all data is to be recorded on disk and paper copies of all measurements are provided to PNNL for third-party evaluation. PNNL is responsible for preparing a report that describes the results of the COGEMA ultrasonic examinations

  10. Ultrasonic Examination of Double-Shell Tank 214-AW-102 Knuckle Region. Examination completed February 2003

    International Nuclear Information System (INIS)

    Pardini, Allan F.; Posakony, Gerald J.

    2003-01-01

    COGEMA Engineering Corporation (COGEMA), under a contract from CH2M Hill Hanford Group (CH2M Hill), has performed an ultrasonic examination of the knuckle region of Double-Shell Tank 241-AW-102 utilizing the Remotely Operated Nondestructive Examination (RONDE) system. The purpose of this examination was to provide information that could be used to evaluate the integrity of the knuckle region of the primary tank. The requirements for the ultrasonic examination of Tank 241-AW-102 were to detect, characterize (identify, size, and locate), and record measurements made of any circumferentially oriented cracks that might be present in the knuckle area of the primary tank. Any measurements that exceed the requirements set forth in the Engineering Task Plan (ETP), RPP-7869, are reported to CH2M Hill and the Pacific Northwest National Laboratory (PNNL) for further evaluation. Under the contract with CH2M Hill, all data is to be recorded on disk and paper copies of all measurements are provided t o PNNL for third-party evaluation. PNNL is responsible for preparing a report(s) that describes the results of the COGEMA ultrasonic examinations

  11. Ultrasonic Examination of Double-Shell Tank 241-AZ-102 Examination Completed August 2003

    International Nuclear Information System (INIS)

    Pardini, Allan F.; Posakony, Gerald J.

    2003-01-01

    COGEMA Engineering Corporation (COGEMA), under a contract from CH2M Hill Hanford Group (CH2M Hill), has performed an ultrasonic nondestructive examination of selected portions of Double-Shell Tank 241-AZ-102. The purpose of this examination was to provide information that could be used to evaluate the integrity of the wall of the primary tank. The requirements for the ultrasonic examination of Tank 241-AZ-102 were to detect, characterize (identify, size, and locate), and record measurements made of any wall thinning, pitting, or cracks that might be present in the wall of the primary tank. Any measurements that exceed the requirements set forth in the Engineering Task Plat (ETP), RPP-11832 (Jensen 2002) and summarized on page 1 of this document, are reported to CH2M Hill and the Pacific Northwest National Laboratory (PNNL) for further evaluation. Under the contract with CH2M Hill, all data is to be recorded on disk and paper copies of all measurements are provided to PNNL for third-party evaluation. PNNL is responsible for preparing a report that describes the results of the COGEMA ultrasonic examinations

  12. Ultrasonic Examination of Double-Shell Tank 241-SY-102. Examination Completed June 2004

    International Nuclear Information System (INIS)

    Pardini, Allan F.; Posakony, Gerald J.

    2004-01-01

    COGEMA Engineering Corporation (COGEMA), under a contract from CH2M Hill Hanford Group (CH2M Hill), has performed an ultrasonic nondestructive examination of selected portions of Double-Shell Tank 241-SY-102. The purpose of this examination was to provide information that could be used to evaluate the integrity of the wall of the primary tank. The requirements for the ultrasonic examination of Tank 241-SY-102 were to detect, characterize (identify, size, and locate), and record measurements made of any wall thinning, pitting, or cracks that might be present in the wall of the primary tank. Any measurements that exceed the requirements set forth in the Engineering Task Plan (ETP), RPP-17750 (Jensen 2003) and/SUMmarized on page 1 of this document, are reported to CH2M Hill and the Pacific Northwest National Laboratory (PNNL) for further evaluation. Under the contract with CH2M Hill, all data is to be recorded on disk and paper copies of all measurements are provided to PNNL for third-party evaluation. PNNL is responsible for preparing a report that describes the results of the COGEMA

  13. EUROFAB: fabrication of four MOX lead tests assemblies for the US DOE

    International Nuclear Information System (INIS)

    Jean-Pierre Bariteau

    2006-01-01

    In a multilateral agreement, the United States (US) and the Russian Federation agreed to reduce their respective weapons stockpiles by each country disposing of 34 tons of military origin plutonium. On behalf of the US government, the Department of Energy contracted with Duke, COGEMA, Stone and Webster (DCS) to design a Mixed Oxide Fuel Fabrication facility (MFFF) which would be built and operated at the DOE Savannah River Site near Aiken, South Carolina. This plant will transform the US excess weapons stockpile into MOX fuel, which will be used it in existing domestic commercial power reactors. The MFFF is based on a replication of AREVA existing facilities (La Hague for Pu polishing and Melox for MOX fabrication). In parallel with the design, construction and startup of the MFFF facility, DOE commissioned fabrication and irradiation of 4 lead test assemblies in one of the Mission Reactors to assist in obtaining NRC approval for MOX fuel loading in US NPPs prior to the production phase of the MFFF facility. This program was named 'EUROFAB', since fabrication had to be made in Europe because no facility implementing the MFFF technology was existing in the USA. The COGEMA Recycling Business unit transmitted a bid to DCS in April 2003, which proposed to perform Eurofab fabrication in its Cadarache (pellets and rods) and Melox (assembly mounting) facilities. In August 2003, the decision was made by DCS, on behalf of the DOE, to award the EUROFAB fabrication contract to COGEMA. (author)

  14. 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

  15. A durable and dependable solution for RTR spent fuel management

    International Nuclear Information System (INIS)

    Thomasson, J.

    1999-01-01

    RTR Operators need efficient and cost-effective services for the management of their spent fuel and this, for the full lifetime of their facility. Thanks to the integration of transport, reprocessing and conditioning services, COGEMA provides a cogent solution, with the utmost respect for safety and preservation of the environment, for the short, medium and long terms. As demonstrated in this paper, this option offers the only durable and dependable solution for the RTR spent fuel management, leading to a conditioning for the final residues directly suitable for final disposal. The main advantage of such an option is obviously the significant reduction in terms of volume and radiotoxicity of the ultimate waste when compared to direct disposal of spent fuels. The efficiency of such a solution has been proven, some RTR operators having already trusted COGEMA for the management of their aluminide fuel. With its commitment in R and D activities for the development of a high performance and reprocessable LEU fuels, COGEMA will be able to propose a solution for all types of fuels, HEU and LEU

  16. Burn-up measurements coupling gamma spectrometry and neutron measurement

    International Nuclear Information System (INIS)

    Toubon, H.; Pin, P.; Lebrun, A.; Oriol, L.; Saurel, N.; Gain, T.

    2006-01-01

    The need to apply for burn-up credit arises with the increase of the initial enrichment of nuclear fuel. When burn-up credit is used in criticality safety studies, it is often necessary to confirm it by measurement. For the last 10 years, CANBERRA has manufactured the PYTHON system for such measurements. However, the method used in the PYTHON itself uses certain reactor data to arrive at burn-up estimates. Based on R and D led by CEA and COGEMA in the framework of burn-up measurement for burn-up credit and safeguards applications, CANBERRA is developing the next generation of burn-up measurement device. This new product, named SMOPY, is able to measure burn-up of any kind of irradiated fuel assembly with a combination of gamma spectrometry and passive neutron measurements. The measurement data is used as input to the CESAR depletion code, which has been developed and qualified by CEA and COGEMA for burn-up credit determinations. In this paper, we explain the complementary nature of the gamma and neutron measurements. In addition, we draw on our previous experience from PYTHON system and from COGEMA La Hague to show what types of evaluations are required to qualify the SMOPY system, to estimate its uncertainties, and to detect discrepancies in the fuel data given by the reactor plant to characterize the irradiated fuel assembly. (authors)

  17. Shipments of irradiated DIDO fuel from Risoe National Laboratory to the Savannah River Site - Challenges and achievements

    International Nuclear Information System (INIS)

    Anne, C.; Patterson, J.

    2003-01-01

    On September 28, 2000, the Board of Governors of Risoe National Laboratory decided to shut down the Danish research reactor DR3 due to technical problems (corrosion on the reactor aluminum tank). Shortly thereafter, the Danish Government asked the National Laboratory to empty the reactor and its storage pools containing a total of 255 DIDO irradiated elements and ship them to Savannah River Site in the USA as soon as possible. Risoe National Laboratory had previously contracted with Cogema Logistics to ship DR3 DIDO fuel elements to SRS through the end of the return program. The quantity of fuel was less than originally intended but the schedule was significantly shorter. It was agreed in June 2001 that a combination of Cogema Logistics' and NAC casks would be preferable, as it would allow Risoe to ship all the irradiated fuel in two shipments and complete the shipments by June 2002. Risoe National Laboratory, Cogema Logistics and NAC International had twelve months to perform the shipments including licensing, basket fabrication for the NAC-LWT casks and actual transport. The paper describes the challenging work that was accomplished to meet the date of June 2002. (author)

  18. Maintenance analysis method and operational feedback: a comprehensive maintenance management

    International Nuclear Information System (INIS)

    Mathieu Riou; Victor Planchon

    2006-01-01

    Full text of publication follows: Current periodic inspections program carried out on the COGEMA LOGISTICS casks is required by regulations and approved by the competent Authority. Thus, Safety and casks conformity to the according certificate of approval are guaranteed. Nonetheless, based on experience it appeared that some maintenance operations did not seem relevant or were redundant. Then, it was decided to rethink completely our maintenance program to reach the following objectives: - Set up the 'a minima' required inspection operations required to guarantee Safety and conformity to the certificate of approval, - Optimize criteria and periodicities of inspections taking into account: operational feedback, routine inspections carried out for each transport, regulations, environmental impact (ALARA, waste reduction,...), cost-effectiveness (reduction of cask's immobilization period,...). - Set up a maintenance program in Safety Analysis Reports that: stands alone (no need to check the specification or the certificate of approval to have the complete list of inspections mandatory to guarantee Safety), gives objectives instead of means of controls. This approach needs then to be re-evaluated by the competent Authority. Study's scope has been limited to the TN TM 12 cask family which is intensely used. COGEMA LOGISTICS has a high operational feedback on these casks. After Authority agreement, and in accordance with its requirements, study will then be extended to the other casks belonging to the COGEMA LOGISTICS cask fleet. Actually, the term 'maintenance' is linked to 'Base maintenance' and 'Main maintenance' and implicitly means that the cask is immobilized for a given period. To emphasize the modifications, the term 'maintenance' is no longer used and is substituted by 'periodic upkeep'. By changing the name, COGEMA LOGISTICS wants to emphasize that: some operations can for instance be realized while the cask is unloaded, periodicities are thought in terms of

  19. Overview of remote handling technologies developed for inspection and maintenance of spent fuel management facilities in France

    Energy Technology Data Exchange (ETDEWEB)

    Desbats, Philippe [CEA - Direction de la Recherche Technologique / LIST, BP 6 - 92265, Fontenay-aux-Roses cedex (France); Piolain, Gerard [COGEMA-HAG/DMCO, AREVA NC SA, 2, rue Paul Dautier, BP 4, 78 141 Velizy Cedex (France)

    2006-07-01

    In the facilities of the end of the nuclear fuel cycle, like spent fuel storage pools, reprocessing plants, Plutonium-based fuel manufacturing plants or waste temporary storage units, materials handling must be carried out remotely, taking into account the nuclear radiating environment. In addition to the automation requirement, robotics equipment in the nuclear industry must be substituted to human operators in order to respect the ALARA principle. More over, remote handling technologies aim to improve the working conditions, as well as the quality of the work achieved by the operators. Ten years ago, COGEMA (AREVA Group) and CEA (French Atomic Energy Agency) started an ambitious R and D program in robotics and remote handling technologies applied to COGEMA spent fuel management facilities in France, with the aim to cover the requirements of the different plant life cycle steps. The paper gives an overview of the important developments that have been carried out by CEA and then transferred to the COGEMA industrial group. The range includes the next generation of servo-manipulators, long range inspection tools and carriers, nuclear versions of industrial robots, radiation hardened electronic systems, interactive environment modeling tools, as well as force-feedback master-slave generic control software for tele-operation systems. Some applications of this development are presented in the paper: - rad-hard electronic modules for robotic equipment which are used by COGEMA in high radiating environment; - long reach articulated carrier for inspection of spent full management blind cells; - new electrical force feedback master/slave system to improve the tele-operation of standard tele-manipulators; - generic control software for tele-manipulators. The results of the robotic program carried out by COGEMA and CEA have been very valuable for the introduction of new technologies inside nuclear industry. Innovative products and sub-systems can be integrated now in a large

  20. 3. forum of radiation protection sciences - Book of abstracts

    International Nuclear Information System (INIS)

    2002-10-01

    This document brings together the abstracts of all presentations given at the 3. European forum of radiation protection sciences on the topic of radiation protection and dismantling logic: 1 - Organisation of dismantling operations financing at UP1 Marcoule (Jean Laurent, GIE CODEM); 2 - Dismantling strategy at the CEA - civil branch (Gerard Cerdan, CEA/DEN/DPA); 3 - Safety and radiation protection control during nuclear facilities dismantling (Estelle Chapalain, DGSNR); 4 - Regulatory evolutions in radiation protection (Marc Ammerich, DGSNR); 5 - Implementation of the ALARA approach in the BR3 reactor dismantling project (Vincent Massaut, SCK-CEN Mol, Belgium); 6 - Study of Super Phenix reactor block dismantling: radiological characterization (Fabrice Biagi, Framatome ANP; Herve Salliot, EDF CIDEN); 7 - Wastes characterization: prerequisites to main cleansing projects (Guy Andrieu, Cogema Marcoule); 8 - Radiation protection in relation with the definitive shutdown of UP1 Marcoule (Philipp Blaise, COGEMA Marcoule); 9 - Deconstruction of the Monts d'Arree power plant (Alain Ensuque, Monts d'Arree site, Brennilis); 10 - Presentation of the cleansing project of Marcoule's pilot workshop (Gerald Imbard, CEA Valrho); 11 - AT1 dismantling at Cogema La Hague (David Nolin, CEA Valrho); 12 - Dismantling management of the CERN-LEP - Large electron-positon collider (John Poole, CERN Switzerland); 13 - Level 3 dismantling of the TRITON facility (Elia Lopes, CEA FAR); 14 - Presentation of cleansing operations at Cogema Marcoule UP1 factory (Christine Georges, Cogema Marcoule); 15 - Decontamination strategy prior to the dismantling of the highly contaminated primary and auxiliary circuits of the BR3 PWR reactor (Pierre Valenduc, SCK-CEN Mol, Belgium); 16 - Nuclear submarines dismantling (Philippe Queau, DCN Cherbourg); 17 - Use of tele-operation in dismantling (Jean Marie Carrere, CEA Valrho); 18 - Design principle of tele-operated tools (Jean Paul Drogoul, Cogema Marcoule); 19

  1. Vitrification of HLW in cold crucible melter

    International Nuclear Information System (INIS)

    Bordier, G.

    2005-01-01

    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 the CEA (French Atomic Energy Commission), COGEMA (Industrial Operator), and SGN (COGEMA's 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 qualified on a full-scale prototype at the CEA pilot facility in Marcoule. Engineering study has been integrated in parallel in order to take into account that the Cold Crucible should be installed remotely in one of the R7 vitrification

  2. Testing of LWR fuel rods to support criticality safety analysis of transport accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Purcell, P.C. [BNFL International Transport, Spent Fuel Services (United Kingdom); Dallongeville, M. [COGEMA Logistics (AREVA Group) (France)

    2004-07-01

    For the transport of low enriched materials, criticality safety may be demonstrated by applying pessimistic modelling assumptions that bound any realistic case. Where Light Water Reactor (LWR) fuel is being transported, enrichment levels are usually too high to permit this approach and more realistic data is needed. This requires a method by which the response of LWR fuel under impact accident conditions can be approximated or bounded. In 2000, BNFL and COGEMA LOGISTICS jointly commenced the Fuel Integrity Project (FIP) whose objective was to develop such methods. COGEMA LOGISTICS were well advanced with a method for determining the impact response of unirradiated fuel, but required further test data before acceptance by the Transport Regulators. The joint project team extensively discussed the required inputs to the FIP, from which it was agreed that BNFL would organise new tests on both unirradiated and irradiated fuel samples and COGEMA LOGISTICS would take major responsibility for evaluating the test results. Tests on unirradiated fuel rod samples involved both dynamic and quasi-static loading on fuel samples. PWR fuel rods loaded with uranium pellets were dropped vertically from 9m onto a rigid target and this was repeated on BWR fuel rods, similar tests on empty fuel rods were also conducted. Quasi-static tests were conducted on 530 mm long PWR and BWR fuel specimens under axial loading. Tests on irradiated fuel samples were conducted on high burn-up fuel rods of both PWR and BWR types. These were believed original to the FIP project and involved applying bending loads to simply supported pressurised rod specimens. In one test the fuel rod was heated to nearly 500oC during loading, all specimens were subject to axial impact before testing. Considerable experience of fuel rod testing and new data was gained from this test programme.

  3. New package systems for EDF recycling policy

    Energy Technology Data Exchange (ETDEWEB)

    Leboucher, I.; Michels, L.; Hugon, F.C. [COGEMA Logistics (AREVA Group) (France); Penoty, C. [EDF - Electricite de France (France); Froment, A. [COGEMA (AREVA Group) (France)

    2004-07-01

    Since the beginning of the nineties, EDF (Electricite France) has been carrying out a policy towards increasing burn-up. As a consequence and to keep energetic performances of the MOX (Mixed OXide uranium and plutonium) fresh fuel assemblies at parity with UO2 fuel, the concentration in plutonium increased up to 7.1%, soon up to 8.65% and even more. To take into account the increased dose rate and the increased thermal power of these MOX fresh fuels in the transportation system, COGEMA LOGISTICS designed, manufactured and licensed the MX8 package to replace the previous packaging. Simultaneously new high-secured transport system was developed. Due to the capacity of the reactor pool, the spent fuel assemblies must be evacuated with a short cooling time and high residual power. Because of the neutron source of these future MOX spent fuel assemblies, the TNa12/2 packaging, which has been in operation since 1980's to transport UO2 or MOX spent fuel to COGEMA La Hague, from EDF, other European and Japanese NPP lacks flexibility. COGEMA LOGISTICS is designing a new cask (TN trademark 112) to transport the future EDF MOX spent fuel assemblies. The TN trademark 112 has to comply with the 1996 edition of the IAEA transport regulations and with the transport and handling equipment presently used for the transport of spent fuel in France. It can be loaded with 12 assemblies, either MOX or UO2. This paper gives a description of two packages belonging to the new generation: - one for fresh MOX fuel assemblies transportation, used on EDF's power plants for MOX reloads, - one for spent MOX fuel assemblies transportation, presently under development with a first transport planned for mid-2007.

  4. A.C.R.O. activity report 2001

    International Nuclear Information System (INIS)

    2001-01-01

    As regards the environmental protection, the A.C.R.O. maintained in 2001 its programs of surveillance around the main western nuclear installations of France. The radioecological surveillance of the site of Cogema La-Hague for the dismantling of the former pipe of release in sea was one of the key points of this action environmental surveillance. The two accidents of atmospheric release in may and october 2001 at Cogema La Hague have shown the interest of an association as A.C.R.O.. It is thank to the measure, by our laboratory, of repercussions on environment of these incidents that it has been possible to bring to light a dysfunction of the measurement system of the gaseous effluents released by the facility operator. To improve the public information, A.C.R.O. concerns its main efforts on the development of the consumer technical information available on-line via its web site and in its regular publication 'the nuclear chronicle'. Besides, the participation of the A.C.R.O. to the radioecology North Cotentin group (within the framework of the continuation of its mission) but also at various local commissions of information (C.L.I.) as well as at the superior council of the safety and nuclear information ( C.S.S.I.N.) stays an essential action. Concerning the environmental protection, the A.C.R.O. maintains its programs of surveillance around the nuclear facilities of La Hague and Chinon and continues the surveillance of the site of Cogema La hague as regards the new pipe of release in sea. Among the new commitments for 2000, the participation to the radioecology North Cotentin group in the framework of the continuation of its mission and the participation to the international intercomparison 'N.O.R.C.O. 2000' punctuated the year. (N.C.)

  5. Interim storage packagings for spent fuels : how to optimize an universal design to local needs

    International Nuclear Information System (INIS)

    Konirsch, O.; Kawabata, T.; Hunter, I.

    2003-01-01

    For the last ten years, the interim storage market for spent fuels issued from Nuclear Power Plants has significantly increased all over the world: there are presently many storage projects either in Asia, in North America and in Europe. Even if there is no international regulation on that field, there is a big concern from all the nuclear industry to try to harmonise the specification for the definition of the Interim Storage Systems. One example of this harmonisation is the common and general wish to develop systems, which allow to be easily transportable either to a final repository or to a reprocessing plant. As this destination is generally not yet known, the storage system should be able to be transported all over the world. On the other hand, the specific requirement for the storage facility and its associated equipment are subject to local and/or national regulation. COGEMA LOGISTICS Group has developed two different technologies which are compatible with this principle of harmonisation: dual purpose metallic cask represented by the TN24 family and the concrete storage system NUHOMS(R). For both technologies, basic designs can be adapted to the local needs in term of performance and of national regulation. To cover all the world, COGEMA LOGISTICS Group has its own subsidiaries, in Asia, in North America and in Europe with their own autonomous engineers teams for designing, licensing, manufacturing and delivering the transport/storage products. COGEMA LOGISTICS Group is presently the leader on the dry interim storage market. The purpose of the present paper is to show how it is possible to optimise a basic existing design of a dual purpose metallic cask for a local need of storage. Taking into account the national rules for storage and the international regulation for transport, the designer shall minimise the development cost for a completely new design and maximise the capacity of the packaging regarding the allowable limits in the Nuclear Power Plant, in

  6. New package systems for EDF recycling policy

    International Nuclear Information System (INIS)

    Leboucher, I.; Michels, L.; Hugon, F.C.; Penoty, C.; Froment, A.

    2004-01-01

    Since the beginning of the nineties, EDF (Electricite France) has been carrying out a policy towards increasing burn-up. As a consequence and to keep energetic performances of the MOX (Mixed OXide uranium and plutonium) fresh fuel assemblies at parity with UO2 fuel, the concentration in plutonium increased up to 7.1%, soon up to 8.65% and even more. To take into account the increased dose rate and the increased thermal power of these MOX fresh fuels in the transportation system, COGEMA LOGISTICS designed, manufactured and licensed the MX8 package to replace the previous packaging. Simultaneously new high-secured transport system was developed. Due to the capacity of the reactor pool, the spent fuel assemblies must be evacuated with a short cooling time and high residual power. Because of the neutron source of these future MOX spent fuel assemblies, the TN 12/2 packaging, which has been in operation since 1980's to transport UO2 or MOX spent fuel to COGEMA La Hague, from EDF, other European and Japanese NPP lacks flexibility. COGEMA LOGISTICS is designing a new cask (TN trademark 112) to transport the future EDF MOX spent fuel assemblies. The TN trademark 112 has to comply with the 1996 edition of the IAEA transport regulations and with the transport and handling equipment presently used for the transport of spent fuel in France. It can be loaded with 12 assemblies, either MOX or UO2. This paper gives a description of two packages belonging to the new generation: - one for fresh MOX fuel assemblies transportation, used on EDF's power plants for MOX reloads, - one for spent MOX fuel assemblies transportation, presently under development with a first transport planned for mid-2007

  7. Waste management issues, a set of technologies

    International Nuclear Information System (INIS)

    Gautrot, J.J.

    2000-01-01

    As any other industry, nuclear fuel cycle back-end raises the major issue of waste management. In France, spent fuel is considered as valuable materials and only the ultimate waste are considered as actual waste. Accordingly, waste issue is as follows: a sorting out has to be done, in order to separate valuable materials from actual wastes, put any outlet flow under a stable form and condition them appropriately to their respective recycling or disposal routes. This implies the implementation of a comprehensive set of technologies. Actually, it is an industrial reality, as the COGEMA Group has for a long time set up a reprocessing and conditioning strategy in its plants. Waste management issues are common to many activities. European as well as French regulators already introduced the twofold necessity to reduce waste volumes, and to dispose of only ''ultimate waste'' as concerns industrial and household waste mainly. In this objective, French nuclear reprocessing and recycling industry may be seen as a breeding ground of well-proven technologies and management options. Actually, processes used can also give an answer to such different issues as excess plutonium immobilization, sites cleaning up (including for instance treatment of the liquid HLW legacy), dismantling wastes management. There are a number of operations to be dealt with worldwide that will find a solution in any of the technologies implemented and optimized in COGEMA facilities. Based on the COGEMA Group know-how, the present paper will describe those technologies and explain how they can solve the other stringent waste management issues worldwide. (author)

  8. MX 8: the next generation high capacity system for the transport of fresh MOX fuel

    International Nuclear Information System (INIS)

    Potelle, F.; Issard, H.

    1998-01-01

    The choice of reprocessing policy was made a long time ago in France, leading to the development of an advanced Pu recycling industry. In 1987, Saint Laurent was the first French reactor to be loaded with fresh MOX fuel. Transnucleaire, then in charge of transport packaging development, created the FS 69 concept, derived from the classical RCC concept for the transport of UO 2 fresh fuel. On the other hand, Cogema, as the main actor in the field of fuel cycle and thus in transport matters, developed the associated security truck and security caisson in order to provide the transport system with the acceptable Physical Protection devices required by French Authorities. As a whole, the security truck and the FS 69 have now been used for more than ten years with a remarkable level of efficiency and safety. Indeed, more than 600 fresh MOX fuel elements have been delivered, without any incident, both regarding safety or fuel integrity requirements. But, as a matter of fact, the replacement of FS 69 transport system is now scheduled for several reasons. First of all, the burnups achieved with UO 2 fuel progressed together with its enrichment within the last ten years, and the MOX 'equivalence' also implies that its Pu content be increased to enhance its reactor performances: from 5.25 % of Pu content today, the MOX fuel will reach 7% tomorrow, and almost 10% the day after tomorrow. Lastly, the reprocessing/recycling policy has been confirmed and amplified, leading to an increasing number of 'moxified' reactors. As a consequence, the French utility (EDF), the fuel designer (Fragema, the joint venture between Framatome and Cogema), the fuel manufacturer (Cogema), and the transporter (Transnucleaire) joined in a specific working group devoted to the development of the MX 8, the next generation high capacity system for the land transport of MOX fuel. (authors)

  9. Testing of LWR fuel rods to support criticality safety analysis of transport accident conditions

    International Nuclear Information System (INIS)

    Purcell, P.C.; Dallongeville, M.

    2004-01-01

    For the transport of low enriched materials, criticality safety may be demonstrated by applying pessimistic modelling assumptions that bound any realistic case. Where Light Water Reactor (LWR) fuel is being transported, enrichment levels are usually too high to permit this approach and more realistic data is needed. This requires a method by which the response of LWR fuel under impact accident conditions can be approximated or bounded. In 2000, BNFL and COGEMA LOGISTICS jointly commenced the Fuel Integrity Project (FIP) whose objective was to develop such methods. COGEMA LOGISTICS were well advanced with a method for determining the impact response of unirradiated fuel, but required further test data before acceptance by the Transport Regulators. The joint project team extensively discussed the required inputs to the FIP, from which it was agreed that BNFL would organise new tests on both unirradiated and irradiated fuel samples and COGEMA LOGISTICS would take major responsibility for evaluating the test results. Tests on unirradiated fuel rod samples involved both dynamic and quasi-static loading on fuel samples. PWR fuel rods loaded with uranium pellets were dropped vertically from 9m onto a rigid target and this was repeated on BWR fuel rods, similar tests on empty fuel rods were also conducted. Quasi-static tests were conducted on 530 mm long PWR and BWR fuel specimens under axial loading. Tests on irradiated fuel samples were conducted on high burn-up fuel rods of both PWR and BWR types. These were believed original to the FIP project and involved applying bending loads to simply supported pressurised rod specimens. In one test the fuel rod was heated to nearly 500oC during loading, all specimens were subject to axial impact before testing. Considerable experience of fuel rod testing and new data was gained from this test programme

  10. Low-level Radioactive waste Management

    International Nuclear Information System (INIS)

    1991-01-01

    This meeting describes low-level radioactive waste management problems and contains 8 papers: 1 Low-level radioactive waste management: exemption concept and criteria used by international organizations. 2 Low-level radioactive waste management: french and foreign regulations 3 Low-level radioactive waste management in EDF nuclear power plants (FRANCE) 4 Low-level radioactive waste management in COGEMA (FRANCE) 5 Importance of low-level radioactive wastes in dismantling strategy in CEA (FRANCE) 6 Low-level radioactive waste management in hospitals 7 Low-level radioactive waste disposal: radiation protection laws 8 Methods of low-level radioactive materials measurements during reactor dismantling or nuclear facilities demolition (FRANCE)

  11. The yawning chasm of French nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    This is an account of a paper appeared in Energy Economist, February 1988 and contains a severe critique of the French nuclear power policy, in particular the Electricite de France, Cogema and Framatome. It is argued that the blueprint of the original nuclear power program has not been achieved in many topics. Points of critique to the EdF are: the electricity price, overcapacities and financial indeptedness. The French industries are not flourishing due to ample supply of cheap energy, nor do French nuclear manufacturers sell the fast breeder technology throughout the world. (qui)

  12. Uranium enrichment by laser: a technology for the future

    International Nuclear Information System (INIS)

    Cazalet, J.

    1999-01-01

    The SILVA (Isotopic Separation by Laser on atomic Vapor of uranium) process, developed by CEA and COGEMA, is an innovative system of production of enriched uranium, to be used as the fuel of nuclear reactors. It is a sound research program, calling on advanced technologies that are quickly changing. The goal is to cut drastically the production cost in comparison with the operating cost of the present plants based on gaseous diffusion. its industrialization is forecast for the beginning of next century. The SILVA process consists in putting a vapor of uranium through a beam of photons emitted by finely tuned lasers capable of ionising selectively the isotopes 235. The ionised isotopes are attracted on plates by an electric field, they are condensed and collected on these plates. The very high selectivity of enrichment technologies by laser, which are quite new, pave the way for compact and modular plants, which will consume little energy. Accordingly their production cost will be very low. So a new process could take a significant part of the uranium enrichment market after 2010. Even if the multinational EURODIF gaseous diffusion plant is modern and performing, it will be necessary to strengthen the French industry of uranium enrichment to maintain or improve its competitive position on the world market. This could be achieved by smoothly replacing EURODIF by a high performance laser plant. This is the common goal of CEA and COGEMA: all the efforts are concentrated on SILVA, the qualities of which (high selectivity, separation in one single step) have been demonstrated in the facilities of Saclay and Pierrelatte. 400 researchers and technicians are involved, as well as many industrial firms. The budget is equally by CEA and COGEMA through a cooperation agreement. The program includes: a phase of scientific and technical research, which has been highlighted in 1997-1998 by a demonstration of feasibility of the process; a phase of technological development, with

  13. 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)

  14. Leachability of bituminized radioactive waste. Literature survey

    International Nuclear Information System (INIS)

    Akimoto, Toshiyuki; Nakayama, Shinichi; Iida, Yoshihisa; Nagano, Tetsushi

    1999-02-01

    Bituminized radioactive waste that will be returned from COGEMA, France is planned to be disposed of in deep geologic repository in Japan. Data on leachability of radionuclides from bituminized waste are required for the performance assessment of the disposal. We made a literature survey on bitumen and bituminized radioactive waste, placing emphasis on leach tests and leach data in terms of geologic disposal. This survey revealed that reliable leach data on transuranium elements and data obtained under reducing conditions that is characteristic to deep underground are lacking. (author). 64 refs

  15. Food inquiry of Pierrelatte: study of the food consumptions of the populations near the site of Pierrelatte-Tricastin: Daily rations and auto consumption

    International Nuclear Information System (INIS)

    2005-01-01

    In the framework of a partnership between Cogema and I.R.S.N. a study of food consumption of populations living near the site of Pierrelatte-Tricastin has been realised in the commune of Bollene. This inquiry took place in four steps in order to describe correctly the seasons evolutions of the food consumption and auto consumption of families. The aim of this present report is to present the comparison realised of data issued from the inquiry of Pierrelatte to these ones from other recent food inquiries. (N.C.)

  16. Food inquiry of Pierrelatte: study of the food consumptions of the populations near the site of Pierrelatte-Tricastin: Daily rations and auto consumption; Enquete alimentaire de Pierrelatte: etude des consommations alimentaires des populations a proximite du site Pierrelatte-Tricastin: rations journalieres et autoconsommation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    In the framework of a partnership between Cogema and I.R.S.N. a study of food consumption of populations living near the site of Pierrelatte-Tricastin has been realised in the commune of Bollene. This inquiry took place in four steps in order to describe correctly the seasons evolutions of the food consumption and auto consumption of families. The aim of this present report is to present the comparison realised of data issued from the inquiry of Pierrelatte to these ones from other recent food inquiries. (N.C.)

  17. 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)

  18. It's safety first on N-fuel carrier ship

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The 3 000t deadweight ship to carry irradiated nuclear fuel ordered recently from Appledore Shipbuilders will be one of the most sophisticated ships built at the firm's modern and totally-enclosed north Devon yard. The ship will be used to carry irradiated nuclear fuel from Japan to be reprocessed at British Nuclear Fuels site at Sellafield and at the Cogema plant in northern France. It has been designed to conform to the most exacting requirements of Pacific Nuclear Transport and will incorporate every safeguard for the shipment of irradiated nuclear fuels

  19. The CEA-industrie Group. Report for 1986

    International Nuclear Information System (INIS)

    1987-01-01

    From the end of 1983, the whole affiliates and participations of CEA are hept by CEA-industry. The group activity is principally in the nuclear field. Cogema and the whole fuel cycle, construction, maintenance, improvement of nuclear power plants, research reactors and naval propulsion boilers and the sector Power plants and nuclear services (Framatome, Technicatome, Intercontrole, Stmi, principally). A non-nuclear sector comes from new techniques or activities developed for the nuclear needs: computer science (CISI), biomedical field (ORIS-industrie), different activities such as ultrafiltration or robotics-productics [fr

  20. 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

  1. Andra 1997 activity report

    International Nuclear Information System (INIS)

    1998-07-01

    This activity report comprises two parts. The first part describes the missions and activities of the ANDRA (the French agency for the management of radioactive wastes): quality control of wastes produced by EdF, CEA, Cogema and the 1100 other small producers, design, construction and management of storage centres, anticipation and development of new management solutions, research and evaluation studies on deep storage facilities, inventory and control of all radioactive materials present in the French territory. The second part is a presentation of financial data. (J.S.)

  2. Animals exposed to radon

    International Nuclear Information System (INIS)

    Masse, R.; Morin, M.; Lafuma, J.; Morlier, J.P.; Chameaud, J.; Bredon, P.

    1992-01-01

    'There is sufficient evidence that 222 Rn is a carcinogen in animals': this statement was important for the classification of radon as carcinogenic to man, outside of uranium mine atmospheres, clearly identified by epidemiology as causing lung cancer. Since recent reviews of animal experiments have been given by NCRP and by IARC, this review will be mainly limited to the recent results which came from two laboratories in the last 20 years. Battelle Pacific Northwest Laboratories (PNL), USA, and COGEMA Laboratoire de Pathologie Professionnelle (LPP) France. (author)

  3. Lessons learned from MELOX plant operation and support to design of new MOX fuel fabrication plants

    International Nuclear Information System (INIS)

    Tourre, Joel; Gattegno, Robert; Guay, Philippe; Bariteau, Jean-Pierre

    2005-01-01

    AREVA is participating in the design of the US MOX Fuel Fabrication Facility (MFFF). To support this project and allow the U.S. Department of Energy (DOE) client to reap full benefit from the MELOX operating experience, AREVA, through COGEMA and its engineering subsidiary SGN have implemented a rigorous process to prudently apply MELOX Lessons Learned to the MFFF design. This paper describes the Lessons Learned process, how the process supports the advancement of fuel fabrication technology and, how the results of the process are benefiting the client. (author)

  4. Cost effectiveness of robotics and remote tooling for occupational risk reduction at a nuclear fuel fabrication facility

    Energy Technology Data Exchange (ETDEWEB)

    Lochard, Jacques

    1989-08-01

    This case study, related to the design stage of a fuel fabrication facility, presents the evaluation of alternative options to manipulate mixed oxide fuel rods in a quality control shop. It is based on a study performed in the framework of the 'MELOX project' developed by COGEMA in France. The methodology for evaluating robotic actions is resulting from a research work part funded by the IAEA under the co-ordinated research programme on 'Comparison of cost-effectiveness of risk reduction among different energy systems', and by the commission of the European Communities under the research and training programme on radiation protection.

  5. Joint declaration on co-operation in the field of the peaceful use of nuclear energy between France and the Federal Republic of Germany

    International Nuclear Information System (INIS)

    1989-06-01

    This Declaration follows upon the signing of a Protocol of intent on 3 April 1989 by VEBA, the major energy consortium in the Federal Republic of Germany supplying nuclear power, and COGEMA, the French State-owned nuclear fuel company and aims to provide a broad framework for co-operation between the two countries. The Declaration, in particular, covers co-operation in the fields of reprocessing, production of MOX fuel (mixed oxide fuel), uranium enrichment, nuclear reactors, information relating to nuclear installations, transport of nuclear material [fr

  6. Maintenance of the packagings used for the transport of spent fuel

    International Nuclear Information System (INIS)

    Lazarevitch, S.; Cooke, B.

    1987-01-01

    Regular maintenance of packagings used for the transport of spent fuel has been carried out in Europe for the past three years. The three companies involved in this kind of transport (Cogema, Nuclear Transport and Pacific Nuclear Transport) have agreed on a common policy for these operations and, in practice, perform the maintenance work at a special facility (AMEC) at the La Hague reprocessing plant in France. This facility was erected in 1983, and commissioned in January 1984. The paper deals with the typical maintenance operations at the AMEC facility, the principles of control applied during maintenance, maintenance experience and future development and prospects. (author)

  7. Studies on the long-term characteristics of HLW glass under ultimate storage conditions

    International Nuclear Information System (INIS)

    Roggendorf, H.; Conradt, R.; Ostertag, R.

    1987-01-01

    This interim report deals with first results of corrosion investigations of HLW simulation glass (COGEMA glass SON 68) in quinary salt solutions of different concentrations; the aim of these investigations was to find out about the corrosion mechanism at the surface of the glass and the quantitative registration of the corrosion products. It became obvious that the surface layers developed can be easily removed and that a determination of weight losses becomes possible thereby. The corrosion rates for a test period of 30 days were determined. (RB) [de

  8. Specific transport and storage solutions: Waste management facing current and future stakes of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Deniau, Helene; Gagner, Laurent; Gendreau, Francoise; Presta, Anne

    2006-01-01

    With major projects ongoing or being planned, and also with the daily management of radioactive waste from nuclear facilities, the role of transport and/or storage packaging has been often overlooked. Indeed, the packaging development process and transport solutions implemented are a key part of the waste management challenge: protection of people and environment. During over four decades, the AREVA Group has developed a complete and coherent system for the transport of waste produced by nuclear industries. The transport solutions integrate the factors to consider, as industrial transportation needs, various waste forms, associated hazards and current regulations. Thus, COGEMA LOGISTICS has designed, licensed and manufactured a large number of different transport, storage and dual purpose cask models for residues and all kinds of radioactive wastes. The present paper proposes to illustrate how a company acting both as a cask designer and a carrier is key to the waste management issue and how it can support the waste management policy of nuclear producers through their operational choices. We will focus on the COGEMA LOGISTICS technical solutions implemented to guarantee safe and secure transportation and storage solutions. We will describe different aspects of the cask design process, insisting on how it enables to fulfill both customer needs and regulation requirements. We will also mention the associated services developed by the AREVA Business Unit Logistics (COGEMA LOGISTICS, TRANSNUCLEAR, MAINCO, and LEMARECHAL CELESTIN) in order to manage transportation of liquid and solid waste towards interim or final storage sites. The paper has the following contents: About radioactive waste; - Radioactive waste classification; - High level activity waste and long-lived intermediate level waste; - Long-lived low level waste; - Short-lived low- and intermediate level waste; - Very low level waste; - The radioactive waste in nuclear fuel cycle; - Packaging design and

  9. The Pierrelatte's military factories dismantling

    International Nuclear Information System (INIS)

    Bourrelier, P.; Kassel, Ch.

    1999-01-01

    The site of Pierrelatte in France, receives since 1958 gaseous diffusion plants assigned to the uranium enrichment for military uses. Since 1996 Cogema implements, by order of the Cea, a dismantling operation of the site. The operation which will begin in 2000, is going to last ten years. This project shows difficulties that make it innovative. Its originality, the planning, the risks, the program progressing and the regulation aspects are detailed in this paper. Beyond the complicated technical operations, the wastes management is of primary importance for the good development of the operations. (A.L.B.)

  10. Volume reduction of low- and medium-level waste by incineration/calcination

    International Nuclear Information System (INIS)

    Buzonniere, A. de; Gauthey, J.C.

    1993-01-01

    Nuclear installations generate large quantities of low- and medium-level radwaste. This waste comes from various installations in the fuel cycle, reactor operation, research institute, hospitals, nuclear plate dismantling, etc.. TECHNICATOME did the project development work for the incineration plant of PIERRELATE (France) on behalf of COGEMA (Compagnie Generale des d'Etudes Technique). This plant has been in active service since November 1987. In addition, TECHNICATOME was in charge of the incinerator by a turnkey contract. This incinerator was commissioned in 1992. For a number of years, TECHNICATOME has been examining, developing and producing incineration and drying/calcination installations. They are used for precessing low- and medium-level radwaste

  11. Status of geological studies undertaken in France on the Oklo deposit since the Libreville Symposium

    International Nuclear Information System (INIS)

    Weber, F.

    1978-01-01

    The questions posed since the Libreville symposium can be grouped under four headings: origin of the deposits and the over-concentrations; degree of burial reached by the series; temperatures attained during the reactions, and effects of the reactions; perturbations subsequent to the reactions. These questions have been the subject of multidisciplinary investigations, including conventional petrographic and mineralogical investigations (Cogema, Fontenay-aux-Roses and the Centre for Sedimentology and Geochemistry of the Surface, Strasbourg), a study of fluid inclusions (Centre for Petrographic and Geochemical Research, Nancy), studies of organic material (French Institute of Petroleum, Rueil, and Cerchar, Verneuil-en-Halatte) and a study of fission traces (Rene Barnas Laboratory, Orsay). (author)

  12. Areva in Niger

    International Nuclear Information System (INIS)

    2005-02-01

    Niger is the second poorest country in the world but it has natural resources underground in the form of uranium ores deposits. This uranium is currently mined by two companies incorporated under Nigerian law: Somair and Cominak, operated by the principal shareholder Areva (through its subsidiary Cogema). After a presentation of Somair and Cominak key figures, this document details the working conditions and radiological protection, the environmentally friendly operations, the production traceability, the local economic development, the strengthening of the health care system and the development of the infrastructure. (A.L.B.)

  13. Importance of low-level radioactive wastes in dismantling strategy in CEA (FRANCE)

    International Nuclear Information System (INIS)

    Lafaille, C.

    1991-01-01

    This paper describes the advance used in C.E.A. to realize dismantling operations in the best technical and economical conditions. Particularly, for low-level radioactive waste management CEA's advance defines, first, the final destination of dismantling materials: - recycling in public lands for level activity inferior to 1 Bq/g; directly or after transformation (melting, calcination, extrusion) - storage in a ground disposal, after compacting, encapsulation or drumming. Two examples are given: - Marcoule G2 - G3 reactor dismantling - Gaseous diffusion plants demolition (COGEMA Pierrelatte)

  14. About the interest of an agreement for a european passport for workers in european regulated nuclear installations

    International Nuclear Information System (INIS)

    Gorin, M.; Bailloeuil, C.; Petrequin, A.

    2002-01-01

    The European directive 96/29 applicable to EU member states is, or will be transposed in each country according to national conditions which could prove to be more restrictive than the demands of the directive. Additionally, specific organisations in each country, reinforce the disparities where radioprotection, and medical and dosimetric follow-up are concerned. In April 2001, on the initiative of a group of French company medical officers (EDF CEA COGEMA), a meeting with company medical officers from various member states of the EEC: Great Britain, Italy, Spain, Belgium, Germany, was organised in order to bring to attention the issue of the movement of contract workers in European regulated nuclear installations

  15. French and International experience on the dialogue around industrial sites; Experience francaise et internationales sur la concertation autour des sites industriels

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, Th. [Centre d' Etude sur l' Evaluation de la Protection dans le Domaine Nucleaire, CEPN, 92 - Fontenay aux Roses (France); Heriard Dubreuil, G.; Gadbois, S. [Mutadis, 94 - Vitry (France); Oudiz, A. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Remond Gouilloud, M. [Paris-6 Univ. Sorbonne, 75 (France)

    2002-12-15

    This report presents the results of a research work about 'the stakes of the dialogue around the follow up of nuclear and non nuclear industrial installations'. It used the experience of the North Cotentin radioecology group where expertise has been implemented in order to evaluate the impact on health of the releases of the Cogema La Hague plant. This report is the fruit of an interdisciplinary group ( experts of activities with risks, radiation protection, regulation in environment). (N.C.)

  16. Nuclear fuel supply: East European challenges

    International Nuclear Information System (INIS)

    Braatz, U.; Dibbert, H.J.

    1993-01-01

    Since the mid-eighties the annual production of natural uranium in the Western world has been below reactor requirements. As a consequence of the penetration of the Western market by Eastern vendors of natural uranium and processing services, the declining trend of the production of natural uranium in the West continued in 1991, production reaching the lowest level since 1976 at 26,000 t of uranium. One point to be mentioned in the structural change of the uranium industry is the takeovers of numerous uranium mining and dressing plants in the United States by other firms, and the growing importance of Cogema in the market. (orig.) [de

  17. Environmental and sanitary evaluation of electro-nuclear sites: methodological research and application to prospective scenarios

    International Nuclear Information System (INIS)

    2004-12-01

    In the framework of the radioactive wastes disposal of the law of 1991, an exchange forum constituted by ANDRA, CEA, COGEMA, EdF, Framatome-ANP and IRSN implemented an environmental and sanitary evaluation of the different methods of radioactive wastes management. This report presents the six studies scenarios, the proposed methodology, the application to the six scenarios and the analysis of the results which showed the efficiency of the different recycling options towards the electronuclear cycle impacts limitation, and a technical conclusion illustrated by improvement possibilities of the methodology. (A.L.B.)

  18. Decontamination by excimer laser

    International Nuclear Information System (INIS)

    2001-01-01

    The process developed in collaboration with the C.N.R.S. has reached the industrial stage. The transport by optical fibre beam has been perfected and allows to work from a distance of 20 m from the source. Demonstration has been made with a laser of a 500 watt power which allows a 5 to 10 m 2 /hour etching efficiency. This process is in the course of qualification in collaboration with the different organisations: C.E.A., COGEMA and E.D.F. This qualification concerns 25 different materials and zircaloy fuel claddings. (author)

  19. Experimental microstructures MOX fuels elaboration

    International Nuclear Information System (INIS)

    Gotta, M.J.; Dubois, S.; Lechelle, J.; Sornay, P.

    2000-01-01

    In order to propose a new MOX fuel, owning higher combustion rate, studies are realized at the CEA in collaboration with Cogema, EDF and Framatome. New microstructures of MOX are looked for around two approaches: the grains size and the plutonium distribution. These approaches are presented and discussed in this paper. The first one develops big grains microstructures obtained, either with anionic (sulfur), or cationic (Cr 2 O 3 ) additives. The second one concerns the CER-CER type composite microstructures. (A.L.B.)

  20. Uranium resources

    International Nuclear Information System (INIS)

    Gangloff, A.

    1978-01-01

    It is first indicated how to evaluate the mining resources as a function of the cost of production and the degree of certainty in the knowledge of the deposit. A table is given of the world resources (at the beginning 1977) and resources and reserves are compared. There is a concordance between requirements and possible production until 1990. The case of France is examined: known reserves, present and future prospection, present production (In 1978 2200 T of U metal will be produced from 3 French processing plants), production coming from Cogema. A total production of 2000 T in 1980 and 10.000 in 1985 is expected [fr

  1. 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)

  2. Transport of Powders through Rotary Kilns: Experimental Study and Modelling

    OpenAIRE

    Debacq , Marie; Hartmann , Didier; Houzelot , Jean-Leon; Ablitzer , Denis

    1999-01-01

    International audience; During the nuclear fuel cycle, uranium as hexafluoride is enriched by means of gaseous-diffusion process. The depleted UF6 resulting from the isotope separation stage is converted into U3O8 to enable its safe storage (conversion carried out by COGEMA). The UF6 -> UO2 conversion is performed in four identical plants : UF6 is hydrolysed in the gaseous phase through a vertical reactor, then the UO2F2 powder formed is pyrohydrolysed into U3O8 powder through a lightly incli...

  3. Cost effectiveness of robotics and remote tooling for occupational risk reduction at a nuclear fuel fabrication facility

    International Nuclear Information System (INIS)

    Lochard, Jacques

    1989-01-01

    This case study, related to the design stage of a fuel fabrication facility, presents the evaluation of alternative options to manipulate mixed oxide fuel rods in a quality control shop. It is based on a study performed in the framework of the 'MELOX project' developed by COGEMA in France. The methodology for evaluating robotic actions is resulting from a research work part funded by the IAEA under the co-ordinated research programme on 'Comparison of cost-effectiveness of risk reduction among different energy systems', and by the commission of the European Communities under the research and training programme on radiation protection

  4. French fission products experiments performed in Cadarache and Valduc. Results comparison

    International Nuclear Information System (INIS)

    Anno, Jacques; Barreau, Anne; Hudelot, Jean Pascal; Girault, Emmanuel; Fouillaud, Patrick; Toubon, Herve

    2003-01-01

    Cofunded by Cogema, two complementary experimental programmes on burn up credit (BUC) related to fission products (FPs) are performed by CEA and IRSN at Cadarache and Valduc. After shortly recalling the main characteristics of each experiment, a first comparison of some results is presented, especially the energy range in which most part of cross section absorption are qualified. Both experiments exhibit great quality and accurate results, giving a high degree of confidence to the whole experimental French process of qualification devoted to BUC. (author)

  5. 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

  6. Calculation scheme for boiling water reactors cores; Methode de calcul des coeurs de reacteurs a eau bouillante par le systeme saphyr

    Energy Technology Data Exchange (ETDEWEB)

    Marsault, Ph [CEA Cadarache, Dept. d' Etudes des Reacteurs (DER/SERSI), 13 - Saint-Paul-lez-Durance (France); Nicolas, A; Lenain, R; Richebois, E; Royer, E; Caruge, D [CEA Saclay, Dept. de Mecanique et de Technologie (DMT/SERMA), 91 - Gif-sur-Yvette (France); Blaise, P [CEA Cadarache, Dept. d' Etudes des Reacteurs (DER/SPEX), 13 - Saint-Paul-lez-Durance (France); Gastaldi, B; Delpech, M [CEA Cadarache, Dept. d' Etudes des Reacteurs (DER/SPRC), 13 - Saint-Paul-lez-Durance (France)

    1999-07-01

    Boiling Water Reactors represent one third of the world's reactors. They are presently evolving towards greater simplification, allowing a reduction in the costs of operation, improved safety and a relative flexibility in their capacity to accommodate 100% MOX cores. The CEA, in a combined effort with its partners, the COGEMA and the EDF, would like to assess the interest of this reactor type, especially on this last point. A definition program and subsequent qualification of the calculation scheme have been undertaken. We are presenting here the specific features inherent in the calculation of these reactors, in comparison to PWRs, as well as the first results of the program. (authors)

  7. The nuclear industry in France

    International Nuclear Information System (INIS)

    Degot, D.

    1981-02-01

    The French nuclear industry is organized around the following main participants: - The E.D.F., owners, industrial architects and operators of the power stations, - The C.E.A. for research and development, with its subsidiary the COGEMA, who deal with all problems involving the fuel cycle, - The Industry with FRAMATOME in charge of the manufacture of nuclear boilers, and ALSTHOM-ATLANTIQUE in charge of turbo-generator units. This paper deals with the activities covered by FRAMATOME and its industrial environment. The standardization of PWR power stations built by French industry and the possibilities of exporting PWR power stations are given a brief mention [fr

  8. 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

  9. Procedures and techniques for the management of experimental and exotic fuel from research and test reactors in France

    International Nuclear Information System (INIS)

    Raisonnier, D.

    1999-01-01

    Since 1995, the Commissariat a I'Energie Atomique CEA has implemented a three point fuel management plan. One of the three points, the removal and the reprocessing of a wide range of spent fuels stored in different facilities in Saclay, Grenoble and Cadarache nuclear research centers, is described. The COGEMA Group has developed and implemented a comprehensive set of solutions for the management of research reactor and exotic fuels. It includes transport casks, storage casks or interim storage facilities at the reactor site, or at a centralized interim storage, as well as spent fuel reprocessing, material recycling and waste conditioning. (author)

  10. The McClean Lake uranium project

    International Nuclear Information System (INIS)

    Blaise, J.R.

    2001-01-01

    The McClean Lake Uranium Project, located in the northern part of Saskatchewan, consists of five uranium deposits, Jeb - Sue A - Sue B - Sue C - McClean, scattered in three different locations on the mineral lease. On 16 March 1995, COGEMA Resources Inc and its partners, Denison Mines Ltd and OURD (Canada) Co Ltd, made the formal decision to develop the McClean Lake Project. Construction of the mine and mill started during summer 1995 and should be finished by mid 1997. Mining of the first deposit, Jeb started in 1996, ore being currently mined. The start of the yellowcake production is scheduled to start this fall. (author)

  11. The Cogemagazine reviews. The rehabilitation of mining sites in France; Les cahiers de Cogemagazine. Le reamenagement des sites miniers en France

    Energy Technology Data Exchange (ETDEWEB)

    Loriot, O.; Bof, M.; Villeneuve, A

    1998-02-01

    The French uranium mines are progressively closing down. After a mining division has closed down, the main objectives of the Cogema group are: ensuring the long-term safety and healthiness of the site, reducing the residual impacts, preventing any abusive intrusion, reducing the surface of land submitted to right-of-way, encouraging the reconversion of the site, and succeeding in the integration of the site in the landscape in agreement with the local authorities. This brochure presents the strategy followed by Cogema for the rehabilitation of his sites: the French mining concessions and the uranium extraction and processing techniques, the storage of tailings and processing residues, the environment protection and the respect of regulation (environmental surveillance, working groups, administrative procedures and regulatory texts, impact studies...), the backfilling and safety of underground mines, the cost studies for the rehabilitation of open cast mines, the dismantling of factories, the confinement of residues and the revegetation, the continuous monitoring of the rehabilitated sites (water, atmosphere, food..). (J.S.)

  12. Return of vitrified wastes from France to Japan

    International Nuclear Information System (INIS)

    2000-01-01

    The radioactive wastes resulting from the burnup of nuclear fuels in nuclear reactors represent 3 to 5% of the spent fuel. These wastes cannot be reused nor recycled and thus are vitrified after reprocessing. Japanese power companies have signed contracts with Cogema in France and BNFL in the UK for the reprocessing of their spent fuels. Then, the ultimate reprocessed wastes are sent back to Japan for storage. This information dossier takes stock of different questions relative to the transport of the vitrified wastes from France to Japan: why France sends back containers of vitrified wastes to Japan? What is a vitrified wastes container made of? How containers are transported? What is the regulatory frame applicable to these transports? Which safety measures are taken during transport? Which physical protection is applied? Which temporary storage facilities are used before and after transportation? How is performed the ultimate storage of wastes in Japan? Which quality and safety warranties are taken? Which emergency plans and exercises are provided? What are the applicable civil liability regimes? And what kind of information is given to the public about these transports. Some general information about energy and nuclear power worldwide, energy and environment, radioactivity, BNFL, Cogema and ORC is given in appendixes. (J.S.)

  13. Feeding the nuclear fuel cycle with a long term view; AREVA's front-end business units, uranium mining, UF6 conversion and isotopic enrichment

    International Nuclear Information System (INIS)

    Capus, G.A.P.; Autegert, R.

    2005-01-01

    As a leading provider of technological solutions for nuclear power generation and electricity transmission, the AREVA group has the unique capability of offering a fully integrated fuel supply, when requested by its customers. At the core of the AREVA group, COGEMA Front End Division is an essential part of the overall fuel supply chain. Composed of three Business Units and gathering several subsidiaries and joint 'ventures, this division enjoys several leading positions as shown by its market shares and historical production records. Current Uranium market evolutions put the natural uranium supply under focus. The uranium conversion segment also recently revealed some concerning evolutions. And no doubt, the market pressure will soon be directed also at the enrichment segment. Looking towards the long term, AREVA strongly believes that a nuclear power renewal is needed, especially to help limiting green house effect gas release. Therefore, to address future supplies needed to fuel the existing fleet of nuclear power plants, but also new ones, the AREVA group is planning very significant investments to build new facilities in all the three front-end market segments. As far as uranium mining is concerned, these new mines will be based upon uranium reserves of outstanding quality. As for uranium conversion and enrichment, two large projects will be based on the most advanced technologies. This paper is aimed at recalling COGEMA Front End Division experience, the current status of its plants and operating entities and will provide a detailed overview of its major projects. (authors)

  14. Key points for the design of Mox facilities

    International Nuclear Information System (INIS)

    Ducroux, R.; Gaiffe, L.; Dumond, S.; Cret, L.

    1998-01-01

    The design of a MOX fuel fabrication facility involves specific technical difficulties: - Process aspects: for example, its is necessary to meet the stringent requirements on the end products, while handling large quantities of powders and pellets; - Safety aspects: for example, containment of radioactive materials requires to use gloveboxes, to design process equipment so as to limit dispersion to the gloveboxes and to use systems for dust collection. - Technological aspects: for example, it is necessary to take into account maintenance early in the design, in order to lower the operation costs and lower the dose to the personnel. - Quality control and information systems: for example, it is necessary to be able to trace all the different products (powder lots, pellets, rods, assemblies). The design methods and organization set-up by COGEMA enables to master these technical difficulties during the different design steps and to obtain a MOX fabrication facility at the best performance versus cost compromise. These design methods rely mainly on: - taking into account all the different above mentioned constraints from the very beginning of the design process (by using the know-how resulting from experience feed-back, and also specific design tools developed by COGEMA and SGN); - launching a technical development and testing program at the beginning of the project and incorporating its results in the course of the design. (author)

  15. LLW/Il conditioning for transportation, storage and disposal

    International Nuclear Information System (INIS)

    Pech, R.; Chevalier, Ph.

    2000-01-01

    In France, Sogefibre (Cogema subsidiary) has developed original containers adapted to the conditioning of LLW and ILW and assuring integrity of the waste form over long period of time. These containers have been designed according to the following criteria, derived from Andra's requirement for the surface disposal: Mechanical strength, resistance to microcracking, Radioactive containment and long life: 300 years minimum. Choice of formulation for the concrete as well as selection of raw materials have been optimised in this objective. Sizes and shapes of Fiber Reinforced Concrete Containers (FRCC) have been developed in relation with handling means of Cogema La Hague facilities for automatized operations. Experience gained after nearly 10 years and 40000 FRCC produced shows that choices have been right and properties of FRCC effectively useful. The paper also recalls mechanical and containment properties and the durability assessment recently updated thanks to results of computer modelling. Degradation phenomenon of the Blended Ternary Cement (clinker, slag, ash) used in FRCC is described and the model presented. (authors)

  16. 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)

  17. 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.)

  18. 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

  19. Return of vitrified wastes from France to Japan; Retour des residus vitrifies de France au Japon

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The radioactive wastes resulting from the burnup of nuclear fuels in nuclear reactors represent 3 to 5% of the spent fuel. These wastes cannot be reused nor recycled and thus are vitrified after reprocessing. Japanese power companies have signed contracts with Cogema in France and BNFL in the UK for the reprocessing of their spent fuels. Then, the ultimate reprocessed wastes are sent back to Japan for storage. This information dossier takes stock of different questions relative to the transport of the vitrified wastes from France to Japan: why France sends back containers of vitrified wastes to Japan? What is a vitrified wastes container made of? How containers are transported? What is the regulatory frame applicable to these transports? Which safety measures are taken during transport? Which physical protection is applied? Which temporary storage facilities are used before and after transportation? How is performed the ultimate storage of wastes in Japan? Which quality and safety warranties are taken? Which emergency plans and exercises are provided? What are the applicable civil liability regimes? And what kind of information is given to the public about these transports. Some general information about energy and nuclear power worldwide, energy and environment, radioactivity, BNFL, Cogema and ORC is given in appendixes. (J.S.)

  20. How Packaging Fleet Renewal Fits French CEA Programs

    International Nuclear Information System (INIS)

    Dumesnil, J.; Malvache, P.; Hugon, F.C.; Sollacaro, M.

    2006-01-01

    CEA's (French Atomic Energy Agency) packaging fleet is dedicated to transportation of test irradiated fuels, of research reactors fuels, of navy propulsion fuels, and of waste coming from and to nuclear plants or facilities. This fleet encompasses more than 30 types of casks ranging from 5 to 30 tons, with either recent designs or other dating back to the seventies. A study has been launched in order to perform a global analysis of the life expectancy of the existing CEA and COGEMA Logistics cask fleets with respect to a 2015 target, in order to anticipate its renewal, while limiting the number of type of cask. Key elements like periodical evolutions of design and transport regulations, lessons learnt of existing casks (design, approval and extensions, operational feedback, maintenance and dismantling) are taken into account in order to ensure compliance and availability of the fleet. Moreover, from design to cask delivery, including regulatory tests, safety analysis report/ CoC, and manufacturing, 3 to 5 years is needed. Therefore cask development should be taken into account earlier of invest and research's programs. The paper will address the current life expectancy study of CEA and COGEMA Logistics packaging fleet, based on lessons learnt and regulation evolution and on general R and D plans by user facilities. It will show how a comprehensive optimized fleet is made available to CEA and other customers. Such a fleet combines optimized investment and uses, thus entailing synergies for well-mastered costs of transports. (authors)

  1. The Cogemagazine reviews. The rehabilitation of mining sites in France

    International Nuclear Information System (INIS)

    Loriot, O.; Bof, M.; Villeneuve, A.

    1998-02-01

    The French uranium mines are progressively closing down. After a mining division has closed down, the main objectives of the Cogema group are: ensuring the long-term safety and healthiness of the site, reducing the residual impacts, preventing any abusive intrusion, reducing the surface of land submitted to right-of-way, encouraging the reconversion of the site, and succeeding in the integration of the site in the landscape in agreement with the local authorities. This brochure presents the strategy followed by Cogema for the rehabilitation of his sites: the French mining concessions and the uranium extraction and processing techniques, the storage of tailings and processing residues, the environment protection and the respect of regulation (environmental surveillance, working groups, administrative procedures and regulatory texts, impact studies...), the backfilling and safety of underground mines, the cost studies for the rehabilitation of open cast mines, the dismantling of factories, the confinement of residues and the revegetation, the continuous monitoring of the rehabilitated sites (water, atmosphere, food..). (J.S.)

  2. The French post irradiation examination database for the validation of depletion calculation tools

    International Nuclear Information System (INIS)

    Roque, Benedicte; Marimbeau, Pierre; Bioux, Philippe; Toubon, Herve; Daudin, Lucien

    2003-01-01

    This paper presents the experimental programmes conducted in France by the Commissariat a l'Energie Atomique (CEA) in order to validate spent fuel inventory calculations for core studies as well as fuel cycle studies. This large experimental programme was obtained in collaboration with our French partners, Electricite de France (EDF), FRAMATOME-ANP and COGEMA. The experimental data are based on chemical analysis measurements from fuel rod cuts irradiated in French reactors for PWR-UOx and MOx fuels, then dissolved in CEA laboratories, and from full assembly dissolutions at the COGEMA/La Hague reprocessing plants for UOx fuels. This enables us to cover a large range of UOx fuels with various enrichments in 235 U, 3.1% to 4.5%, associated with burnups from 10 GWd/t to 60 GWd/t. Recently, MOx fuels have also been investigated, with an initial Pu amount in the central zone of 5.6% and a maximum burnup of 45 GWd/t. Uranium, Plutonium, Americium, Curium isotopes and some fission products were analysed. Furthermore, Fission Products involved in Burn up Credit studies were measured. The experimental database contains also data for Boiling Water Reactor (BWR) with irradiated samples of BWR 9x9 and full BWR assemblies dissolutions. Furthermore some data exist for Fast Breeder Reactor (FBR) with small samples irradiated in the PHENIX reactor. An overview of ongoing programmes is also presented. (author)

  3. Measured tritium in groundwater related to atmospheric releases from the Marcoule nuclear site

    International Nuclear Information System (INIS)

    Levy, F.; Clech, A.; Crochet, P.

    1996-01-01

    Tritium is released into the atmosphere during normal operation from the industrial facilities operated by COGEMA at Marcoule; over a 1 5-year period covered by this study (1979-1994) the quantities ranged from 4940 to 520 TBq·yr -1 . Atmospheric release in rainy weather results in tritium migration into the ground water by a series of mechanisms associated with the water cycle. COGEMA monitors the ground water by means of bore holes. Atmospheric monitoring is also routinely performed; data on the tritium activity concentration in the air and rainwater are available for the same time period. A simplified observation suggests a relation between the atmospheric tritium release and the ground water radioactivity. In 1994, the activity ranged from 100 to 200 Bq·l -1 in the boreholes located 1 km and 2 km downwind from the point of release, diminishing with the distance to less than 20 Bq·l -1 at about 3 km. The authors attempted to model two types of transfers: atmospheric transfer from the release chimney to the borehole, and transfer in the alluvial ground water. The aquifer comprises the alluvial deposits forming the Codolet plain extending to the south of Marcoule, downwind from the point of atmospheric tritium release. The hydrogeology of the entire Marcoule site has been described in previous studies by the French bureau of geological and mineralogical research (BRGM) and ANTEA. (author)

  4. 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)

  5. FAKIR: a user-friendly standard for decay heat and activity calculation of LWR fuel

    International Nuclear Information System (INIS)

    Pretesacque, P.; Nimal, J.C.; Huynh, T.D.; Zachar, M.

    1993-01-01

    The shipping casks owned by the transporters and the unloading and storage facilities are subjected by their design safety report to decay heat and activity limits. It is the responsibility of the consignor or the consignee to check the compliance of the fuel assemblies to the shipped or stored with regard to these limiting safety parameters. Considering the diversity of the parties involved in the transport and storage cycle, a standardization has become necessary. This has been achieved by the FAKIR code. The FAKIR development started in 1984 in collaboration between COGEMA, CEA-SERMA and NTL. Its main specifications were to be a user-friendly code, to use the contractual data given in the COGEMA transport and reprocessing sheet 1 as input, and to over-estimate decay heat and activity. Originally based on computerizable standards such as ANSI or USNRC, the FAKIR equations and data libraries are now based on the fully qualified PEPIN/APOLLO calculation codes. FAKIR is applicable to all patterns of irradiation histories, with burn up from 1000 MWd/TeU to 70.000 MWd/TeU and cooling times from 1 second to 100 years. (J.P.N.)

  6. Criticality evaluation of BWR MOX fuel transport packages using average Pu content

    International Nuclear Information System (INIS)

    Mattera, C.; Martinotti, B.

    2004-01-01

    Currently in France, criticality studies in transport configurations for Boiling Water Reactor Mixed Oxide fuel assemblies are based on conservative hypothesis assuming that all rods (Mixed Oxide (Uranium and Plutonium), Uranium Oxide, Uranium and Gadolinium Oxide rods) are Mixed Oxide rods with the same Plutonium-content, corresponding to the maximum value. In that way, the real heterogeneous mapping of the assembly is masked and covered by a homogeneous Plutonium-content assembly, enriched at the maximum value. As this calculation hypothesis is extremely conservative, COGEMA LOGISTICS has studied a new calculation method based on the average Plutonium-content in the criticality studies. The use of the average Plutonium-content instead of the real Plutonium-content profiles provides a highest reactivity value that makes it globally conservative. This method can be applied for all Boiling Water Reactor Mixed Oxide complete fuel assemblies of type 8 x 8, 9 x 9 and 10 x 10 which Plutonium-content in mass weight does not exceed 15%; it provides advantages which are discussed in our approach. With this new method, for the same package reactivity, the Pu-content allowed in the package design approval can be higher. The COGEMA LOGISTICS' new method allows, at the design stage, to optimise the basket, materials or geometry for higher payload, keeping the same reactivity

  7. 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)

  8. CEA and its radioactive wastes

    International Nuclear Information System (INIS)

    Marano, S.

    1999-01-01

    CEA annually produces about 3500 tons of radioactive wastes in its 43 basic nuclear installations. CEA ranks third behind EDF and Cogema. Low-level wastes (A wastes) are sent to ANDRA (national agency for the management of nuclear wastes)whereas medium-level wastes (B wastes) are stored by CEA itself. CEA has checked off its storing places and has set up an installation Cedra to process and store ancient and new nuclear wastes. 3 other installations are planned to operate within 6 years: Agate (Cadarache) will treat liquid effluents, Stella (Saclay) will process liquid wastes that are beta or gamma emitters, and Atena (Marcoule) will treat and store radioactive sodium coming from Phenix reactor and IPSN laboratories. The use of plasma torch for vitrifying wastes is detailed, the management of all the nuclear wastes produced by CEA laboratories and installations is presented. (A.C.)

  9. Measurement and analysis of radioactive substances

    International Nuclear Information System (INIS)

    2001-01-01

    Here are gathered the abstracts presented to the 3. summer university of the year 2001 whose main themes were the destructive (5 conferences) and nondestructive (8 conferences) analyses applied to nuclear industry. The points of view of different organisms (as DSIN: Directorate for the Safety of Nuclear Installations, IPSN: Institute of Nuclear Protection and Safety, OPRI: Office of Protection against Ionizing Radiations, TUI: Institute for Transuranium Elements, COGEMA, EDF: Electric Utilities, ANDRA: French National Agency for Radioactive Waste Management, CRLC Val d'Aurelle, France) concerning the needs involved in nuclear facilities control, the methods of radionuclide speciation in use internationally, the measurements and analyses of radioactive substances are given too as well as some general concepts concerning 1)the laser-matter interaction 2)the ions production 3)the quality applied to the measurements and analyses 4)the standard in activity metrology. (O.M.)

  10. 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

  11. The SILVA atomic process

    International Nuclear Information System (INIS)

    Cazalet, J.

    1997-01-01

    The SILVA laser isotope separation process is based on the laser selective photo-ionization of uranium atomic vapour; the process is presently under development by CEA and COGEMA in France, with the aim to reduce by a factor three the cost of uranium enrichment. The two main components of a SILVA process plant are the lasers (copper vapour lasers and dye lasers) and the separator for the vaporization (with a high energy electron beam), ionization and separation operations. Researches on the SILVA process started in 1985 and the technical and economical feasibility is to be demonstrated in 1997. The progresses of similar rival processes and other processes are discussed and the remaining research stages and themes of the SILVA program are presented

  12. 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

  13. Mining and miners of the French uranium - III - The time of great adventures (1959 - 1973)

    International Nuclear Information System (INIS)

    Paucard, A.

    1996-07-01

    This third volume of ''Mining and miners of the French uranium'' describes the historical, political and strategical aspects of the French experience in uranium prospecting and exploitation during the period 1959 -1973. This volume comprises two parts. Part one concerns the political and strategical aspects of the French uranium policy according to the economical and geopolitical context of this period. The second part describes the uranium exploration and exploitation works in the French territory and overseas (Madagascar, Gabon, Niger, Central African Republic, Canada, West Africa, Cameroon, Congo, Turkey, Iran, Afghanistan, Pakistan, India, Argentina, Brazil, Australia, Indonesia..). A chapter is devoted to the miners' life and working conditions during this period. The complete volume is written using unpublished bibliographic sources from the CEA and Cogema and from personal miners' archives. It is full of anecdotes and extracts of letters and reports and written with a saga novel style but refers continuously to the geological context of each deposit. (J.S.)

  14. Uranium mines and French mining companies: a magnificent adventure

    International Nuclear Information System (INIS)

    Blanc, J.

    2008-01-01

    The French mining adventure still arouses enthusiasm. The search for uranium began in 1945 with the creation of the Cea (Atomic Energy Board) whose one mission was to supply the nascent French nuclear programme with the necessary materials. Prospecting works were then led throughout France, Madagascar, the Ivory Coast and the French equatorial Africa. More than 60 years later the only surviving actor of this quest for uranium has become the mining department of Areva Nuclear Cycle which is itself a sub-company of Areva. The author, who was an ancient high executive of Cogema draws a detailed history of the French uranium mining industry with with its ups and downs, by analysing the impact of the 2 oil crisis and of the decline of nuclear energy in the decade following the Chernobyl accident. (A.C.)

  15. Utilization of test boreholes in prospecting and mining operations

    International Nuclear Information System (INIS)

    Sierak, J.P.

    1987-01-01

    Test boreholes are of fundamental importance for mining and prospecting operations. The drilling techniques are suited to the geological conditions and to the nature of the information desired. At Cogema, non-coring test boreholes, mainly drilled by a rotary percussive method, represent over 90% of the footage drilled; they achieve impressive performances at a cost which is by far less than that of coring test boreholes. The geological exploitation of these test boreholes is effected by a combined investigation of well logging and of cuttings. These investigations lead to an assessment for certain substances like uranium or coal or they mark the limits for favourable zones which alone will form the object of coring boreholes. In mining operations, boreholes indicate the definition for workable panels; they ensure at less cost the distribution of fluids, the forwarding of stowing material and the mine ventilation [fr

  16. Nuclear - the faint hope Areva

    International Nuclear Information System (INIS)

    Dupin, Ludovic

    2015-01-01

    This article discusses the future of Areva as a part of its activities (nuclear reactor building and maintenance) is now managed by EDF. The author notices that Areva's present situation looks like the Cogema's one before its merge with Framatome and some CEA activities to give birth to Areva. The main problem is the debt for a group which possesses important assets (hyper-profitable uranium mines, advanced technology plants for nuclear fuel processing) and opportunities (the possibility to become a leader in the dismantling activity, to take advantage of the increasing uranium demand), but is unable to self-finance, suffers from its heavy organisation which needs to be reviewed and even separated into two companies, and is also threatened by the cost of new reactors and by being too small to launch new projects in front of the giants of the mining sector

  17. The safety of French pressurised water reactors: a regulator's perspective

    International Nuclear Information System (INIS)

    Lacoste, A.-C.

    1993-01-01

    France has invested heavily in nuclear technology and is today, arguably, the dominant player in the industry: in EdF we have a utility operating over 50 reactors; in Cogema we have a company operating in every sector of the fuel cycle industry; and in Framatome, perhaps the major nuclear reactor constructor in the world. As wedded as the country is to nuclear energy, France has to be aware of any potentially harmful developments - politically, socially and industrially. Neither can the international arena be neglected, where events can have a profound effect on France's worldwide interests. The following articles demonstrate how much energy and ingenuity France is devoting to resolving the many critical issues facing its nuclear industry, including safety, economics and waste disposal. (Author)

  18. Combined evaluation. Plutonium transports in France. Problems of safety and reliability of transport container FS47

    International Nuclear Information System (INIS)

    Marignac, Y.; Coeytaux, X.; Large, J.H.

    2004-09-01

    This report concerns the safety and the protection of plutonium dioxide transported from Cogema La Hague to the mixed oxide fuel plant of Marcoule and Cadarache. The French approach of the transport safety is based on the combining of two essential principles: the first one affirms that the performances of the FS47 container in regard of containment (norms TS-R-1 from IAEA for the accidental conditions) is conceived to resist in any situation even terrorism or sabotage. In fact, the IAEA norm follows a probabilistic study without a voluntary attack such a terrorist one. The second principle rests on the ability to prevent the treat of terrorism acts, because of a secrecy policy on the plutonium transport. It appeared that the Green peace association has succeeded several times to know exactly the hours, the trips of the plutonium transport and this simple thing raises more questions than it solves. (N.C.)

  19. Treatment of plutonium contamined solid wastes by electrogenerated Ag(II)

    International Nuclear Information System (INIS)

    Saulze, J.L.

    1990-01-01

    A process for the treatment of plutonium contaminated solid wastes is designed. Two types of wastes have been studied; incineration ashes (COGEMA UP1) and sludges produced in the cryotreatment facility in Cadarache Center (France). The principle of the process is based on the rapid dissolution of PuO 2 (contained in the wastes) under the action of aggressive Ag(II) species, regenerated electrochemically. In the case of the treatment of incinerator ashes an electrochemical pretreatment is necessary if the chloride ion content of the ashes is high. The feasibility of the decontamination process has been proved for the two types of plutonium contaminated solid wastes at a pilot level; for example 1 Kg of ashes (or 0.75 Kg of sludges) has been treated in one experiment, and 97% (or 95%) of the total plutonium was dissolved at the end of the experiment. Industrial applications of this new process are underway [fr

  20. The nuclear fuel cycle

    International Nuclear Information System (INIS)

    Patarin, L.

    2002-01-01

    This book treats of the different aspects of the industrial operations linked with the nuclear fuel, before and after its use in nuclear reactors. The basis science of this nuclear fuel cycle is chemistry. Thus a recall of the elementary notions of chemistry is given in order to understand the phenomena involved in the ore processing, in the isotope enrichment, in the fabrication of fuel pellets and rods (front-end of the cycle), in the extraction of recyclable materials (residual uranium and plutonium), and in the processing and conditioning of wastes (back-end of the fuel cycle). Nuclear reactors produce about 80% of the French electric power and the Cogema group makes 40% of its turnover at the export. Thus this book contains also some economic and geopolitical data in order to clearly position the stakes. The last part, devoted to the management of wastes, presents the solutions already operational and also the research studies in progress. (J.S.)

  1. Future nuclear activities on a European scale must take account of the interests of Germany and its neighbouring countries

    International Nuclear Information System (INIS)

    Berke, C.

    1989-01-01

    Anybody having concernment in nuclear industry and engineering, and particularly in the fuel reprocessing activities, will be deeply concerned by the emerging cooperation between VEBA and Cogema at Cap de la Hague, and by the statements that could be heard from leading politicians. It is true that the current political and regulatory situation really does not invite potential operators to engage in further construction of nuclear installations, but one must not forget that 40 p.c. of electricity supplies are generated by West German nuclear power stations. Abandoning nuclear power does not seem to be a good decision if one considers the still growing demand for energy in the world, and the effects of fossil fuel consumption on the global climate. (DG) [de

  2. 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

  3. The other research ways for future

    International Nuclear Information System (INIS)

    Camarcat, N.

    1995-01-01

    This paper describes two of the three research ways developed by the French organizations in accordance with the December 30, 1991 law about the different possibilities for radioactive waste management: the separation and transmutation of isotopes, and the improvement of packaging and long-time surface storage. The separation and transmutation processes comprises two aspects developed in collaboration with COGEMA: the Puretex process for the volume reduction of B and C reprocessing wastes, and the Actinex process for the transformation of long-life and high-level radioactive wastes into shorter-life wastes. For the long-time surface storage, new packaging and processing techniques are developed to reduce the volume of wastes. (J.S.). 5 figs., 1 tab., 1 photo

  4. 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.)

  5. Acts of the Ville d'Avray seminar on the 21. and 22. of january 2003 on the dialogue around industrial sites

    International Nuclear Information System (INIS)

    2003-01-01

    Following the research work on the stakes of the social dialogue around the follow up of nuclear and non nuclear industrial installations opened by I.R.S.N. in 2000, a seminar has been organised on the 21. and 22. of january 2003 at Ville d' Avray. This seminar gathered different personalities( administration, experts, operators, associations, information local commissions, elected) in order to discuss and enrich the conclusions of the research work and elaborate a contribution about the dialogue process. The different subjects tackled were: Approach concerning the release of the british nuclear fuel installation at Sellafield, nuclear power plants of Saint Alban and Cogema La Hague, industrial site of Metaleurop at Noyelles-Godault, local commission of surveillance of the nuclear site of power generation of Fessenheim, evolution of the legislation frame around installations. (N.C.)

  6. Conclusions and recommendations of the SCOPE-RADSITE workshop on remediation achievements after uranium mining and milling

    International Nuclear Information System (INIS)

    Vandenhove, H.; Vandecasteele, C.M.; Collard, G.

    2002-01-01

    The SCOPE-RADSITE Project provides a unique international scientific forum where the radioactive wastes generated in the development of nuclear weapons, including their potential impact on the environment and human populations, are studied and reviewed. At the present SCOPE-RADSITE workshop a team of experts presented the current status of uranium mining and milling operations in the United States, in the former Soviet Union (FSU) and in Central and Eastern Europe. The effect of radiocontaminants resulting from the uranium mining and milling operations to species other than humans and the combined effects of environmental radiation and other agents were discussed. Finally, three cases of remediation projects were presented: remediation at COGEMA sites in France, the WISMUT rehabilitation project in Germany and uranium mine reclamation in Texas and remediation achievements were described. Finally the workshop discussed important issues and recommendations to be considered when approaching remediation of past legacies resulting from uranium mining and milling. (author)

  7. Colloquium act 'Nogent - 2001'

    International Nuclear Information System (INIS)

    Lagadec, P.; Lacoste, A.C.; Lazar, Ph.; Eimer, M.; Pouilloux, M.; Pellat, R.; Sene, R.; Schmitt, P.

    2006-01-01

    This colloquium is essentially devoted to the nuclear crisis and its management. As regards the nuclear crisis, it is especially about the behavior of the C.L.I. (local commissions of information) of the communication, the errors to be avoided and possible surprises. Several experiences are reported: the crisis exercise at the nuclear center of electric production (C.N.P.E.) of Saint-Laurent-des-Eaux, the experience of Cogema La hague in communication, transparency and communication for secret installations, the experience of an independent expert from the group of scientists for the information on nuclear (G.S.I.E.N.) and the local commission of information of Fessenheim. (N.C.)

  8. Measurement and analysis of radioactive substances; Mesure et analyse de substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    Here are gathered the abstracts presented to the 3. summer university of the year 2001 whose main themes were the destructive (5 conferences) and nondestructive (8 conferences) analyses applied to nuclear industry. The points of view of different organisms (as DSIN: Directorate for the Safety of Nuclear Installations, IPSN: Institute of Nuclear Protection and Safety, OPRI: Office of Protection against Ionizing Radiations, TUI: Institute for Transuranium Elements, COGEMA, EDF: Electric Utilities, ANDRA: French National Agency for Radioactive Waste Management, CRLC Val d'Aurelle, France) concerning the needs involved in nuclear facilities control, the methods of radionuclide speciation in use internationally, the measurements and analyses of radioactive substances are given too as well as some general concepts concerning 1)the laser-matter interaction 2)the ions production 3)the quality applied to the measurements and analyses 4)the standard in activity metrology. (O.M.)

  9. Case law and administrative decisions

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    About the case law we find four parts, one concerns France and the judgement of the council of state on an application for annulment of the decree of 10 january 2003 authorizing Cogema to modify a major nuclear installation, a second one is in relation with the Usa through the ruling in relation to the sale of uranium enrichment services in the united States, decision concerning the Yucca mountain repository, Indiana michigan power company v. United States, natural resources defense council, snake river alliance, confederated tribes and bands of the Yakama indian Nation, Shoshone Bannock Tribes v. Abraham. For the third part devoted to European union it is question of the judgement of the European Court of justice in European union v. UK, the fourth part concerns administrative decisions with the early shutdown of Barsebaeck-2 in Sweden. (N.C.)

  10. Adsorption process analysis at the solid-gas interface by the polarization phenomenon study

    International Nuclear Information System (INIS)

    Mouton-Chazel, V.

    1994-01-01

    In order to improve the safety of anti-gas filters users, the Cogema (Nuclear Materials General Company) has developed a gaseous pollutants saturation detection technology for respiratory protection masks. As a matter of fact, the problem consists in studying the surface properties of a solid. In this study the adsorption has been considered as a phenomenon which can be followed by a relatively simple electrical measure technology. A microscopic description of the adsorption phenomenon has been given at first and explained by the thermodynamics laws. Then a theoretical model has been elaborated. The developments which have been brought to this model in this work have allowed to give a satisfactory interpretation of the phenomena observed during the adsorption of a polar gas on a zeolite. (O.M.)

  11. Treatment of solid waste highly contaminated by alpha emitters. Recent developments of leaching process with continuous electrolyte regeneration

    International Nuclear Information System (INIS)

    Madic, C.

    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 during research experiments on fuel reprocessing. Leaching processes using electrogenerated Ag (II(a very agressive agent for PuO 2 )) in nitric acid solutions, were developed and several facilities were designed and built to operate the processes: (1) ELISE and PROLIXE facilities, for the treatment of α and α, β, γ solid wastes (CEA, FONTENAY-AUX-ROSES) (2) PILOT ASHES FACILITY for delete, the treatment of plutonium contaminated ashes (COGEMA, MARCOULE). A brief description of the process and of the different facilities is presented; the main results obtained in ELISE and PROLIXE are also summarized

  12. Colloquium act 'Nogent - 2001'; Acte du colloque 'Nogent - 2001'

    Energy Technology Data Exchange (ETDEWEB)

    Lagadec, P. [Ecole Polytechnique, 75 - Paris (France); Lacoste, A.C. [Ministere de l' Economie, des Finances et de l' Industrie, Dir. de la Surete des Installation Nucleaires, 75 - Paris (France); Lazar, Ph. [Conseil Superieur de la Surete et de l' Information Nucleaires (CSSIN), 75 - Paris (France); Eimer, M. [Commissions locales d' Information et de Surveillance (CLIS), 41 - Saint Laurent des Eaux (France); Pouilloux, M. [Cogema la Hague, 50 - Beaumont Hague (France); Pellat, R. [CEA, 75 - Paris (France); Sene, R. [Groupement des Scientifiques pour l' Information sur l' Energie Nucleaire, 91 - Orsay (France); Schmitt, P. [CLS de Fessenheim, 68 (France)

    2006-07-01

    This colloquium is essentially devoted to the nuclear crisis and its management. As regards the nuclear crisis, it is especially about the behavior of the C.L.I. (local commissions of information) of the communication, the errors to be avoided and possible surprises. Several experiences are reported: the crisis exercise at the nuclear center of electric production (C.N.P.E.) of Saint-Laurent-des-Eaux, the experience of Cogema La hague in communication, transparency and communication for secret installations, the experience of an independent expert from the group of scientists for the information on nuclear (G.S.I.E.N.) and the local commission of information of Fessenheim. (N.C.)

  13. Directory of the French nuclear industry

    International Nuclear Information System (INIS)

    2002-10-01

    This directory includes data sheets on the French companies operating in the nuclear industry. It begins with an introduction containing information on the French nuclear industry: 1 - nuclear power development in France (national energy plan, history, organization, economic advantages, reactors); 2 - French operator: Electricite de France (EdF); 3 - the industry (Areva, Cogema, mining activities, uranium chemistry and enrichment, processing, recycling, engineering, services, Framatome ANP); 4 - R and D and knowledge dissemination: French atomic energy commission (CEA); 5 - nuclear safety, security, control and regulation: nuclear safety authority (ASN), general direction of nuclear safety and radioprotection (DGSNR), institute of radioprotection and nuclear safety (IRSN), radioactive wastes, ANDRA's role; 6 - associations: French atomic forum (FAF), French nuclear industry trade association (GIIN), French nuclear energy society (SFEN), French radiation protection society (SFRP). Then, the data sheets of the directory follows. (J.S.)

  14. Quality assurance and product quality

    International Nuclear Information System (INIS)

    Lacroix, D.; Bastiani, P. de

    2004-01-01

    The basic quality assurance requirements have to be completed by means that are oriented towards the quality of products; in COGEMA LOGISTICS our approach is based on four principles: 1) an integrated management system: Quality, health and safety, environment 2) an organization based on the responsibility of all actors, trust and transparency 3) a methodical approach to continuously improve the methods that are employed to achieve quality: -process management -corrective and preventive actions -self assessments and various surveys 4) but at the same time strong procedures for control and monitoring of all activities: -technical and quality audits (external and internal) -at source inspections -engineering activities inspections This performance-based approach is necessary to guaranty the effectiveness of the traditional formal QA means

  15. Publication of the inspection follow-up letters of the ASN on its site web asn.gouv.fr; Publication des lettres de suite d'inspection de l'ASN sur son site web asn.gouv.fr

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    Since February 2002, the French authority of nuclear safety (ASN) publishes on its web site (http://www.asn.gouv.fr) the letters addressed to the operators of nuclear facilities at the end of its inspections. The ASN carries out about 700 inspections every year which concern the French nuclear facilities, the central services of nuclear operators or of their suppliers, and the transports of nuclear materials. Each inspection is followed by a follow-up letter which mentions all anomalies noticed during the inspection and eventually asks for some remedial actions or for some complements of information. This document brings together the letters published between february and May 2002 and concerning the on-site inspections of nuclear facilities (EdF nuclear power plants, CEA centers, Cogema facilities, other sites) and the off-site inspections (Andra, transports of nuclear materials). (J.S.)

  16. Combined evaluation. Plutonium transports in France. Problems of safety and reliability of transport container FS47; Evaluation Conjointe. Transports de plutonium en France. Problemes de surete et de securite du container de transport FS47

    Energy Technology Data Exchange (ETDEWEB)

    Marignac, Y.; Coeytaux, X. [Wise-Paris, 75 (France); Large, J.H. [Nuclear Engineer, Large and Associates, Londres (United Kingdom)

    2004-09-15

    This report concerns the safety and the protection of plutonium dioxide transported from Cogema La Hague to the mixed oxide fuel plant of Marcoule and Cadarache. The French approach of the transport safety is based on the combining of two essential principles: the first one affirms that the performances of the FS47 container in regard of containment (norms TS-R-1 from IAEA for the accidental conditions) is conceived to resist in any situation even terrorism or sabotage. In fact, the IAEA norm follows a probabilistic study without a voluntary attack such a terrorist one. The second principle rests on the ability to prevent the treat of terrorism acts, because of a secrecy policy on the plutonium transport. It appeared that the Green peace association has succeeded several times to know exactly the hours, the trips of the plutonium transport and this simple thing raises more questions than it solves. (N.C.)

  17. 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.

  18. Considering the post-1995 enrichment market

    International Nuclear Information System (INIS)

    Gunter, L.

    1994-01-01

    World demand for uranium enrichment services is likely to grow only a little over the next decade, from the current 28 million separative work units (SWU) per year to 33 MSWU per year. Much of the growth will come from Asia where nuclear generating capacity is still increasing. The current situation of the primary enrichment companies is summarized. The primary Western suppliers, Cogema, United States Enrichment Corporation and Urenco, are competing for increased market share in the USA, Europe and Asia as utilities purchase their post-1995 requirements. Entry of the Russian enrichment company, Tenex, into Western markets has been limited by trade restrictions. As a consequence of disarmament, blended weapons material has resulted in a surplus of low-enriched uranium. Together with over-capacity amongst the primary enrichers this has led to an expectation that reduced prices will be negotiable in the medium term. (3 figures). (UK)

  19. Uranium Research in Senegal

    International Nuclear Information System (INIS)

    Kanouté, Mamadou

    2015-01-01

    The work of mining companies have so far not proved economic uranium resources, but they have nevertheless contributed greatly to a better understanding of the geology, particularly in Eastern Senegal, on the upper Precambrian basin including which equivalents exist throughout West Africa (the uranium belt of Zaire) prospected by CEA-COGEMA teams. The researches carried out in Senegal, but also in Guinea and Mali helped establish a detailed map and understand the course of geological history. With new exploration techniques and data of airborne geophysical (radiometric) provided by the Mining Sector Support Programme (PASMI 9th EDF 9 ACP SE 09), AREVA, at the end of the first period validity of the exploration permit increased significantly, the resources. Prospects are favorable to a doubling of resources; objective of a uranium mine in Senegal. Synergies are possible and desirable with joint exploitation of uranium deposits located in Mali, near the border with Senegal.

  20. Market implications of advanced enrichment techniques

    International Nuclear Information System (INIS)

    Rougeau, J.-P.

    1987-01-01

    The only commercial outlet for uranium is for nuclear reactors and the uranium market will be closely linked to the nuclear power market for the forseeable future. Any production cost saving in the uranium cycle clearly, therefore, increases the chances for world-wide expansion of the nuclear industry. Thus, although there is overcapacity in enrichment, development of cheaper, new or more efficient established techniques, is important. The atomic vapour laser isotope separation process is considered and discussed against this background. Separative work units are explained for this technique. The problems of integrating laser isotope separation into the fuel cycle are discussed. The effects on the amount of natural uranium required for different recycling strategies, and for different laser tails assay and time schedules are illustrated. Over the next twenty years laser-based enrichment will have an important effect on the fuel cycle industry. COGEMA is expected to play a part in developing these new techniques. (U.K.)

  1. Annual report 2000

    International Nuclear Information System (INIS)

    2001-01-01

    This document provides information on the activities of the Cea-Industry Group during the year 2000. The following topics are presented: the profile of the Cea-Industry Group, keys data for 2000, the nuclear fuel cycle, the nuclear power plants and nuclear services, the biomedical, the semiconductors, the financial aspects and the management report of the board of directors. A special interest is given to the new organization which has been set up and which will give birth to an industrial group of global dimension, named Topco for the present. By combining the activities of Cogema, Framatome ANP and their subsidiaries, the ''nuclear technologies'' business Topco, will regroup french expertise in the atom, from the fuel cycle to cleanup and dismantling, from services to engineering. (A.L.B.)

  2. The TN-GEMINI: experience on a versatile alpha waste transport container

    International Nuclear Information System (INIS)

    Roland, V.; Chanzy, Y.

    2001-01-01

    The present paper discusses experience gained in moving alpha wastes and its teachings regarding transport aspects of D and D. Alpha wastes are generated in fuel cycle facilities such as those involved in reprocessing, in manufacture of mixed oxide fuel, and by research laboratories. If a significant amount of wastes has to be transported, then a Type B packaging is required. Developed by Transnucleaire and COGEMA, the TN GEMINI container enables nuclear facilities operators to optimise their alpha waste transport management, and more generally contribute to their D and D projects. After describing succinctly the design of the TN GEMINI, the paper will explain how the packaging is being operated. Teachings from experience will be shared. (orig.)

  3. Development of fibre reinforced concrete overpacks in France

    International Nuclear Information System (INIS)

    Boudry, J.C.; Pech, R.

    1991-01-01

    Radioactive waste conditioning is a major step in the processes implemented in nuclear installations. The objective is to contain the radioactive materials in nuclear waste as satisfactory as possible for man and the environment contained ensuring containment integrity having to be guaranteed over very long periods of time. Medium-level (ML) and even very low-level (LL) waste is no exception to this rule. Cogema thus conducted research for many years and developed a novel process to condition nuclear waste in containers reinforced with metal fibres, called fibre concrete containers. This process, welcomed by the French Safety Authorities and ANDRA, the French Radioactive Waste Management Agency, currently appears to be the best way to condition low and medium-level solid waste. (author)

  4. Image analysis and 2D/3D modeling of the MOX fuel microstructure

    International Nuclear Information System (INIS)

    Oudinet, Ghislain

    2003-01-01

    The microstructure of the MOX fuel, made with UO_2 and PuO_2, determines his 'in pile' behavior. The french companies CEA and COGEMA are highly interested in its description by image analysis, which is the object of the present work. The segmentation algorithms described here use pictures issued from a microprobe and a SEM, to analyse the plutonium and porosity distribution in the fuel pellets. They are innovating, automated and robust enough to be used with a small data set. They have been successfully tested on different fuels, before and after irradiation. Three-dimensional informations have been computed with a genetic algorithm. The obtained 3D object size distributions allowed the modeling of many different industrial and research fuels. 3D reconstruction is accurate and stable, and provides a basis for different studies among which the study of the MOX fuel 'in pile' behavior. (author)

  5. The ''waste unit'' of the opencast uranium mine of Bellezane

    International Nuclear Information System (INIS)

    Sirot, P.

    1986-01-01

    Cogema works at Bellezane by an opencast method a deposit of uraniferous ore which will have to extract a tonnage of 15 Mt gross for a uranium metal content of 800 t. The waste of the overburden is mined in steps of 15 m height. The ore itself is mined in slices of 3 to 5 m height to improve the selectivity. Heavy equipment is used; it comprises in particular for the overburden a large Liebherr 914 power shovel with a bucket of 11m 3 which operates in two shifts per day, loading three Caterpillar trucks of 77 t. The results are impressive, i.e. 750 t per man and shift for the overburden and 400 t per man and shift for the ore. The author gives also a breakdown for the extraction costs of the two sectors [fr

  6. Paper of 30B, 48Y and 48Z flask maintenance

    International Nuclear Information System (INIS)

    Peclier, Roger.

    1980-11-01

    The paper starts with a brief review of the French and American regulations and gives information on a waiver recently granted by the Ministry of Industry Departments. Because of the large fleet of 8 to 10 thousand flasks existing in France, the COGEMA had to build a special workshop for maintaining these types of tanks. These tanks, considered to be pressurized, have to undergo statutory hydraulic testing every five years. For problems of criticality and water pollution, allowing for the vessel feet remaining in the flask, a preliminary internal cleaning to remove this vessel foot is necessary prior to filling with water for the hydraulic test. Internal cleaning is also required at times, either to prevent degradation of the product to be transported or to eliminate irradiation exceeding transport standards [fr

  7. Advanced Purex process and waste minimization at La Hague

    International Nuclear Information System (INIS)

    Masson, H.; Nouguier, H.; Bernard, C.; Runge, S.

    1993-01-01

    After a brief recall of the different aspects of the commercial irradiated fuel reprocessing, this paper presents the achievements of the recently commissioned UP3 plant at La Hague. The advanced Purex process implemented with a total waste management results in important waste volume minimization, so that the total volume of high-level and transuranic waste is lower than what it would be in a once-through cycle. Moreover, further minimization is still possible, based on an improved waste management. Cogema has launched the necessary program, which will lead to an overall volume of HLW and TRU wastes of less than 1 m 3 /t by the end of the decade, the maximum possible activity being concentrated in the glass

  8. The communication in safety matter

    International Nuclear Information System (INIS)

    Lacoste, A.C.

    1997-01-01

    The nuclear risk has three interesting characteristics: it is new, it is insidious and it can be disastrous. These three characteristics lead to consider a particular role of public authorities( Dsin Direction of Nuclear Installations Safety). Nuclear energy can be taxed of two original sins: the close relation between military nuclear and civil nuclear energy, and the nuclear, in France, lacks of democracy.Third point: only five speakers in front of authorities: EDF, Cea, Cogema, Framatome and Andra and these five ones are linked with State. These points summarize the French situation in nuclear energy. By communication the Dsin tries to answer to two obligation, a moral code and a democratic debate. The tools to communicate are the review 'controle' which is published every two months, the Minitel service 'Magnuc ' (code 3614 MAGNUC). This role of communication is not required especially by local elected people but it is the administration which tries to make it work. (N.C.)

  9. Presentation of the GIE INTRA Group's operational means

    International Nuclear Information System (INIS)

    Cochard, A.

    2010-01-01

    Located on the Chinon nuclear power plant site, the Intra Group is an economic interest grouping which has been created by the three French nuclear operators (EDF, CEA, and COGEMA now AREVA) after the Chernobyl accident. Its missions are to possess permanently available means of intervention in case of severe accident or radiological situation, to be able to intervene at any time on the French territory, to develop a European network of expertise, and to build up an ability centre for robotic intervention in hostile environment. This document briefly presents its different available means: remotely controlled equipment (inside and outside equipment, public works equipment), and radiological characterization equipment. Other aspects are briefly evoked: organization, information transmission, exercises and interventions, international relationships, future trends

  10. 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

  11. Report of the present state of nuclear fuel and the activities of the Swedish Nuclear Fuel Supply Company during October 1979 to September 1980

    International Nuclear Information System (INIS)

    1980-11-01

    A summary of the company's activities is presented. The world reserves of uranium are estimated to be enough for 100 years. The prospecting of uranium ores in Sweden is continued. The national requirements of natural uranium on to the year 2010 are estimated to 26000-39000 ton. A reserve storage of low enrichment uranium is being built up and so is a center for spent fuel storage near Oskarshamn. Contracts with Cogema concerning reprocessing have been entered into and a maritime transport system is being planned. The projects of the final disposal of radioactive waste are in progress. The research and development of the various aspects of the material science and geology in Connection with the final disposal is dealt with on both national and international basis. (G.B.)

  12. Economy and the fuel market

    International Nuclear Information System (INIS)

    1994-01-01

    The nuclear fuel manufacturing constitutes a considerable venture for the competitiveness of the nuclear power sector although it represents a relatively modest fraction (around 4%) of the nuclear kWh cost. The COGEMA group is participating through its branches in the control of the most part (32%) of the world manufacturing capacity of fuel for PWR. Amounting up to 242 operating installations this reactor type is the most widespread in the world. The paper discusses the costs, the fuel clients and the fuel suppliers. Data concerning the boiling water and fast neutron reactors, geographical localization of the PWR and VVER reactors all over the world, the PWR and fuel for PWR manufacturers are also presented

  13. CEA and mining industry

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    The French atomic energy commission (CEA) is involved in the mining industry in several ways: - in the front-end of the nuclear industry through its daughter companies and participations in the exploration and exploitation of uranium ores, but also of gold and alloy metals with a 26% participation in Eramet company, the world leader of manganese and nickel. This activity is the main occupation of Cogema daughter company, via the Areva holding; - in the back-end of the nuclear fuel cycle with the delicate problem of the management of radioactive wastes; - in parallel with the nuclear industry through an important activity in semiconductor materials (FCI and SMTElectronics); - and finally through various research works on several mineral compounds. This article focusses on the fuel cycle aspects of the CEA activities and concludes with the research works carried out today on thermonuclear fusion. (J.S.)

  14. Progress report on safety research of high-level waste management for the period April, 1982 to March, 1983

    International Nuclear Information System (INIS)

    Nakamura, Haruto; Tashiro, Shingo

    1983-06-01

    Main results obtained on Safety Research of High-Level waste Management in 1982 were editted. 1) The leaching mechanisms of the vitrified waste were studied to estimate the leach rate in disposal condition. 2) For the safety assessment of storage and disposal of the returning waste resulted from overseas reprocessing, properties of the glass simulating the composition by COGEMA are being measured. 3) In order to assess the integrity of the repository, influence of heat on the characteristics of rock mass and buffer materials was studied in underground drift. And also the retardation mechanism of the leached elements by rock mass was discussed. 4) The construction of Waste Safety Testing Facility (WASTEF) was completed, and vitrification test and near-field test using large radiation sources were initiated. (author)

  15. Acts of the Ville d'Avray seminar on the 21. and 22. of january 2003 on the dialogue around industrial sites; Actes du seminaire de Ville d'Avray des 21 et 22 janvier 2003 sur la concertation autour des sites industriels

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-01-15

    Following the research work on the stakes of the social dialogue around the follow up of nuclear and non nuclear industrial installations opened by I.R.S.N. in 2000, a seminar has been organised on the 21. and 22. of january 2003 at Ville d' Avray. This seminar gathered different personalities( administration, experts, operators, associations, information local commissions, elected) in order to discuss and enrich the conclusions of the research work and elaborate a contribution about the dialogue process. The different subjects tackled were: Approach concerning the release of the british nuclear fuel installation at Sellafield, nuclear power plants of Saint Alban and Cogema La Hague, industrial site of Metaleurop at Noyelles-Godault, local commission of surveillance of the nuclear site of power generation of Fessenheim, evolution of the legislation frame around installations. (N.C.)

  16. 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

  17. To make the economy of nuclear?

    International Nuclear Information System (INIS)

    Tinturier, B.; Barre, B.; Le Bars, Y.; Catz, H.; Perez, S.; Laponche, B.; Charpin, J.M.; Dessus, B.; Pellat, R.; Lipietz, A.

    2000-01-01

    This issue treats the report to the Prime minister about the prospective economical study of the nuclear electric path, study made by Jean-Michel Charpin, Benjamin Dessus and Rene Pellat. Synthesis, comments and criticisms are the essential of this issue. The different parts hand over to the President of Electricite de France, Bernard Tinturier, to the Director of the Research and development of COGEMA, Bertrand Barre (he speaks for oneself), to the President of ANDRA (national agency for the radioactive waste management), Yves Le Bars, to a Cea salaried employee administrator who has been elected on a list sponsored by the C.F.D.T., Henri Catz, to a Cea researcher, national responsible of the National Federation Energy Mines (C.G.T.), Serge Perez. (N.C.)

  18. Comparative consideration and design of a security depot for high radioactive glass-enclosed materials

    International Nuclear Information System (INIS)

    Jaroni, U.

    1985-01-01

    From the beginning of 1990 the COGEMA shall supply glass-enclosed high radioactive waste of the reprocessing of German fuel elements back to the Federal Republic of Germany. As to this time the final waste storage in the salt stock of Gorleben will not be available the glass cannisters have to be deposited above ground. First a comparison is made out of a number of proposed storage concepts for the deposition of HAW-glass blocks. The safety technical behaviour of the facility is considered. On the basis of the gained results a new facility design is presented, which can take 450 glass cannisters in a discoid built up cast-steel vessel and makes possible the utilization of the resulting radioactive heat of dissociation. During the development of this concept besides a compact, reasonable method of building and the thermodynamic behaviour of the storage the aspect of high security against release of radioactive materials was emphasized. (orig.) [de

  19. Loading, transport and storage of casks of the type CASTOR registered HAW28M in the frame of vitrified high-level waste repatriation from France

    International Nuclear Information System (INIS)

    Horn, Thomas; Graf, Wilhelm; Gosch-Warning, Michaela

    2011-01-01

    Until 2005 the German nuclear power plant operators have contracts with AREVA NC (former COGEMA) and NDA (former BNFL) concerning the reprocessing of spent fuel elements. The reprocessed and vitrified radioactive waste has to be repatriated to Germany. Due to the reprocessing of spent fuel elements with increased burnup and the repatriation after shorter cooling time the total activity and the Cm-244 content of the high-level-waste coquilles have increased since 2008. Consequently the heat output has increased to 2 kW/coquille. Therefore the new transport cask type CASTOR registered HAW28M was developed. The authors describe the design of the casks, the licensing according to the German transport regulations, loading procedures, radiation measurements and shipment completion. In autumn 2011 the repatriation of vitrified high-level waste from France is supposed to be completed with the transport of eleven CASTOR registered HAW28M.

  20. Developing a public information programme in France

    International Nuclear Information System (INIS)

    Tissot-Colle, Catherine

    1991-01-01

    In today's world, companies must initiate their own communications programmes or else they will be overtaken by others under circumstances and at times that are both generally unfavourable and not of their choosing. The development of a corporate communications programme is good for a company's commercial activities, for its management, and for its integration into its operating environment, as well as for its internal harmony. This is true for any company, regardless of its business sector. However, for companies in the nuclear field, such as the Cogema Group, do special considerations need to be taken into account? What is the communications track record of this industry? Should the overall communications strategy of a company be challenged based on this record? The questions are addressed in this paper. (author)

  1. Fiber reinforced concrete: an advanced technology for LL/ML radwaste conditioning and disposal

    International Nuclear Information System (INIS)

    Tchemitcheff, E.; Verdier, A.

    1993-01-01

    Radioactive waste immobilization is an integral part of operations in nuclear facilities. The goal of immobilization is to contain radioactive materials in a waste form which can maintain its integrity over very long periods of time, thus effectively isolating the materials from the environment and hence from the public. This is true regardless of the activity of the waste, including low-, and medium-level waste (LLW, MLW). A multiple-year research effort by Cogema culminated in the development of a new process to immobilize nuclear waste in concrete containers reinforced with metal fibers. The fiber concrete containers satisfy all French safety requirements relating to waste immobilization and disposal, and have been certified by Andra, the national radioactive waste management agency. The fiber concrete containers have been fabricated on a production scale since July 1990 by Sogefibre. (author). 3 refs., 5 figs., 7 tabs

  2. The technical and industrial evolutions in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Rougeau, J.P.; Guais, J.C.

    1989-01-01

    The fuel cycle industry is a vital part of nuclear energy generation. Producers in every step of this industry, from uranium to reprocessing are working to adapt their products and services both to the more and more competitive conditions of the market and to the utilities evoluting specific needs. For the next decade, the main trend is uranium economy and reduction of industrial costs. For the longer term, the difficult prevision of nuclear energy developments, in particular with new types of reactors necessitates a true capacity of adaptation both from the utilities and from the fuel cycle industry. Cogema has already demonstrated the ability to adapt its industrial capabilities and therefore can prepare confidently for the future challenges [fr

  3. 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

  4. The mining methods at the Fraisse mine

    International Nuclear Information System (INIS)

    Heurley, P.; Vervialle, J.P.

    1985-01-01

    The Fraisse mine is one of the four underground mines of the La Crouzille mining divisions of Cogema. Faced with the necessity to mechanize its workings, this mine also had to satisfy a certain number of stringent demands. This has led to concept of four different mining methods for the four workings at present in active operation at this pit, which nevertheless preserve the basic ideas of the methods of top slicing under concrete slabs (TSS) or horizontal cut-and-fill stopes (CFS). An electric scooptram is utilized. With this type of vehicle the stringent demands for the introduction of means for fire fighting and prevention are reduced to a minimum. Finally, the dimensions of the vehicles and the operation of these methods result in a net-to-gross tonnages of close to 1, i.e. a maximum output, combined with a minimum of contamination [fr

  5. International issue: the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    In this special issue a serie of short articles of informations are presented on the following topics: the EEC's medium term policy regarding the reprocessing and storage of spent fuel, France's natural uranium supply, the Pechiney Group in the nuclear field, zircaloy cladding for nuclear fuel elements, USSI: a major French nuclear engineering firm, gaseous diffusion: the only commercial enrichment process, the transport of nuclear materials in the fuel cycle, Cogema and spent fuel reprocessing, SGN: a leader in the fuel cycle, quality control of mechanical, thermal and termodynamic design in nuclear engineering, Sulzer's new pump testing station in Mantes, the new look of the Ateliers et Chantiers de Bretagne, tubes and piping in nuclear power plants, piping in pressurized water reactor. All these articles are written in English and in French [fr

  6. SGN-Reseau Eurisys participates to the Hanford military site rehabilitation

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    Numatec Hanford Corporation, a subsidiary company of SGN-Reseau Eurisys and Cogema, gained with Fluor Daniel the contract for the rehabilitation of the old military nuclear centre of Hanford (Washington, USA). This contract of 5 years represents 5 billions of US dollars with 300 millions of dollars for the French part. This short paper gives a general description of the Hanford installations and of the partners involved in the contract: Fluor Daniel consortium, Lockheed Martin, Babcock and Wilcox, Duke Engineering and Services, Rust Federal Services, Numatec Hanford Corporation (NHC), SGN-Eurisys Services Corporation (SESC). The schedule comprises: the stabilisation of the residual plutonium in all installations before December 1999, the removal of muds and debris from the K storage pool of irradiated fuels before June 2000, the draining and cleaning of the high activity storage tanks before December 2001 and the general decontamination of the installations up to the year 2005. (J.S.)

  7. Risk assessment associated with the transport of low specific activity waste to the Centre de l'Aube disposal facility, France

    International Nuclear Information System (INIS)

    Raffestin, D.; Tort, V.; Manen, P.; Schneider, T.; Lombard, J.

    1994-01-01

    Since 1991, French Low Specific Activity wastes have been stored in the near-surface waste disposal site in the Aube region (CSA). In 1995, the CSA plans to receive approximately 23,000 m 3 of waste from the three major producers, EDF (Electricite de France), COGEMA (COmpagnie GEnerale des MAtieres nucleaires), and the CEA (Commissariat a l'Energie Atomique). Four different kinds of package are broadly represented: the 200 l drums to be compacted, the 200 l drums filled with fixed wastes, concrete shells and metallic boxes. As the radiological exposures resulting from waste transport could stem from both incident-free transport and accident situations, two separate studies have been conducted. Using the INTERTRAN code (IAEA software) for accident-free transport, the overall effective collective doses related to the whole transport activity have been calculated and a risk of 0.48 man.Sv per year has been deduced. (author)

  8. Public information - North West region of Russian Federation

    International Nuclear Information System (INIS)

    Saiapina, A.

    2000-01-01

    Center of Public Information (CPI) in North West region of Russian Federation is a part of the State Regional Educational Center of Ministry of the Russian Federation on atomic energy. The premises of the Centre (about 500 sq. rn.) include the exposition hall, video hall, the hall for press conferences, rooms for meetings, conferences. CPI provides the visitor with the wide range of information dealing with the nuclear power. It was opened in the structure of State Regional Educational Centre in 1997. Regional Centre of Public Information of MINATOM of Russia in Saint Petersburg was created according to the agreement with the European Union Commission in the framework of the TACIS program with the participation of French companies EDF, COGEMA, STEPFER. The objectives of the CPI are discussed (authors)

  9. Adsorption process analysis at the solid-gas interface by the polarization phenomenon study; Analyse des processus d`adsorption a l`interface solide - gaz par l`etude du phenomene de polarisation

    Energy Technology Data Exchange (ETDEWEB)

    Mouton-Chazel, V

    1994-10-05

    In order to improve the safety of anti-gas filters users, the Cogema (Nuclear Materials General Company) has developed a gaseous pollutants saturation detection technology for respiratory protection masks. As a matter of fact, the problem consists in studying the surface properties of a solid. In this study the adsorption has been considered as a phenomenon which can be followed by a relatively simple electrical measure technology. A microscopic description of the adsorption phenomenon has been given at first and explained by the thermodynamics laws. Then a theoretical model has been elaborated. The developments which have been brought to this model in this work have allowed to give a satisfactory interpretation of the phenomena observed during the adsorption of a polar gas on a zeolite. (O.M.). 169 refs.

  10. Panorama of mining activities in France during 1995

    International Nuclear Information System (INIS)

    Michel, J.C.; Bornuat, M.; Mouron, R.

    1996-01-01

    The French mining industry in 1995 continued to follow the overall trend of the past 5 to 10 years characterized mainly by: 1)a decline in the production of most energy materials: oil, coal, uranium. This decline will probably be further accentuated over the next two years with the planned closure of Lodeve (U), Forbach, La Mure and Carmaux (coal). Gas production, however, has remained relatively stable at 4.7 to 5 billion m''3 per year. 2)a scarcity of metal ore mines in Metropolitan France 3)an increase in the production of gold that, in 1995, came close to 6 tonnes in Metropolitan France and reached 8.4 tonnes with French Guiana. 4)the development of metal ore mining in the DOM-TOM 5) divergent developments in the industrial mineral sector: downward trends for sulfur, talc, andalusite, diatomite and silica; upward trends for kaolin, mica, feldspar and salt. Although overall the decline in mine production continued, the panorama does include some positive aspects: 1)France's independence in the energy sector exceeded the half-way mark two years ago and 1995 saw an appreciable decrease in the nation's energy bill compared to 1994. 2)French companies involved in metal mining have adapted themselves to world trends: Cogema has diversified its uranium sources mainly through its mining interests in Canada; Eramet has strengthened its activities by becoming the majority shareholder of Comilog, a manganese producer in Gabon. France also has mining interests in Africa, South America and Europe through LaSource Compagnie Miniere (BRGM and Normandy) created in 1995 3) France's position and production in the industrial mineral sector are significant at European scale, if not at world scale, as regards andalusite, diatomite, kaolin, mica, feldspar, sulfur, potassium, salt and industrial silica. Finally, mention must be made of the increasing environmental awareness by the French authorities and mining companies. This has resulted in a major rehabilitation of mine sites by

  11. Risk perception and risk communication: lessons learned

    International Nuclear Information System (INIS)

    Baillif, L.; Sackur, J.

    1998-01-01

    Industry can master risks but it cannot master the representations people have of these risks. This is why distortions may occur, as the public perceives risks where they are not, or in a totally deformed way. To deal with this type of situation which is dangerous in the long run, both for society and industry, it is necessary to study in detail where and how the difference between real risks and perceived risks is introduced. It then becomes possible to determine what means of action are available to manage the representations and the perceptions of risks. We shall mention two rather different examples of type of direct contact with the industrial reality; in France, we have determined policy of visits of nuclear sites (more than 10 000 people visit Cogema- la Hague site yearly), mainly addressed to school children and people living in the vicinity of the site. During these visits there is of course no question of explaining the detailed operation of the facility or the risks it generates. The purpose is to make the representation of the nuclear industry just as familiar as the representation of another large-scale technology tool: trains, dams,. In a different manner, missions are organised by Cogema - B.N.F.L.- O.R.C. (Overseas reprocessing Committee) to de dramatize the transport of high level vitrified wastes from Europe to Japan. these missions travel through those countries the ship come close to. Here, again, although the target is more the relays of opinion, the effective presence of specialized transport ship is a crucial element in putting a halt to phantasmic representations, as they are born from the remoteness of the object. (N.C.)

  12. Design of casks: incorporating operational feedback from maintenance

    Energy Technology Data Exchange (ETDEWEB)

    Bimet, F.; Hartenstein, M. [COGEMA Logistics, Saint Quentin (France)

    2004-07-01

    Casks are designed to conform to regulations and to client specifications. Essential areas such as easy operation, low costs of maintenance, low operation and maintenance doses, limited waste, are not explicitly covered. Notwithstanding, COGEMA LOGISTICS uses all feedback available, so that casks are designed to be easy, safe and economical to operate and maintain. Maintenance is an activity where you do spot items that old-time designers could have made better, and things that users should not have done. Thanks to quality assurance, there are a number of data available, waiting to be collected and exploited; they have to be identified, located, retrieved, and analysed. Using information such as wear, damage, use of spare parts, access problems helps to make casks ever better. It leads to more efficient concepts, and to upgrades on existing designs; it also allows to integrate environmental considerations, inter alia in the choice of materials and in maintenance methods. It is necessary for the designer to interact with the users, the cask owners, the maintenance providers, in order to gather all relevant information and events. This is made easier when all these actors are ''under one roof'', or have very close ties. This paper presents COGEMA LOGISTICS methods for collecting and analysing all these experiences waiting to be used. It explains our process for analysing data, preparing yearly reports that are made available to our designers. It describes how each new design is subject to a maintainability study, using this feedback, so that the cask safety is always assured, that radiological doses are kept to a minimum, and that operating and maintenance costs will remain as low as possible.

  13. Prospects and conclusion

    International Nuclear Information System (INIS)

    1994-01-01

    The present issue of 'Les Cahiers de COGEMAGAZINE', dedicated to role played by Cogema in the nuclear fuel cycling, ends with a short account on perspectives and concluding considerations. In the world nuclear fuel industry the most active zones appear to be France, Japan, China, Taiwan and Korea. A real expansion is to be expected in UO 2 market for PWRs. Also rapid development will be recorded by the production of MOF (mixed oxide fuels) especially due to the inception of British reprocessing plant at Thorp and the increase of number of MOF-fuelled reactors. The most significant lines of progress related to the new fuels are estimated to be: high burn-up (by increasing the resistance to fission gas pressure and irradiation), improvement of response to power excursions, fuel matrices of stronger retention, increase in the plutonium content of MOF, 100% MOF-fuelled reactors, optimizing the utilization of consumable poisons (for PWR) and very high burn-up and very long service lifetimes (for Breeders). In a nuclear environment, now in a rather low expansion rate, the French nuclear fuel industry enjoys the benefit of: an important national market, industrial experimented teams able to tackle all the steps from design to realization of a diversity of nuclear fuel types, fabrication facilities combining suppleness to clients' demands with requirements for high quality, a highly-rated worldwide position, and important capabilities of technological further development. An annex is added showing the percentage involvement of COGEMA and FRAMATOME in the fields of UO 2 -PuO 2 fuel production for PWR, fuels for Breeder, WER and experimental reactors and transport. Also participation of other European companies like PECHINEY, BELGONUCLEAIRE and SIEMENS is indicated

  14. Experience with contamination protection of spent fuel transport packages in Germany since 2000/2001

    International Nuclear Information System (INIS)

    Krinninger, H.; Bach, R.; Seidel, J.; Jung, P.

    2004-01-01

    On April 30, 1998 just a few days before the PATRAM 1998 conference at Paris, the French Nuclear Installations Safety Directorate (DSIN now DGSNR) published a press release, that during the year before some 35% of the spent fuel transports to the reprocessing plant of COGEMA at La Hague have non-fixed surface contamination in excess of the regulatory standard. A few day in advance DSIN informed in French Ministries and the competent foreign authorities of the customer countries of COGEMA. The consequences of this publication were multi-fold and perceived by the public as an act negligence of the nuclear industry. Because of concerns about additional radiation exposure to the railway workers by the unions the French Railway company SNCF suspended all transports by May 6, 1998 until implementation of corrective measures. This decision of SNF interupted also the spent fuel transports from continental Europe to the reprocessing plant of BNFL at Sellafield all performed across France to the port of Dunkirk. Furthermore on May 25, 1998 the German Federal Ministry of Environment, Nature Protection and Nuclear Safety (BMU) imposed a transport ban for shipment of spent fuel from commercial power plants and for high active waste returned from La Hague to the Gorleben site. The conditions for resumption of these transports were outlined by NMU in a 10-point programme. In response to these publications on contamination findings competent German State and Federal Authorities commissioned investigations by independent experts dealing with the identification of the causes, the proposal of counter measures, the investigation of shortcomings in the transport system in general and recommendations for retification of it

  15. Design of casks: incorporating operational feedback from maintenance

    International Nuclear Information System (INIS)

    Bimet, F.; Hartenstein, M.

    2004-01-01

    Casks are designed to conform to regulations and to client specifications. Essential areas such as easy operation, low costs of maintenance, low operation and maintenance doses, limited waste, are not explicitly covered. Notwithstanding, COGEMA LOGISTICS uses all feedback available, so that casks are designed to be easy, safe and economical to operate and maintain. Maintenance is an activity where you do spot items that old-time designers could have made better, and things that users should not have done. Thanks to quality assurance, there are a number of data available, waiting to be collected and exploited; they have to be identified, located, retrieved, and analysed. Using information such as wear, damage, use of spare parts, access problems helps to make casks ever better. It leads to more efficient concepts, and to upgrades on existing designs; it also allows to integrate environmental considerations, inter alia in the choice of materials and in maintenance methods. It is necessary for the designer to interact with the users, the cask owners, the maintenance providers, in order to gather all relevant information and events. This is made easier when all these actors are ''under one roof'', or have very close ties. This paper presents COGEMA LOGISTICS methods for collecting and analysing all these experiences waiting to be used. It explains our process for analysing data, preparing yearly reports that are made available to our designers. It describes how each new design is subject to a maintainability study, using this feedback, so that the cask safety is always assured, that radiological doses are kept to a minimum, and that operating and maintenance costs will remain as low as possible

  16. Evidence of lung cancer risk from animal studies

    International Nuclear Information System (INIS)

    Cross, F.T.

    1988-03-01

    Human epidemiological data provide the most important basis for assessing risks of radon exposures. However, additional insight into the nature of exposure-response relationships is provided by animal experimentation and dosimetric determinations. Animal studies have now been conducted for more than 50 years to examine the levels of pollutants in underground mines that were responsible for the respiratory effects observed among miners. This work has emphasized respiratory cancer and the interaction of radon with other agents, such as ore dust, diesel-engine-exhaust fumes and cigarette smoke. The more recent data on radon-daughter inhalation exposures were provided by two American research centers, The University of Rochester (UR) and the Pacific Northwest Laboratory (PNL), and by the Compagnie Generale des Matieres Nucleaires (COGEMA) laboratory in France. Approximately 2000 mice, 100 rats and 80 dogs were employed in the completed UR studies, begun in the mid 1950s; 800 hamsters, 5000 rats and 100 dogs in the ongoing PNL studies, begun in the late 1960s; and 10,000 rats in the ongoing COGEMA studies, also begun in the late 1960s. More complete updated biological effects, data resulting from chronic radon-daughter inhalation exposures of mice, hamsters, rats and beagle dogs were examined. Emphasis on the carcinogenic effects of radon-decay product exposure, including the influences of radon-daughter exposure rate, unattached fraction and disequilibrium, and co-exposures to other pollutants. Plausible values for the radon (radon-daughter) lifetime lung-cancer risk coefficients are also provided. 13 refs., 1 fig., 1 tab

  17. MOX fuel transport: the French experience

    International Nuclear Information System (INIS)

    Sanchis, H.; Verdier, A.; Sanchis, H.

    1999-01-01

    In the back-end of the fuel cycle, several leading countries have chosen the Reprocessing, Conditioning, Recycling (RCR) option. Plutonium recycling in the form of MOX fuel is a mature industry, with successful operational experience and large-scale fabrication plants an several European countries. The COGEMA Group has developed the industrialized products to master the RCR operation including transport COGEMA subsidiary, TRANSNUCLEAIRE has been operating MOX fuel transports on an industrial scale for more than 10 years. In 1998, around 200 transports of Plutonium materials have been organised by TRANSNUCLEAIRE. These transports have been carried out by road between various facilities in Europe: reprocessing plants, manufacturing plants and power plants. The materials transported are either: PuO 2 and MOX powder; BWR and PWR MOX fuel rods; BWR and PWR MOX fuel assemblies. Because MOX fuel transport is subject to specific safety, security and fuel integrity requirements, the MOX fuel transport system implemented by TRANSNUCLEAIRE is fully dedicated. Packaging have been developed, licensed and manufactured for each kind of MOX material in compliance with relevant regulations. A fleet of vehicles qualified according to existing physical protection regulations is operated by TRANSNUCLEAIRE. TRANSNUCLEAIRE has gained a broad experience in MOX transport in 10 years. Technical and operational know-how has been developed and improved for each step: vehicles and packaging design and qualification; vehicle and packaging maintenance; transport operations. Further developments are underway to increase the payload of the packaging and to improve the transport conditions, safety and security remaining of course top priority. (authors)

  18. BWR - Spent Fuel Transport and Storage with the TNTM9/4 and TNTM24BH Casks

    International Nuclear Information System (INIS)

    Wattez, L.; Marguerat, Y.; Hoesli, C.

    2006-01-01

    The Swiss Nuclear Utilities have started in 2001 to store spent fuel in dry metallic dual-purpose casks at ZWILAG, the Swiss interim storage facility. BKW FMB Energy Ltd., the Muehleberg Nuclear Power Plant owner, is involved in this process and has elected to store its BWR spent fuel in a new high capacity dual-purpose cask, the TNeTeM24BH from the COGEMA Logistics/TRANSNUCLEAR TN TM 24 family. The Muehleberg BWR spent fuels are transported by road in a medium size shuttle transport cask and then transferred to a heavy transport/storage cask (dry transfer) in the hot cell of ZWILAG site. For that purpose, COGEMA Logistics designed and supplied: - Two shuttle casks, TN TM 9/4, mainly devoted to transport of spent fuel from Muehleberg NPP to ZWILAG. Licensed according to IAEA 1996, the TN TM 9/4 is a 40 ton transport cask, for 7 BWR high bum-up spent fuel assemblies. - A series of new high capacity dual-purpose casks, TN TM 24BH, holding 69 BWR spent fuels. Two transport campaigns took place in 2003 and 2004. For each campaign, ten TN TM 9/4 round trips are performed, and one TN TM 24BH is loaded. 5 additional TN TM 24BH are being manufactured for BKW, and the next transport campaigns are scheduled from 2006. The TN TM 24BH high capacity dual purpose cask and the TN TM 9/4 transport cask characteristics and capabilities will then be detailed. (authors)

  19. Approaches to overall architecture of transport systems for spent fuel and high level waste: examples from Europe and Canada

    International Nuclear Information System (INIS)

    Roland, V.; Neider, T.

    2006-01-01

    As over the years, the nuclear industry worldwide was developing and building a clean, efficient and safe energy supply, it also built along the essential link for any global industry, transportation. The early approach at IAEA of creating international recommendations that then would be integrated into national laws came as a blessing to the structuration of transport This enabled a clear, recognized safety regime that has a proven world track record of outstanding safety. It also gave us a common language, and one may say that within the nuclear community, there is indeed a nuclear transport community. Because of steady and large flows of material for the nuclear cycles, countries where reprocessing of spent fuel takes place had to implement early on large transport structures and organizations. In most countries where reprocessing is not yet the main path for spent fuel management, like in the USA and in Canada, large scale transport for the back-end is still at the inception stage. Today the industry must demonstrate that waste is properly managed and that the peaceful use of nuclear energy delivers indeed the best economic and environmental value. Transport has to answer a part of this challenge if the industry is to grow further. The paper will illustrate how the current continental Europe systems of transport progressively evolved so as to make daily deliveries of spent nuclear fuel to the COGEMA La Hague reprocessing plant a strong, dependable and effective system. It also shows that this experience is in the background of a major study ordered by Ontario Power Generation from COGEMA Logistics, as a contribution to the work of the trust now examining approaches to long-term management of spent fuel in Canada. (author)

  20. Fuel integrity project: analysis of light water reactor fuel rods test results

    Energy Technology Data Exchange (ETDEWEB)

    Dallongeville, M.; Werle, J. [COGEMA Logistics (AREVA Group) (France); McCreesh, G. [BNFL Nuclear Sciences and Technology Services (United Kingdom)

    2004-07-01

    BNFL Nuclear Sciences and Technology Services and COGEMA LOGISTICS started in the year 2000 a joint project known as FIP (Fuel Integrity Project) with the aim of developing realistic methods by which the response of LWR fuel under impact accident conditions could be evaluated. To this end BNFL organised tests on both unirradiated and irradiated fuel pin samples and COGEMA LOGISTICS took responsibility for evaluating the test results. Interpretation of test results included simple mechanical analysis as well as simulation by Finite Element Analysis. The first tests that were available for analysis were an irradiated 3 point bending commissioning trial and a lateral irradiated hull compression test, both simulating the loading during a 9 m lateral regulatory drop. The bending test span corresponded roughly to a fuel pin intergrid distance. The outcome of the test was a failure starting at about 35 mm lateral deflection and a few percent of total deformation. Calculations were carried out using the ANSYS code employing a shell and brick model. The hull lateral compaction test corresponds to a conservative compression by neighbouring pins at the upper end of the fuel pin. In this pin region there are no pellets inside. The cladding broke initially into two and later into four parts, all of which were rather similar. Initial calculations were carried out with LS-DYNA3D models. The models used were optimised in meshing, boundary conditions and material properties. The calculation results compared rather well with the test data, in particular for the detailed ANSYS approach of the 3 point bending test, and allowed good estimations of stresses and deformations under mechanical loading as well as the derivation of material rupture criteria. All this contributed to the development of realistic numerical analysis methods for the evaluation of LWR fuel rod behaviour under both normal and accident transport conditions. This paper describes the results of the 3 point bending

  1. Fuel integrity project: analysis of light water reactor fuel rods test results

    International Nuclear Information System (INIS)

    Dallongeville, M.; Werle, J.; McCreesh, G.

    2004-01-01

    BNFL Nuclear Sciences and Technology Services and COGEMA LOGISTICS started in the year 2000 a joint project known as FIP (Fuel Integrity Project) with the aim of developing realistic methods by which the response of LWR fuel under impact accident conditions could be evaluated. To this end BNFL organised tests on both unirradiated and irradiated fuel pin samples and COGEMA LOGISTICS took responsibility for evaluating the test results. Interpretation of test results included simple mechanical analysis as well as simulation by Finite Element Analysis. The first tests that were available for analysis were an irradiated 3 point bending commissioning trial and a lateral irradiated hull compression test, both simulating the loading during a 9 m lateral regulatory drop. The bending test span corresponded roughly to a fuel pin intergrid distance. The outcome of the test was a failure starting at about 35 mm lateral deflection and a few percent of total deformation. Calculations were carried out using the ANSYS code employing a shell and brick model. The hull lateral compaction test corresponds to a conservative compression by neighbouring pins at the upper end of the fuel pin. In this pin region there are no pellets inside. The cladding broke initially into two and later into four parts, all of which were rather similar. Initial calculations were carried out with LS-DYNA3D models. The models used were optimised in meshing, boundary conditions and material properties. The calculation results compared rather well with the test data, in particular for the detailed ANSYS approach of the 3 point bending test, and allowed good estimations of stresses and deformations under mechanical loading as well as the derivation of material rupture criteria. All this contributed to the development of realistic numerical analysis methods for the evaluation of LWR fuel rod behaviour under both normal and accident transport conditions. This paper describes the results of the 3 point bending

  2. Second Annual Maintenance, Inspection, and Test Report for PAS-1 Cask Certification for Shipping Payload B

    International Nuclear Information System (INIS)

    KELLY, D.J.

    2000-01-01

    The Nuclear Packaging, Inc. (NuPac), PAS-1 cask is required to undergo annual maintenance and inspections to retain certification in accordance with U.S. Department of Energy (DOE) Certificate of Compliance USA/9184B(U) (Appendix A). The packaging configuration being tested and maintained is the NuPac PAS-1 cask for Payload B. The intent of the maintenance and inspections is to ensure the packaging remains in unimpaired physical condition. Two casks, serial numbers 2162-026 and 2162-027, were maintained, inspected, and tested at the 306E Development, Fabrication, and Test Laboratory, located at the Hanford Site's 300 Area. Waste Management Federal Services, Inc. (WMFS), a subsidiary of GTS Duratek, was in charge of the maintenance and testing. Cogema Engineering Corporation (Cogema) directed the operations in the test facility. The maintenance, testing, and inspections were conducted successfully with both PAS-1 casks. The work conducted on the overpacks included weighing, gasket replacement, and plastic pipe plug and foam inspections. The work conducted on the secondary containment vessel (SCV) consisted of visual inspection of the vessel and threaded parts (i.e., fasteners), visual inspection of sealing surfaces, replacement of O-ring seals, and a helium leak test. The work conducted on the primary containment vessel (PCV) consisted of visual inspection of the vessel and threaded parts (i.e., fasteners), visual inspection of sealing surfaces, replacement of O-ring seals, dimensional inspection of the vessel bottom, a helium leak test, and dye penetrant inspection of the welds. The vermiculite material used in the cask rack assembly was replaced

  3. The French development program for a UMo fuel

    International Nuclear Information System (INIS)

    Romano, R.; Nigon, J.L.; Languille, A.; Le Borgne, E.; Freslon, H.

    1999-01-01

    Until now high density U 3 Si 2 fuels were satisfactory for LEU conversion of certain reactors, but their use is limited because their density is physically limited to 5,8 gU/cm3 and they have very poor reprocessing capacities. After the end of the present US return policy in may 2006, the reactor operators will be indeed in a very difficult position with silicides. The international community is thus interested in a very high density fuel with good reprocessing capacities in order to convert most reactors and to find a back end solution. In France, CEA, CERCA, and COGEMA have thus launched an important program in order to sort potential candidates of uranium alloys. UMo is one of the most interesting candidates. After the selection of UMo alloys, France has pooled different skills to start an important program on UMo fuels: CEA has started an important project for a new reactor (Jules Horowitz); CERCA is the main manufacturer for MTR fuel; TECHNICATOME is the design expert for research reactors and associated cores; FRAMATOME is the parent company of CERCA and is interested in the development of new reactors; COGEMA is interested in reprocessing spent fuels. This new fuel has three aims: to allow reactors to benefit from a high performing fuel; to have a reprocessable fuel to limit the fuel storage period and the associate safety problem, and solve the back end issue; to support the international effort for non proliferation involving the end of the use of HEU. This high density fuel will decrease the number of fuel assemblies needed to run the reactors and decrease the global cost of the fuel cycle as the back end management cost is in proportion with the quantity of fuel. Reactor operators will thus derive an advantage from this new fuel, in terms of economy

  4. The future of nuclear energy in Europe

    International Nuclear Information System (INIS)

    Lauvergeon, A.

    2000-01-01

    More than 430 nuclear power plants are in operation in 33 countries worldwide. In 1999, they generated nearly 2.4 billion kilowatthours, thus meeting approximately one fifth of the world population's electricity requirement. Every third nuclear power plant is located in a member country of the European Union. These 145 plants generated an aggregate 826 billion kilowatthours last year. This corresponds to almost one third of the entire electricity generation in Europe. The special future requirements facing individual countries and power utilities not only ecologically, as a consequence of the Kyoto Protocol, but also economically, as a consequence of the deregulation of the European electricity market, make the intention of Germany to dispense with the use of nuclear power incomprehensible to the French point of view. Germany must pay special attention to fulfilling its international treaties and bilateral contracts, as Anne Lauvergeon, CEO of Cogema, explained in her presentation at the Bonn KTG conference. This applied in particular to the back end of the fuel cycle. In this respect, the head of Cogema argues that the waste and spent fuel management pathway must be chosen freely by the operator of a nuclear power plant. Within the safety requirements applying equally to all operators, the operator may freely decide under economic aspects whether he wants to recycle his spent fuel or dispose of it as waste. Only when this freedom of choice is guaranteed and used will it be ensured that the economically and technically best solution will win the day in the competition of systems. (orig.) [de

  5. Dry storage technologies: Optimized solutions for spent fuels and vitrified residues

    International Nuclear Information System (INIS)

    Roland, Vincent; Verdier, Antoine; Sicard, Damien; Neider, Tara

    2006-01-01

    In many countries, fuel cycle and waste policies influence the way operators organize waste management. These policies help drive progress and improvements in areas such as waste minimization programs, conditioning or industrial transformation before final or intermediate conditioning. The criteria that lead to different choices include economic factors, the presence or absence of a wide range of options such as transport, and reprocessing and recycling policies. The current international trend towards expanding Spent Fuel Interim Dry Storage capabilities goes with an improvement of the performance of the proposed systems which have to accommodate Spent fuel Assemblies characterized by ever increasing burn-up, fissile isotopes contents, thermal releases, and total inventory. Due to heterogeneous worldwide reactor pools and specific local constraints the proposed solutions have also to cope with a wide variety of fuel design. The Spent Fuel Assemblies stored temporarily for cooling may have to be transported either to reprocessing facilities or to interim storage facilities before direct disposal; it is the reason why the retrievability, including or not the need of transportation of the proposed systems, is often specified by the utilities for the design of their storage systems and sometimes required by law. In most cases, the producers of spent fuel require a large capacity that is cumulated over many years, each reload at a time. Then the key criterion is maximum modularity. Furthermore, the up front capital costs required for this type of solution has to be attractive for the investor. Two solutions, dual purpose metal casks of the TN TM 24 family or dual purpose or single purpose concrete shielded welded canisters such as NUHOMS R , implemented by COGEMA LOGISTICS, and TRANSNUCLEAR Inc. offer flexibility and modularity and have been adapted also to quite different fuels. Among what influences the choice, we can consider: - In favor of metal casks: Minimal

  6. 22. ATSR congress - Book of abstracts

    International Nuclear Information System (INIS)

    2004-10-01

    This document brings together the abstracts of all presentations given at the 22. congress of the French association for radiation protection techniques and sciences (ATSR) on the topic of the Management of a radiological emergency situation (Organisation and means): First plenary session - alert and first aid: 1 - Radiological and nuclear emergencies: a new doctrine, a new organisation (M. Bourguignon - DGSNR); 2 - Role and organisation of the Nuclear safety authority (M. Stoltz - DGSNR); 3 - The recasting of the nuclear specific intervention plans - PPI (P. Audebert - Ministry of Interior); 4 - Missions and organisation of the DSND - the Delegate for nuclear safety of defense, the safety authority of national defense (R. Isnard - Ministry of Defense); 5 - Management of radiological emergency situations by the IRSN (V. Chambrette - IRSN); Second plenary session - emergency medical measures: 6 - The Mobile radiological intervention units (CMIR) of fire brigades coping with nuclear accidents (D. Giordan - CMIR Yvelines); 7 - The medical organisation in front of radio-nuclear terrorism - SAMU Presentation (C. Telion - SAMU Paris); 8 - Presentation of the national guide of medical intervention in the case of nuclear or radiological event (J. Balosso, F. Loizzo - Grenoble teaching hospital); 9 - Nuclear accident: advantage and importance of stable iodine in accidental situation (P.Y. Hemidy - EDF); 10 - Place of biological dosimetry in accident crisis management (L. Roy - IRSN); 11 - Management of medical emergencies in nuclear environment - Cogema La Hague and Cherbourg hospital collaboration (P. Pradeau - Cogema la Hague); Third plenary session - Evaluation of consequences: 12 - Crisis tools developed at Meteo-France from the local to the international scale - Meteorological data transmission (F. Bonnardot - Meteo France); 13 - IRSN's radiological consequences unit (A. Thomassin - IRSN); 14 - National crisis organisation at CEA at last exercises experience feedback

  7. French industrial capabilities for the back-end operations

    International Nuclear Information System (INIS)

    Caspar, Gilles A.

    1988-01-01

    Based upon processes initiated by the Commissariat a l'Energie Atomique and its industrial partners, France has been elaborating for about thirty years a steady and consistent programme for the back-end fuel cycle. French industrial actors for each segment of this cycle are shown in annex. The CEA is the research and development national entity sustaining the industrial efforts of the French companies involved in all stages of the fuel cycle : enrichment, fabrication, reprocessing, radwaste management. Such a cooperation assistance is devoted to processes developments, equipment qualification, engineering back up, as this will be reviewed along present communication. As well known, mastering a new technology from fundamental research to full scale industrial deployment, requires time and considerable financial commitments. Both CEA and COGEMA have devoted the requested time and funds to reach an effective industrialization of the closed fuel cycle. This industrial achievement is now completed. UP2 La Hague reprocessing unit produces effectively over 40 T per month and its capacity will be doubled to reach a nominal production of 800 T per year available in 1993 for our EDF domestic utility. It has recently reprocessed the two thousandth ton of LWR fuel and treated in 1987 over 400 T of the same, thus exceeding the nominal capacity. On the same site our UP3 unit under construction will be operating next year with a capacity of also 800 tons per year devoted to foreign utilities. Last year, in view of our excellent operational experience, Cogema reassessed the whole financial scheme for both plants including maintenance and refurbishing expenses. We may confirm that the reprocessing cost, after base load period ending in year 1999, will be reduced by 30 to 40%. The once through option does not effectively solve the spent fuel problem since to-day nobody has qualified an ultimate repository site associated with a licensed reliable process for irradiated fuel embedding

  8. Transparency and dialogue: the keys of radioactive material transportation

    International Nuclear Information System (INIS)

    Neau, H.J.; Hartenstein, M.

    2004-01-01

    Today, public opinion, local actors, organizations and associations are expecting a transparent information on nuclear activities. The fact is, a great number already has daily instant access to information and is able to share it very quickly, thanks to new technologies. Public opinion's sensitiveness is a key element, as risk remains at the center of public concerns. The discrepancy between objectively assessed risks and perceived risks is a permanent challenge for acceptance of nuclear energy. The opponents are also using it, to build their misleading strategy. When anti-nuclear groups claim for an increasing involvement in the decision-making processes, they also get there the most efficient means to hamper our activities, namely operational information on the nuclear transport activities. In order to tackle this challenging issue, COGEMA and its parent company AREVA are engaged in improving their information policy. It has been extended to international and national transports commissioned by COGEMA LOGISTICS. Regarding the most recent transport operations, specific information policy has been implemented at the national and local level through media, information committees, trade unions. But, on the one hand, this policy is facing limits: transparency and openness stop where sensitivity and confidentiality start. On the other hand, opponents are building a challenging process, which is ''more and more''. Whatever the industry efforts are, opponents will remain unsatisfied as they cannot afford otherwise.Consequently, we need to assume a proactive policy in the field of the information on safety of radioactive material transportation. But above all, this policy must be dedicated to the public opinion. It must not be a way to answer to opponent's attacks. The industry's transparency and information must support public opinion's understanding of the important issues which are on progress: global access to the energy, preservation of the environment, providing

  9. Transparency and dialogue: the keys of radioactive material transportation

    Energy Technology Data Exchange (ETDEWEB)

    Neau, H.J.; Hartenstein, M. [COGEMA Logistics (AREVA Group) (France)

    2004-07-01

    Today, public opinion, local actors, organizations and associations are expecting a transparent information on nuclear activities. The fact is, a great number already has daily instant access to information and is able to share it very quickly, thanks to new technologies. Public opinion's sensitiveness is a key element, as risk remains at the center of public concerns. The discrepancy between objectively assessed risks and perceived risks is a permanent challenge for acceptance of nuclear energy. The opponents are also using it, to build their misleading strategy. When anti-nuclear groups claim for an increasing involvement in the decision-making processes, they also get there the most efficient means to hamper our activities, namely operational information on the nuclear transport activities. In order to tackle this challenging issue, COGEMA and its parent company AREVA are engaged in improving their information policy. It has been extended to international and national transports commissioned by COGEMA LOGISTICS. Regarding the most recent transport operations, specific information policy has been implemented at the national and local level through media, information committees, trade unions. But, on the one hand, this policy is facing limits: transparency and openness stop where sensitivity and confidentiality start. On the other hand, opponents are building a challenging process, which is ''more and more''. Whatever the industry efforts are, opponents will remain unsatisfied as they cannot afford otherwise.Consequently, we need to assume a proactive policy in the field of the information on safety of radioactive material transportation. But above all, this policy must be dedicated to the public opinion. It must not be a way to answer to opponent's attacks. The industry's transparency and information must support public opinion's understanding of the important issues which are on progress: global access to the energy

  10. 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

  11. Radium 226 and lead 210 water extraction from mill tailings samples

    International Nuclear Information System (INIS)

    Fourcade, N.; Zettwoog, P.; Mery, G.

    1994-01-01

    Depositories for waste from the processing of uranium ore may release seepage waters into the environment through their impoundments. Seepage waters, when percolating through the wastes, extract radium 226. In the design or rehabilitation stage of such depositories, the exposure of critical groups of the population to radium 226 from the ground water pathway must be assessed. The same applies to lead 210. The first step is to assess the possibility of extracting the radium 226 and the lead 210 from samples of solid wastes and sludges in laboratory tests using water from the site. Extensive tests of this type were carried out in our laboratories between 1982 and 1991 on samples of mill tailings which had been collected in six installations of COGEMA and its subsidiaries. The main results are presented and analyzed. Physical, chemical and mineralogical factors influencing the leaching rates and the total quantity of water-extractable radium 226 are identified. In the case of a wet storage option, a tentative modelling of the water extraction phenomenon is proposed for the prediction of the source term both in the short term, and in the long term when all more or less soluble salts have been eliminated from the solid wastes

  12. Institute of Nuclear Waste Management Technology (INE). 1994 progress report on research and development

    International Nuclear Information System (INIS)

    1995-01-01

    In 1994 INE worked on the following research projects: radionuclide behaviour during corrosion of high-level radioactive COGEMA glass; studies of glassy basalt of the Werra-Fulda salt deposit as a natural analogue of the corrosion of HAW glass; corrosion studies of high burnup LWR fuels in brine; chemical behaviour of Tc in aqueous, chloride systems; corrosion studies of waste container materials; solution chemistry of U; thermodynamics of Np(V) in concentrated brines; radiation-chemical effects in the vicinity of repositories; laser spectroscopic speciation and thermodynamics of Cm(III); development of laser spectroscopic methods; radiochemical and chemical analyses of nuclear samples; solid-state and surface analyses; coupling of transport and speciation models; influence of colloid formation on the migration behaviour of long-lived radionuclides; studies of the consolidation behaviour of filling material; thermomechanical effects of inhomogeneities in the salt dome; basic studies and process engineering developments in the field of solidification of high-level radioactive fission product solutions; corrosion behaviour of WAK-HAW containing glass products in brines. (orig./HP) [de

  13. The yawning chasm of French nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The financial problems of the nuclear power industry in France are explained. Cogema, the waste reprocessing company ventured into the French financial futures market and lost money. It is trying to sue its brokers over this disaster. Framatome, the State reactor manufacturer is trying to diversify into aeronautics, electronics and foodstuffs. The electric utility EdF is sliding into debt and, with no price rise allowed, this situation will get worse. Theoretically EdF should be delivering cheap electricity from nuclear power stations. However, French electricity prices are not significantly cheaper than those of Germany and the United Kingdom. The generating capacity will increase greatly over the next few years. The availability of existing plants is also improving. In spite of efforts to export its electricity (about 10% is exported) EdF seem unable to make its extra electricity cheaper and is heavily in debt. The fast breeder programme has also not lived up to expectations due to a sodium leak at Superphenix. (U.K.)

  14. Nuclear power, society and environment

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    2 subjects are treated: the regular public opinion poll ordered by CEA, EdF, COGEMA and FRAMATOME and the denuclearization of one of the nuclear research center belonging to CEA. Every year in december the BVA polling institute leads a public opinion poll about how nuclear activities are perceived by people. This year about 1000 people have been questioned about the French nuclear power program, radioactivity, safety in nuclear facilities, nuclear wastes, information and public debates. The most meaningful result is that now fewer people think that nuclear energy will play a major role in 10 or 20 years. More people now think that radioactivity even at very low doses is dangerous. In 1946 the ZOE reactor was built on the site of the ancient stronghold of Chatillon which became the nuclear research center of Fontenay-aux-roses in april 1957. From 1958 to 1962 ZOE and a pilot unit of spent fuel reprocessing were dismantled. The test reactor Triton whose definitive shutdown took place in 1982, underwent a complete decontamination, as for Minerve reactor it was removed to Cadarache. The hot laboratories in which methods concerning the fabrication of plutonium fuels, the reprocessing and the handling of high activity wastes have been settled and tested, are due to be dismantled. 20 hot cells, 134 glove boxes and about 100 tanks of liquid effluents are involved. CEA has budgeted 910 millions of francs for the complete denuclearization of this site, it will be over in 2010. (A.C.)

  15. Test operation of the uranium ore processing pilot plant and uranium conversion plant

    International Nuclear Information System (INIS)

    Suh, I.S.; Lee, K.I.; Whang, S.T.; Kang, Y.H.; Lee, C.W.; Chu, J.O.; Lee, I.H.; Park, S.C.

    1983-01-01

    For the guarantee of acid leaching process of the Uranium Ore Processing Pilot Plnat, the KAERI team performed the test operation in coorperation with the COGEMA engineers. The result of the operation was successful achieving the uranium leaching efficiency of 95%. Completing the guarentee test, a continuous test operation was shifted to reconform the reproducibility of the result and check the functions of every units of the pilot plant feeding the low-grade domestic ore, the consistency of the facility was conformed that the uranium can easily be dissolved out form the ore between the temperature range of 60degC-70degC for two hours of leaching with sulfuric acid and could be obtained the leaching efficiency of 92% to 95%. The uranium recovery efficiencies for the processes of extraction and stripping were reached to 99% and 99.6% respectively. As an alternative process for the separation of solid from the ore pulp, four of the Counter Current Decanters were shifted replacing the Belt Filter and those were connected in a series, which were not been tested during the guarantee operation. It was found out that the washing efficiencies of the ore pulp in each tests for the decanters were proportionally increased according to the quantities of the washing water. As a result of the test, it was obtained that washing efficiencies were 95%, 85%, 83% for the water to ore ratio of 3:1, 2:1, 1.5:1 respectively. (Author)

  16. Overseas uranium exploration by PNC

    International Nuclear Information System (INIS)

    Nagashima, Reiji; Iida, Yoshimasa; Shigeta, Naotaka; Takahashi, Osamu; Yamagishi, Akiko; Miyada, Hatsuho; Kobayashi, Takao

    1998-01-01

    Japan entirely depends on overseas countries for uranium resources for its nuclear electric power generation due to the lack of domestic resources. In order to secure a steady supply of natural uranium, Japanese government has implemented a long-term procurement policy through purchase contracts by private sectors, subsidizing private sectors' exploration and initial stage exploration outside the reach of private sectors' activity by PNC (Power Reactor and Nuclear Fuel Development Corporation). The subsequent long slump in the price of uranium, however, led most of Japanese private sectors to discontinue their exploration activity. Upon this situation, PNC has pursued a little more advanced stage exploration in addition to basic research and initial stage exploration and has improved its exploration techniques to enable the discovery of deep-seated uranium ore deposits. As the result, PNC has acquired significant uranium exploration tenements and interests similar to those owned by major uranium companies such as Cameco and Cogema. PNC has also contributed to discovery of new uranium deposits. In this report, the history of PNC's activities and its role in the long-term uranium procurement policy are reviewed and it is also described about the outcome thorough its activities and future exploration trend and the tasks. (author)

  17. 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)

  18. Nuclear safety: transparency in radioactive clouds

    International Nuclear Information System (INIS)

    Bondy, J.Ph.

    2002-01-01

    The supervision of industry and defence on French radiation protection and withhold information during public inquiries in nuclear facilities questions make organizations anxious. Two examples are given: the first one concerns the file presented by EDF in november 1998 to get new release authorizations on the st Alban site, some information about tritium lacked( thirty analysis on tritium lacked for impact studies) and tritium is an element that represents 99.99% of released radioactivity by the nuclear power plant in the Rhone river. The Crirad organization asked for the public inquiry canceling. In vain. The second example is relative to the reprocessing plant of La Hague; at the end of 1999 the Cogema wished to extend its fuel range and increase its treatment capacity then it dropped off a file of public inquiry that did not take into account the increase of radioactive releases. The operator did not want the file to wear on this aspect, it won one's case. (N.C.)

  19. A general approach for quantifying the heat-ageing of gaskets

    International Nuclear Information System (INIS)

    Andre, R.; Malesys, P.

    2004-01-01

    A recurrent concern in the design of packaging for the transportation of radioactive material is to determine the elastomeric gaskets life at high temperature. Most gasket suppliers specify maximum allowable temperatures during ''continuous service'' and ''peak service'' (such as ''200 C in continuous service'' or ''250 C in peak'') but they do not specify the definition of ''continuous'' or ''peak'' service, what are the acceptance criteria and how these maximum temperatures are determined. Based on this type of data, it is difficult to assess the acceptability of a gasket submitted to fluctuating temperatures. COGEMA LOGISTICS has launched a test program on the different rubber grades used on its casks to determine, for different temperature levels (e.g. 200 C, 210 C,.., 250 C..), the maximum seal life based on clearly defined criteria. The goal is to establish, for each rubber grade, the seal life versus temperature curve. These curves can be used to know if a gasket exposed to any specified temperature profile can guarantee the leaktightness. The principle of the method is to calculate a sum of ''elementary damage rates'' on the temperature profile (split up into elementary time intervals) and to compare this sum (the ''global damage rate'') to a ''aximum permissible damage rate''. If the global damage rate is lower than the maximum permissible damage rate, the leaktightness of the packaging can be guaranteed for the given temperature profile

  20. System Definition Document: Reactor Data Necessary for Modeling Plutonium Disposition in Catawba Nuclear Station Units 1 and 2

    International Nuclear Information System (INIS)

    Ellis, R.J.

    2000-01-01

    The US Department of Energy (USDOE) has contracted with Duke Engineering and Services, Cogema, Inc., and Stone and Webster (DCS) to provide mixed-oxide (MOX) fuel fabrication and reactor irradiation services in support of USDOE's mission to dispose of surplus weapons-grade plutonium. The nuclear station units currently identified as mission reactors for this project are Catawba Units 1 and 2 and McGuire Units 1 and 2. This report is specific to Catawba Nuclear Station Units 1 and 2, but the details and materials for the McGuire reactors are very similar. The purpose of this document is to present a complete set of data about the reactor materials and components to be used in modeling the Catawba reactors to predict reactor physics parameters for the Catawba site. Except where noted, Duke Power Company or DCS documents are the sources of these data. These data are being used with the ORNL computer code models of the DCS Catawba (and McGuire) pressurized-water reactors

  1. Report of Activity, July 1995 - June 1997; Rapport d`activite Juillet 1995 - Juin 1997

    Energy Technology Data Exchange (ETDEWEB)

    Tamain, B. [Lab. de Physique Corpusculaire, Caen Univ., 14 (France)

    1997-12-31

    The LPC (Laboratoire de Physique Corpusculaire) dedicated the major part of its 50 years activity to the Physics of Heavy Ions research conducted at GANIL. The activity in last two years on which this report is focused refers to this domain. Of special priority was the topics of hot and /or compressed nuclear matter aiming at understanding the physics of multifragmentation.The new ionization chambers INDRA and development of control programming required special efforts. A second direction of activity was the study of exotic nuclei particularly of halo nuclei. Specific equipment like the multi-detectors of DEMON and TAPS were designed for approaching the hot nuclei. Projects based on SPIRAL beams and collaborations dedicated to investigation of different new branches of exotic radioactivity ({beta}, xn: TONNERRE project) or mechanisms of induced fusion by radioactive nuclei to produce superheavy nuclei are reported on. The LPC was implied also in two important research programs, PRACEN and GEDEON (treatment of radioactive wastes) which made clear the evolution of research for the next two years: the correct understanding of the mechanisms of light particle production in neutron induced collisions at 20 to 200 MeV. In the frame of NEMO Collaboration that approaches topics related to the weak interactions the Laboratory has developed and tested the trigger system of NEMO3. A program utilizing ion trapping on SPIRAL for efficient studies on {beta}-neutrino angular correlations in superallowed decays will be thus feasible. Contracts like COGEMA and DAMRI oriented toward applied research are also mentioned

  2. International

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    This rubric reports on 10 short notes about international economical facts about nuclear power: Electricite de France (EdF) and its assistance and management contracts with Eastern Europe countries (Poland, Hungary, Bulgaria); Transnuclear Inc. company (a 100% Cogema daughter company) acquired the US Vectra Technologies company; the construction of the Khumo nuclear power plant in Northern Korea plays in favour of the reconciliation between Northern and Southern Korea; the delivery of two VVER 1000 Russian reactors to China; the enforcement of the cooperation agreement between Euratom and Argentina; Japan requested for the financing of a Russian fast breeder reactor; Russia has planned to sell a floating barge-type nuclear power plant to Indonesia; the control of the Swedish reactor vessels of Sydkraft AB company committed to Tractebel (Belgium); the renewal of the nuclear cooperation agreement between Swiss and USA; the call for bids from the Turkish TEAS electric power company for the building of the Akkuyu nuclear power plant answered by three candidates: Atomic Energy of Canada Limited (AECL), Westinghouse (US) and the French-German NPI company. (J.S.)

  3. 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

  4. Calculation code evaluating the confinement of a nuclear facility in case of fires

    International Nuclear Information System (INIS)

    Laborde, J.C.; Prevost, C.; Vendel, J.

    1995-01-01

    Accident events involving fire are quite frequent and could have a severe effect on the safety of nuclear facilities. As confinement must be maintained, the ventilation and filtration systems have to be designed to limit radioactive release to the environment. To determine and analyse the consequences of a fire on the contamination confinement, IPSN, COGEMA and SGN are participating in development of a calculation code based on introduction, in the SIMEVENT ventilation code, of various models associated to fire risk and mass transfer in the ventilation networks. This calculation code results from the coupling of the SIMEVENT code with several models describing the temperature in a room resulting of a fire, the temperatures along the ventilation ducts, the contamination transfers through out the ventilation equipments (ducts, dampers, valves, air cleaning systems) and the High Efficiency Particulate Air (HEPA) filters clogging. The paper proposed presents the current level of progress in development of this calculation code. It describes, in particular, the empirical model used for the clogging of HEPA filters by the aerosols derived from the combustion of standard materials used in the nuclear industry. It describes, also, the specific models used to take into account the mass transfers and resulting from the basic mechanisms of aerosols physics. In addition, an assessment of this code is given using the example of a simple laboratory installation

  5. Headlines... Areva on the way toward centrifugation

    International Nuclear Information System (INIS)

    Anon.

    2004-01-01

    The French industrial group Areva, that gathers Cogema and Framatome-ANP, has entered into a partnership with the British nuclear consortium Urenco for creating ETC (enrichment technology company) in order to replace its uranium enrichment facility (Georges-Besse-I) that is planned to close in 2012 by a new one (George-Besse-II) that will enter into service as early as 2007. The new facility will be based on the centrifugation technique developed by Urenco, this technique will cut the consumption of electricity by 3 in comparison with the gaseous diffusion technique used in the Georges-Besse-I facility. The other asset of the centrifugation technique is that the facility can grow with the number of centrifuges that are set. In 2007 only 7% of the total number of centrifuges will be installed, which will sufficient to satisfy the demand for enriched uranium. The full size of the facility will be reached in 2016 through gradual steps of 10% more centrifuges set every year. (A.C.)

  6. Report of Activity, July 1995 - June 1997

    International Nuclear Information System (INIS)

    Tamain, B.

    1997-01-01

    The LPC (Laboratoire de Physique Corpusculaire) dedicated the major part of its 50 years activity to the Physics of Heavy Ions research conducted at GANIL. The activity in last two years on which this report is focused refers to this domain. Of special priority was the topics of hot and /or compressed nuclear matter aiming at understanding the physics of multifragmentation.The new ionization chambers INDRA and development of control programming required special efforts. A second direction of activity was the study of exotic nuclei particularly of halo nuclei. Specific equipment like the multi-detectors of DEMON and TAPS were designed for approaching the hot nuclei. Projects based on SPIRAL beams and collaborations dedicated to investigation of different new branches of exotic radioactivity (β, xn: TONNERRE project) or mechanisms of induced fusion by radioactive nuclei to produce superheavy nuclei are reported on. The LPC was implied also in two important research programs, PRACEN and GEDEON (treatment of radioactive wastes) which made clear the evolution of research for the next two years: the correct understanding of the mechanisms of light particle production in neutron induced collisions at 20 to 200 MeV. In the frame of NEMO Collaboration that approaches topics related to the weak interactions the Laboratory has developed and tested the trigger system of NEMO3. A program utilizing ion trapping on SPIRAL for efficient studies on β-neutrino angular correlations in superallowed decays will be thus feasible. Contracts like COGEMA and DAMRI oriented toward applied research are also mentioned

  7. Design of an experiment to measure the decay heat of an irradiated PWR fuel: MERCI experiment; Conception d'une experience de mesure de la puissance residuelle d'un combustible irradie: l'experience MERCI

    Energy Technology Data Exchange (ETDEWEB)

    Bourganel, St

    2002-11-01

    After a reactor shutdown, a significant quantity of energy known as 'decay heat' continues to be generated from the irradiated fuel. This heat source is due to the disintegration energy of fission products and actinides. Decay heat determination of an irradiated fuel is of the utmost importance for safety analysis as the design cooling systems, spent fuel transport, or handling. Furthermore, the uncertainty on decay heat has a straight economic impact. The unloading fuel spent time is an example. The purpose of MERCI experiment (irradiated fuel decay heat measurement) consists in qualifying computer codes, particularly the DARWIN code system developed by the CEA in relation to industrial organizations, as EDF, FRAMATOME and COGEMA. To achieve this goal, a UOX fuel is irradiated in the vicinity of the OSIRIS research reactor, and then the decay heat is measured by using a calorimeter. The objective is to reduce the decay heat uncertainties from 8% to 3 or 4% at short cooling times. A full simulation on computer of the MERCI experiment has been achieved: fuel irradiation analysis is performed using transport code TRIPOLI4 and evolution code DARWIN/PEPIN2, and heat transfer with CASTEM2000 code. The results obtained are used for the design of this experiment. Moreover, we propose a calibration procedure decreasing the influence of uncertainty measurements and an interpretation method of the experimental results and evaluation of associated uncertainties. (author)

  8. Determination of 93Zr, 107Pd and 135Cs in zircaloy hulls analytical development on inactive samples

    International Nuclear Information System (INIS)

    Excoffier, E.; Bienvenu, Ph.; Combes, C.; Pontremoli, S.; Delteil, N.; Ferrini, R.

    2000-01-01

    A study involving the participation of three laboratories of the Direction of the Fuel Cycle has been undertaken within the framework of a common interest program existing between the COGEMA and the CEA. Its purpose is to develop analytical methods for the determination of long-lived radionuclides in zircaloy hulls coming from spent fuel reprocessing operations. Acting as a complement to work carried out at the DRRV in ATALANTE concerning zircaloy dissolution and direct analysis of hull solutions, a study is now being conducted at the DESD/SCCD/LARC in Cadarache on three of these radionuclides, namely: zirconium 93, palladium 107 and caesium 135. It concerns three radioisotopes having very long periods (∼10 6 y), and which stabilize mainly through emission of β particles. The analytical technique chosen for the final measurement is inductively coupled plasma mass spectrometry (ICP/MS). Prior to the measurement, chemical separation processes are used to extract the radionuclides from the matrix and separate them from interfering elements and β emitters. The method developed initially on inactive solutions is being validated on irradiated samples coming from UP2/800 - UP3 reprocessing plants. (authors)

  9. Men and their land. The mining sites of the Mokta French Company in Lozere

    International Nuclear Information System (INIS)

    1994-09-01

    This booklet summarizes the history of the mining activity in the Lozere district (France) devoted to the extraction of uranium ores. This activity started in 1957 with the open cast exploitation of the Cellier deposit which lasted 35 years and produced 4200 t of uranium from 5800000 t of ore. The exploitation was performed by the French Company of Uranium Ores (CFMU). The uranium crisis started in 1962 and led to an increase of prospecting activities. The crisis ended with the first oil crack in 1973 and the uranium demand and prices grew up until 1979 when the Three Mile Island reactor accident occurred. The second crisis that followed led to the development of new recovery processes such as the heap lixiviation process. In 1980, the CFMU became the French Company of Mokta (CFM) and in 1986, the CFM became a 100% daughter company of the Cogema group. The exploitation of the Bondons mine ended in 1989 and the program of site rehabilitation started. The document focusses on the environmental aspects of this program, the reforestation, the drainage of surface waters and the control of water quality. (J.S.)

  10. Men and their land. The mining sites of the Mokta French Company in Lozere; Des hommes et leur terre. Les sites miniers de la Compagnie Francaise de Mokta en Lozere

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    This booklet summarizes the history of the mining activity in the Lozere district (France) devoted to the extraction of uranium ores. This activity started in 1957 with the open cast exploitation of the Cellier deposit which lasted 35 years and produced 4200 t of uranium from 5800000 t of ore. The exploitation was performed by the French Company of Uranium Ores (CFMU). The uranium crisis started in 1962 and led to an increase of prospecting activities. The crisis ended with the first oil crack in 1973 and the uranium demand and prices grew up until 1979 when the Three Mile Island reactor accident occurred. The second crisis that followed led to the development of new recovery processes such as the heap lixiviation process. In 1980, the CFMU became the French Company of Mokta (CFM) and in 1986, the CFM became a 100% daughter company of the Cogema group. The exploitation of the Bondons mine ended in 1989 and the program of site rehabilitation started. The document focusses on the environmental aspects of this program, the reforestation, the drainage of surface waters and the control of water quality. (J.S.)

  11. Review of BNFL's operational experience of wet type flasks

    International Nuclear Information System (INIS)

    McWilliam, D.S.

    2004-01-01

    BNFL International Transport's operational experience includes shipping 6000te of spent fuel from Japan to Sellafield, through its dedicated terminal at Barrow, and to Cogema La Hague. This fuel was shipped under the PNTL (Pacific Nuclear Transport Ltd) banner for which BNFL is responsible. PNTL owned and operated a fleet of 5 ships for Japanese business and a fleet of 80 wet and 58 dry flasks, for the transport of Light Water Reactor (LWR) spent fuel, from both Pressurised Water Reactors (PWR) and Boiling Water Reactors (BWR). ''Wet'' or ''dry'' flask is the common terminology used to distinguish between spent fuel flasks transporting fuel where the fuel is immersed in water, or spent fuel flasks that have been drained of water and dried. This paper concentrates on the wet type of flask utilised to transport fuel to Sellafield, that is the Excellox type (including similar type NTL derivatives). It aims to provide a summary of operational experience during handling at power stations, shipment, unloading at reprocessors and from scheduled maintenance

  12. 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

  13. 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)

  14. French en engineering and operation rules for plutonium facilities

    International Nuclear Information System (INIS)

    Bertolotti, G.; Drain, F.; Dubois, G.; Monnatte, J.; Mathieu, P.

    1998-01-01

    COGEMA is operating large size purifying and conditioning plutonium facilities at LA HAGUE and MOX fuels fabrication plant at Marcoule. A high safety standard is recognised for these facilities. It is mainly based on : - prevention of spreading of radioactive materials to workers and environment by physical barriers ensuring static containment and by a cascade of pressure differentials ensuring dynamic containment, - radiation shielding and remote controlled processes ensuring very low dose to workers, - prevention of criticality accident by criticality control methods and double contingency principle, - prevention of fire risks by control of ignition sources, adequate management of combustible materials, physical separation between zones where there is a risk of fire and the remainder of the facility. The facilities are operated while respecting safety requirements as described in the General Operating Rules. The equipment involved in safety functions are monitored and periodically checked. Continuous improvement by incorporation of feed back of safety experience results in: - effective decrease of exposure to operating staff; - reduction of solid waste, liquid and gaseous effluents; - no significant incident recorded. (author)

  15. Leaching behavior of a simulated bituminized radioactive waste form under deep geological conditions

    International Nuclear Information System (INIS)

    Nakayama, Shinichi; Iida, Yoshihisa; Nagano, Tetsushi; Akimoto, Toshiyuki

    2003-01-01

    The leaching behavior of a simulated bituminized waste form was studied to acquire data for the performance assessment of the geologic disposal of bituminized radioactive waste. Laboratory-scale leaching tests were performed for radioactive and non-radioactive waste specimens simulating bituminized waste of a French reprocessing company, COGEMA. The simulated waste was contacted with deionized water, an alkaline solution (0.03-mol/l KOH), and a saline solution (0.5-mol/l KCl) under atmospheric and anoxic conditions. The concentrations of Na, Ba, Cs, Sr, Np, Pu, NO 3 , SO 4 and I in the leachates were determined. Swelling of the bituminized waste progressed in deionized water and KOH. The release of the soluble components, Na and Cs, was enhanced by the swelling, and considered to be diffusion-controlled in the swelled layers of the specimens. The release of sparingly soluble components such as Ba and Np was solubility-limited in addition to the progression of leaching. Neptunium, a redox-sensitive element, showed a distinct difference in release between anoxic and atmospheric conditions. The elemental release from the bituminized waste specimens leached in the KCl was very low, which is likely due to the suppression of swelling of the specimens at high ionic strength. (author)

  16. Incineration ashes conditioning by isostatic pressing and melting

    International Nuclear Information System (INIS)

    Jouan, A.; Ouvrier, N.; Teulon, F.

    1990-01-01

    Alpha-bearing solid incineration wastes are conditioned for two principal reasons: to enhance the quality of the finished product for long-term storage, and to reduce the total waste volume. Isostatic pressing parameters were defined using containers 36 mm in diameter; the physicochemical properties of the compacted ashes were determined with 140 mm diameter containers and industrial feasibility was demonstrated with a large (300 mm diameter) container. Two types of ashes were used: ashes fabricated at Marcoule (either in devices developed by the CEA for the MELOX project with a standard MELOX composition, or by direct incineration at COGEMA's UP1 plant) and fly ash from a domestic waste incinerator. A major engineering study was also undertaken to compare the three known ash containment processes: isostatic pressing, melting, and cement-resin matrix embedding. The flowsheet, operational chronology and control principles were detailed for each process, and a typical plant layout was defined to allow comparisons of both investment and operating costs

  17. Development of a new neutron shielding material, TN trademark Resin Vyal for transport/storage casks for radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    Abadie, P. [COGEMA Logistics (AREVA Group), Saint-Quentin-en-Yvelines (France)

    2004-07-01

    TN trademark Resin Vyal, a patent pending composite, is a new neutron shielding material developed by COGEMA LOGISTICS for transport/storage casks of radioactive materials (spent fuel, reprocessed fuel,..). This material is composed of a thermosetting resin (vinylester resin in solution of styrene) and two mineral fillers (alumine hydrate and zinc borate). Its shielding ability for neutron radiation is related to a high hydrogen content (for slowing down neutrons) and a high boron content (for absorbing neutrons). Source of hydrogen is organic matrix (resin) and alumine hydrate; source of boron is zinc borate. Atomic concentrations are equal to 5.10{sup 22} at/cm{sup 3} for hydrogen and 9.10{sup 20} at/cm{sup 3} for boron. Due to the flame retardant character of components, the final material has a good fire resistance (it is auto-extinguishable). Its density is equal to 1,8. The manufacturing process of these material is easy: it consists in mixing the fillers and pouring in-situ (in cask); so, the curing of this composite, which leads to a three-dimensional structure, takes place at ambient temperature. Temperature resistance of this material was evaluated by performing exposition tests of samples at different temperatures (150 C to 170 C). According to tests results, its maximal temperature of use was confirmed equal to 160 C.

  18. Assessing environmental and health impact of the nuclear fuel cycle. Methodology and application to prospective actinides recycling options

    International Nuclear Information System (INIS)

    Garzenne, Claude; Grouiller, Jean-Paul; Le Boulch, Denis

    2005-01-01

    French Industrial Companies: EDF, AREVA (COGEMA and FRAMATOME-ANP), associated with ANDRA, the organization in charge of the waste management in France, and Public Research Institute CEA and IRSN, involved in the nuclear waste management, have developed in collaboration a methodology intended to assess the environmental and health impact of the nuclear fuel cycle. This methodology, based on fuel cycle simulation, Life Cycle Analysis, and Impact Studies of each fuel cycle facilities, has been applied to a set of nuclear scenarios covering a very contrasted range of waste management options, in order to characterize the effect of High Level Waste transmutation, and to estimate to what extent it could contribute to reduce their overall impact on health and environment. The main conclusion we could draw from this study is that it is not possible to discriminate, as far as health and environmental impacts are concerned, nuclear scenarios implementing very different levels of HLW transmutation, representative of the whole range of available options. The main limitation of this work is due to the hypothesis of normal behavior of all fuel cycle facilities: main future improvement of the methodology would be to take the accidental risk into account. (author)

  19. Contribution to the modeling of elaborate cement barriers behaviour with respect to radioelements migration by the study of ancient analogue materials; Apport de l`etude de materiaux analogues anciens a la modelisation du comportement des barrieres ouvragees en ciment vis-a-vis de la migration des radioelements

    Energy Technology Data Exchange (ETDEWEB)

    Rougeau, P

    1994-10-13

    The durability of cement matrices and their capacity of radioelements retention are determining factors for their use as elaborate barriers in radioactive waste disposal facilities. This study focusses on the observation of concretes in real situation of alteration or in contact with radioelements for predictive modelling. Two materials have been selected. One is a concrete from a gallery wall of the Margnac uranium mine (Cogema, France) submitted to uranium-rich infiltration waters. The alteration concentrates in two characteristic successive zones: the first is composed of calcium depleted and aluminum enriched calcite and calcium hydro-silicates and the second, between the first zone and the sound matrix, is characterized by a self-filling in process due to massive ettringite precipitation induced by sulfate ions transport. Uranium migration depends closely on the fissures and porosity of the cement matrix. The second series of samples correspond to 2000 years old archaeological cements from Pompei (Italy) made of volcanic ashes and carrying uranium traces. These samples were submitted to burying and alteration is characterized by a carbonation of the cement matrix. The mineralogy is closed to the one defined in the first alteration zone of the uranium mine concrete. Both studies demonstrate that the presence of carbonate ions in the percolation water plays a major role in the alteration process. Sulfate reactions must be considered too and tend to diminish the materials porosity and to increase the delay in radionuclides migration processes. (J.S.). 131 refs., 92 figs., 55 tabs., 51 photos., 15 appends.

  20. Transport and storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Lung, M.; Lenail, B.

    1987-01-01

    From a safety standpoint, spent fuel is clearly not ideal for permanent disposal and reprocessing is the best method of preparing wastes for long-term storage in a repository. Furthermore, the future may demonstrate that some fission products recovered in reprocessing have economic applications. Many countries have in fact reached the point at which the recycling of plutonium and uranium from spent fuel is economical in LWR's. Even in countries where this is not yet evident, (i.e., the United States), the French example shows that the day will come when spent fuel will be retrieved for reprocessing and recycle. It is highly questionable whether spent fuel will ever be considered and treated as waste in the same sense as fission products and processed as such, i.e., packaged in a waste form for permanent disposal. Even when recycled fuel material can no longer be reused in LWR's because of poor reactivity, it will be usable in FBR's. Based on the considerable experience gained by SGN and Cogema, this paper has provided practical discussion and illustrations of spent fuel transport and storage of a very important step in the nuclear fuel management process. The best of spent fuel storage depends on technical, economic and policy considerations. Each design has a role to play and we hope that the above discussion will help clarify certain issues

  1. Public opinion research in France: A new approach through people's values understanding

    International Nuclear Information System (INIS)

    Bres-Tutino, France; Pages, Jean-Pierre; Leger, Laurent

    1998-01-01

    Nuclear energy perception by the public has not only technical aspects but is also relevant to public debate and related to people's values. The developed countries and affluent societies, have been showing, in particular, a shift towards post-materialist values. Some of these values and needs environment protection, quality of life, involvement in decision-making process (government, corporates) must be taken into account when analysing public opinion towards nuclear energy. That is the reason why since 1992 a yearly nuclear barometer survey has been run, jointly, by the main corporations involved in nuclear research and industry CEA, the French Atomic Energy Commission, COGEMA, EDF and FRAMATOME. This barometer includes not only quantitative indicators but also, several series of questions on public attitude towards risk perception, controversial issues discussed in the media, potential energy sources for the future, politicians credibility etc. In addition, a very detailed public segmentation allows researchers to analyse similarities and differences related to age, gender, level of education of the population. This paper intends to give some concrete examples and current results on French public attitude towards nuclear energy and on the relation between social values and support for nuclear power

  2. Economics of the back-end of fuel cycle: Controversy, uncertainties and the industrial evidence

    International Nuclear Information System (INIS)

    Guais, J.C.

    1987-01-01

    This paper underlines the usefulness of the document issued by OECD/NEA on the ''economics of the nuclear fuel cycle,'' as a reference methodology. As regards the technical and costs assumptions, we feel that COGEMA as the most important reprocessor to date has accumulated a large industrial experience allowing a better knowledge of the various costs included in the back-end operations, from spent fuel transportation handling and storage, to reprocessing and wastes conditioning. A comparative analysis of the two main options for the fuel cycle: reprocessing/recycling versus once-through, is performed on these grounds. In the economic conditions prevailing in Western Europe and in Japan, the resulting cost comparison is in favor of the reprocessing/recycling cycle. The authors conclude that economics is important as it is, is not the only criteria to be considered then assessing the back-end options: overall strategy, energy policy, environmental consideration and public acceptance are the other view-points to use to reach a sound decision in this field

  3. Nuclear energy communications in France: gaining public confidence

    International Nuclear Information System (INIS)

    Chaussade, J.-P.

    1990-01-01

    Nuclear power plants today are an accepted part of the French landscape; a total of 54 units have been constructed on some 20 different sites. They have been relatively well accepted by the general public and, in particular, by those people living in the vicinity of plants. This favourable situation, however, did not come about automatically - it required a great deal of effort in terms of public information, starting during the 1970s. This effort must be maintained, especially since public confidence in nuclear energy was severely shaken by the Chernobyl accident. Our success in pursuing France's planned construction programme depends on our ability to build on this confidence. Indeed, since 1987, we have had to rethink our communications strategy. However, Electricite de France (EDF) is not alone in this; public authorities, the SCSIN (an Industry Department equivalent to the NRC), CEA (French atomic energy commission), in its capacity as a research organisation, together with plant constructor Framatome and nuclear fuel company Cogema, all have a role to play in this communications drive. The key to our communications campaign lies in listening to public opinion. Opinion polls and qualitative surveys allow us to judge public awareness and pinpoint expectations and concerns. This article summarises the main surveys we have carried out. (3 figures) (Author)

  4. Treatment of solid waste highly contaiminated by alpha emitters

    International Nuclear Information System (INIS)

    Madic, C.; Breschet, C.; Vigreux, 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 nucleaires 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, Y contamination levels; to recover the plutonium, a 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. 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

  5. Review of 1992 industry developments

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The year 1992 was remarkable for a number of major events that affected the market. The key developments can be categorized in areas such as supply restrictions, legislative and political events, industry consolidations, reactor and mine closures as well as start-ups, and achievements at assorted fuel cycle operations. Clearly, the most influential event was the US uranium anti-dumping investigation, but other significant developments included Euratom's actions restricting imports of CIS-origin uranium into the European Community, continuing upheaval and evolution of the market-based economies of the CIS and central Europe, the second-most active year ever in the uranium spot market, the formation of ConverDyn and the indefinite shutdown of Sequoyah Fuels, Cogema's purchase of Urangesellschaft, passage of a US Energy Bill, China's signing of the Non-Proliferation Treaty, renewed progress on Taiwan's fourth nuclear station, formation of the Japanese fuel cycle corporation JNFL, premature closure of three US reactors for economic reasons, and several mergers and acquisitions that further consolidated the uranium and nuclear industries. As a whole, the past year will be looked back on by market participants as a year of turning point, both good and bad, in the evolution of the industry

  6. OMIRIS educational tool

    International Nuclear Information System (INIS)

    Dumont, X.; Artus, J.C.; Gonin, M.; Bidard, F.; Hickman, B.

    2004-01-01

    The biological effects of ionizing radiations are one of the most important issues for workers exposed to these radiations in nuclear plants. To deliver information to workers about this topic, the 'Utility Medical Work Officers' wanted an educational tool. This tool named 'OMIRIS' was prepared under the authority of the federation of professors in radiology, radiobiology and radioprotection and the industrial nuclear partners in France (ANDRA, AREVA/COGEMA and FRAMATOME-ANP, CEA and EDF). The use of animation techniques helps to present in a simple way this complex topic using an interactive, pleasant and comprehensible form. Detailed information is given about 5 themes: 1) the various sources of ionizing radiation whatever they are natural, medical, industrial or military; 2) the various types of exposure, whether internal or external, their characteristics: duration, target organs and radiological toxicity and the different means of protection; 3) the concept of dose, the importance of dose rate and the reference values of doses; 4) the biological effects on the human organism, notions of dose threshold and aims, results and limitations of epidemiological surveys; and 5) the regulation based on radiological protection studies

  7. Melox west fitting building a major contribution towards an enhanced flexibility

    International Nuclear Information System (INIS)

    Fraize, G.; Belmont, J.M.; Bouzon, P.

    1998-01-01

    As of April 1, 1998, 28 European Light Water Reactors (LWR) have been loaded with MOX fuel. In the near future (by 2010), up to 50 reactors should be 'moxified' in Europe. and about 15 in Japan. The trend towards expanding MOX fuel utilization in LWRs is based on very good records of in-core performances. Indeed, the accumulated experience (more than 1000 MOX fuel assemblies loaded in the European reactors) demonstrates MOX fuel performances as excellent and comparable for reactors operations to UO 2 fuel. To cope with the growing MOX fuel demand, some countries have equipped themselves (or should equip themselves in the near future) with the state-of-art MOX industrial capabilities. This growing demand is obviously linked with a higher diversity in fuel designs requirements. The empowerment of the MELOX plant, the first high-throughput MOX fuel fabrication facility in operation in the world, is in keeping with this situation. Utilities have to face the market moves, and their expectations towards fuel suppliers are changing. The MELOX West Fitting Building (MWFB) resulting from an optimized design know-how, is the demonstration of the COGEMA Group high capability of adaptation. With the MWFB, the completion of a versatile fabrication plant adapted to the international fuel market will be reached. (author)

  8. Transfer shuttle for vitrified residue canisters control of risks associated with external exposure and heat release

    Energy Technology Data Exchange (ETDEWEB)

    BIndel, L.; Gamess, A.; Lejeune, E.; Cellier, P.; Maillard, A. [SGN Reseau Eurisys, 78 - Saint Quentin (France)

    1998-07-01

    In the La Hague COGEMA's plant area, nuclear residue isolated by reprocessing are transported by means of specific transfer shuttles between the different processing and/or conditioning facilities and the storage ones. These shuttles are designed by reference to the applicable dose equivalent rate (DER) limits for transport on the site and the thermal behavior limitations of certain mechanical components which guarantee the containment of the transported waste. This paper describes and example of a study conducted on a transfer shuttle for vitrified residue canisters. Concerning the control of risks associated with external exposure and with heat releases, these were handled by the 'Shielding-Criticality-Dispersion' and 'process Modelling and Simulation' Sections of the Technical Division of SGN. The dose profiles around the shuttle, as a function of the shielding heterogeneities and possible radiation leakage, as well as the thermal fields within the shuttle, were calculated using 3D models. These design studies ultimately helped to select and validate the optimal solutions. (authors)

  9. Post graduate course of radiation protection. V. 1-2; Cours post-universitaire de radioprotection. V. 1-2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    In September 1991, the General Conference of IAEA, in the resolution GC/XXXV/RES/552 demanded the Director General to formulate the propositions in the field of education and teaching of radiation protection. After its meeting in 1993, the General Conference (document GC/XXXVII/1067) a program of education in radiation protection and nuclear safety. The IAEA has chosen L'Instut national des science et techniques nucleaires (INSTN) de Saclay, France, to perform the french training for its long-term education in nuclear field. During the nine weeks in May and June 1994, 24 participants from 22 countries attended 80 courses presented by 70 teachers. The organizers have attained a successful cooperation of competent French organizations in the field of radiation protection and nuclear safety as: Institut de protection et de surete nucleaire (IPSN), Commissariat a l'energie atomique (CEA), Compagnie generales des matieres nucleaires (COGEMA), Agence nationale pour la gestion de dechets radioactif (ANDRA), Office de protection contre les raynnements ionisants (OPRI), Electicite de France (EDF), as well as outstanding specialists in the medical field. The series of these lectures are presented in these two volumes. Admitting that the education and training in the field of radiation protection and nuclear safety are responsibilities of national authorities the IAEA hopes that this published material would be widely used by the Member States as a basis for their training programs in the mentioned field.

  10. Chernobyl: exclusive investigation. How the French nuclear lobby buries the truth in contaminated areas. The After-Chernobyl or 'Living happy' in contaminated area

    International Nuclear Information System (INIS)

    2006-01-01

    According to the results of this inquiry, the CEPN (study centre on assessment of protection in the nuclear sector) has been created by the main actors of the nuclear industrial sector (EFG, Cogema, CEA and IRSN) and is at the origin of the ETHOS and CORE projects. Moreover, these projects have been financed by public funds. It also shows that the FNSEA (farmer trade union) has been allied to the French nuclear lobby for the distribution probably contaminated and radioactive foodstuff. It evokes the case of Belarus researcher who denounced such contamination and the misappropriation of international funds, and who was sent to jail. It comments the collaboration between the French nuclear sector and the Belarus regime, denounces how the truth about Chernobyl has been hidden, the cynical results of the ETOS program which would imply the consumption of contaminated foodstuff in France in case of nuclear accident. Some proposals are made: to dismantle the CEPN, to stop the participation of French organisations to the CORE and FARMING programs, creation of an independent commission on the consequences of the Chernobyl accident, and so on. For the authors, phasing out nuclear is the only solution o avoid a new Chernobyl

  11. The rock Saskatchewan

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    These have been pretty rough times for Uranium producers. Whether they are going to get better anytime soon is open to debate. But one thing is certain: If any producer is going to meet the challenges ahead, it's Cameco. When it comes to uranium, there is no question that Cameco is a global powerhouse. Cameco is capable of supplying about 15% of Western World uranium demand [120 million pounds]. It is arguably the world's lowest-cost producer, primarily because it owns the highest-grade ore deposits in the world at Key Lake and Rabbit Lake in the uranium-rich Athabasca basin of Saskatchewan. [Cameco owns two-thirds of and operates Key Lake and Rabbit Lake; the other third is owned by Uranerz Exploration ampersand Mining]. The ore grades at these two mines are 1.6% uranium at Key Lake and 2% at Rabbit Lake, surpassing the average ore grades of Cameco's chief competitors, Cogema of France and ERA of Australia. Furthermore, Cameco operates and owns the lion's share of several undeveloped mines that contain some of the richest ore in the world

  12. SEPA (Service d'etudes, de Procedes et Analyses)

    International Nuclear Information System (INIS)

    2017-01-01

    The SEPA (Service d'etudes, de Procedes et Analyses), is an engineering department specializing in the analysis and processing of uranium ore. It comes from a long tradition of mining in France that began sixty-five years ago with the French Atomic Energy Commission (CEA) and that has been carried on by COGEMA and then Areva. SEPA brings a combination of experience and excellence to its activities thanks to its multidisciplinary staff (mineralogists, chemists, mechanical engineers, instrumentation specialists...), who come from diverse cultural backgrounds. Today, the SEPA draws on its wealth of know-how and expertise to devise and develop new methods for processing and valorizing ores everywhere in the world. Its mission is to: - Develop and conduct laboratory tests on methods for processing uranium and other valuable elements such as molybdenum, vanadium, rare earths, niobium, tantalum and thorium; - Analyze ores obtained during prospecting at locations all over the world; -Serve as an advisor in the commissioning of Areva industrial units and ore processing plants; -Perform environmental analyses during the full period of mining operations; -Conduct audits and provide advice on processes and analysis methods; -Carry out research and development in all aspects of minerals treatment (including the filing of patents). The SEPA combines experience, skills and a global approach to technologies used in ore processing. Its role is to continually improve the processes for extracting, processing and valorizing ores while protecting the environment

  13. Nuclear fuel supply continues to be cheap and secure

    International Nuclear Information System (INIS)

    Braatz, U.; Dibbert, H.J.

    1985-01-01

    The fuel supply for German nuclear power stations has been secured in the long term in all the individual circuit stages. There are problems because of existing overcapacity worldwide on the suppliers' side. The worldwide throttling of natural uranium production has proved to be a possible way of supporting uranium prices. Because of the stagnant market for longterm contracts, there is still worry among uranium producer regarding further development of the market. The 1984 turnover on the spot market for natural uranium has nearly trebled compared with the previous year. The excess uranium conversion capacity in this sector caused low capacity utilisation and led to offers with considerable reductions. Turbulence with its epicentre in the USA has a feature of the separation work market. The centrifuge enrichers are better placed regarding production costs than the gas diffusion enrichers even with low capacity utilisation and use this advantage. The gas diffusion plants were only at half load, which led to new contract offers from DOE and to competitive prices with long term guaranteed discounts offered by COGEMA. The laser enrichment process was great interest to all energy producing countries. The use of recovered uranium and plutonium is still in the experimental stage. In view of the growing quantities of plutonium, the use of MOX in thermal reactors is growing in importance. (orig./HP) [de

  14. Nucleaire et Energies Nr 63 - June 2014. 18 months before the Paris Climate Conference

    International Nuclear Information System (INIS)

    Lenail, Bernard; Ducroux, Guy; Lamorlette, Guy; Seyve, Claude; Simonnet, Jacques; Justin, Francois; Darricau, Aime; Blanc, Jacques; Salanave, Jean-Luc; Raisonnier, Daniele; Deleigne, Francoise

    2014-06-01

    After a first article which evokes the perspective and challenges of the Paris Climate Conference, two articles address energy issues: a discussion of the evolution of the energy sector (challenge of energy transition, evolutions of the energy mix in different countries, shale gases in the USA, Europe and France, electricity prices in France, situation and projects of French energy companies) and an overview of news in the renewable energy sector (in Morocco, Germany and the UK, the second bidding for offshore wind projects in France). Three articles deal with nuclear energy: agreements and projects in Niger, news about various fuel production sites in different countries, overview of the situation of reactors (EPR, China) and decisions on projects and investments in different countries, overview of activities and events related to the back-end of the fuel cycle (notably in different Areva sites) and to decommissioning in different countries. Four articles address societal issues related to nuclear safety and environment (relationships between French nuclear operators and Safety Authorities, the situation of populations around Fukushima, Greenpeace in Fessenheim, the issue of fuel sheath wear, use of rare earth materials in wind turbines), a positive perception of the presence of Areva (after Cogema) in Niger, a scenario for Fessenheim, and the deep disposal Cigeo project

  15. Post graduate course of radiation protection. V. 1-2

    International Nuclear Information System (INIS)

    1995-01-01

    In September 1991, the General Conference of IAEA, in the resolution GC/XXXV/RES/552 demanded the Director General to formulate the propositions in the field of education and teaching of radiation protection. After its meeting in 1993, the General Conference (document GC/XXXVII/1067) a program of education in radiation protection and nuclear safety. The IAEA has chosen L'Instut national des science et techniques nucleaires (INSTN) de Saclay, France, to perform the french training for its long-term education in nuclear field. During the nine weeks in May and June 1994, 24 participants from 22 countries attended 80 courses presented by 70 teachers. The organizers have attained a successful cooperation of competent French organizations in the field of radiation protection and nuclear safety as: Institut de protection et de surete nucleaire (IPSN), Commissariat a l'energie atomique (CEA), Compagnie generales des matieres nucleaires (COGEMA), Agence nationale pour la gestion de dechets radioactif (ANDRA), Office de protection contre les raynnements ionisants (OPRI), Electicite de France (EDF), as well as outstanding specialists in the medical field. The series of these lectures are presented in these two volumes. Admitting that the education and training in the field of radiation protection and nuclear safety are responsibilities of national authorities the IAEA hopes that this published material would be widely used by the Member States as a basis for their training programs in the mentioned field

  16. PROMETHEE: a versatile R and D measurement device for low level waste assay

    International Nuclear Information System (INIS)

    Romeyer Dherby, J.; Passard, C.; Mariani, A.

    1996-01-01

    The accurate measurement of heavy nuclide masses and activities in radioactive wastes drums is an important part of waste management. The Active/Passive non destructive assay of radioactive waste drums using a 14 MeV neutron generator is particularly interesting for alpha low level measurements or for gamma irradiating wastes. The development, optimisation, and validation of such a device for industrial use necessitate the building of a demonstrator. In 1985, the CEA decided to build at Cadarache the PROMETHEE modular system for experimenting the pulsed generator techniques, and since then, this device has led us to define several specific systems. At the present time, in the frame of COGEMA actions to reduce the volume of the reprocessing waste, a new strategy of drumming and incineration 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 goal, a developments and tests are carried out on the PROMETHEE research and development facility at CEA CADARACHE, in order to obtain the required performances

  17. PROMETHEE: a versatile R and D measurement device for low level waste assay

    Energy Technology Data Exchange (ETDEWEB)

    Romeyer Dherby, J.; Passard, C.; Mariani, A

    1996-12-31

    The accurate measurement of heavy nuclide masses and activities in radioactive wastes drums is an important part of waste management. The Active/Passive non destructive assay of radioactive waste drums using a 14 MeV neutron generator is particularly interesting for alpha low level measurements or for gamma irradiating wastes. The development, optimisation, and validation of such a device for industrial use necessitate the building of a demonstrator. In 1985, the CEA decided to build at Cadarache the PROMETHEE modular system for experimenting the pulsed generator techniques, and since then, this device has led us to define several specific systems. At the present time, in the frame of COGEMA actions to reduce the volume of the reprocessing waste, a new strategy of drumming and incineration 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 goal, a developments and tests are carried out on the PROMETHEE research and development facility at CEA CADARACHE, in order to obtain the required performances.

  18. Characterization of alpha low level waste in 118 litre drums by passive and active neutron measurements in the promethee assay system

    International Nuclear Information System (INIS)

    Jallu, F.; Passard, C.; Mariani, A.; Ma, J.L.; Baudry, G.; Romeyer-Dherbey, J.; Recroix, H.; Rodriguez, M.; Loridon, J.; Denis, C.; Toubon, H.

    2003-01-01

    This paper deals with the PROMETHEE (PROMpt, epithermal and THErmal interrogation experiment) waste assay system for alpha low level waste (LLW) characterization. This device, including both passive and active neutron measurement methods, is developed at the French Atomic Energy Commission (C.E.A.), Cadarache Centre, in cooperation with COGEMA. Its purpose is to reach the requirements for incinerating alpha waste (less than 50 Bq[α], i.e. about 50 μg of Pu per gram of raw waste) in 118 litre- > drums. The PROMETHEE development and progress are performed with the help of simulation based on the Monte Carlo code MCNP4 [1]. These calculations are coupled with specific experiments in order to confirm calculated results and to obtain characteristics that can not be approached by the simulation (background for example). This paper presents the PROMETHEE measurement cell, its current performances, and studies performed at the laboratory about the most limiting parameters such as the matrix of the drum - its composition (H, Cl..), its density and its heterogeneity degree -the localization and the self-shielding properties of the contaminant. (orig.)

  19. Characterization of alpha low level waste in 118 litre drums by passive and active neutron measurements in the promethee assay system

    Energy Technology Data Exchange (ETDEWEB)

    Jallu, F.; Passard, C.; Mariani, A.; Ma, J.L.; Baudry, G.; Romeyer-Dherbey, J.; Recroix, H.; Rodriguez, M.; Loridon, J.; Denis, C. [French Atomic Energy Commission (C.E.A./Cadarache), DED/SCCD/LDMN, Durance (France); Toubon, H. [COGEMA, VELIZY-VILLACOUBLAY (France)

    2003-07-01

    This paper deals with the PROMETHEE (PROMpt, epithermal and THErmal interrogation experiment) waste assay system for alpha low level waste (LLW) characterization. This device, including both passive and active neutron measurement methods, is developed at the French Atomic Energy Commission (C.E.A.), Cadarache Centre, in cooperation with COGEMA. Its purpose is to reach the requirements for incinerating alpha waste (less than 50 Bq[{alpha}], i.e. about 50 {mu}g of Pu per gram of raw waste) in 118 litre-<> drums. The PROMETHEE development and progress are performed with the help of simulation based on the Monte Carlo code MCNP4 [1]. These calculations are coupled with specific experiments in order to confirm calculated results and to obtain characteristics that can not be approached by the simulation (background for example). This paper presents the PROMETHEE measurement cell, its current performances, and studies performed at the laboratory about the most limiting parameters such as the matrix of the drum - its composition (H, Cl..), its density and its heterogeneity degree -the localization and the self-shielding properties of the contaminant. (orig.)

  20. New methodology for source location and activity determination in preparation of repairing or decommissioning activities

    International Nuclear Information System (INIS)

    Toubon, H.; Boudergui, K.; Pin, P.; Nohl, B.; Lefevre, S.; Chiron, M.

    2006-01-01

    The operations of dismantling of nuclear installations are often difficult due to the lack of knowledge about the position, the identification and the radiological characteristics of the contamination. To avoid the manual mapping and simply sampling and radiochemical analysis, which takes time and causes doses new tools are now used: - CARTOGAM to detect the position of the activity and the relative dose rates of the different hot spots, - NaI, CZT or Ge gamma spectrometers to characterize the major radionuclides, - a model with ISOCS gamma attenuation code or MERCURAD-PASCALYS gamma attenuation and dose rate evaluation code CARTOGAM and MERCURAD were developed in collaboration with CEA and COGEMA. All these tools are used to build a complete methodology to give adapted solutions to the nuclear facilities. This methodology helps to prepare for and execute decontamination and dismantling activities. After describing the methodology, examples are given of its use in preparation of repairing at an EDF NPP site and in dismantling operations at a CEA site. These examples give concrete insights into their significance and the productivity gains they offer. (authors)

  1. Report of Activity, July 1995 - June 1997; Rapport d`activite Juillet 1995 - Juin 1997

    Energy Technology Data Exchange (ETDEWEB)

    Tamain, B [Lab. de Physique Corpusculaire, Caen Univ., 14 (France)

    1998-12-31

    The LPC (Laboratoire de Physique Corpusculaire) dedicated the major part of its 50 years activity to the Physics of Heavy Ions research conducted at GANIL. The activity in last two years on which this report is focused refers to this domain. Of special priority was the topics of hot and /or compressed nuclear matter aiming at understanding the physics of multifragmentation.The new ionization chambers INDRA and development of control programming required special efforts. A second direction of activity was the study of exotic nuclei particularly of halo nuclei. Specific equipment like the multi-detectors of DEMON and TAPS were designed for approaching the hot nuclei. Projects based on SPIRAL beams and collaborations dedicated to investigation of different new branches of exotic radioactivity ({beta}, xn: TONNERRE project) or mechanisms of induced fusion by radioactive nuclei to produce superheavy nuclei are reported on. The LPC was implied also in two important research programs, PRACEN and GEDEON (treatment of radioactive wastes) which made clear the evolution of research for the next two years: the correct understanding of the mechanisms of light particle production in neutron induced collisions at 20 to 200 MeV. In the frame of NEMO Collaboration that approaches topics related to the weak interactions the Laboratory has developed and tested the trigger system of NEMO3. A program utilizing ion trapping on SPIRAL for efficient studies on {beta}-neutrino angular correlations in superallowed decays will be thus feasible. Contracts like COGEMA and DAMRI oriented toward applied research are also mentioned

  2. Sampling of charged liquid radwaste stored in large tanks

    International Nuclear Information System (INIS)

    Tchemitcheff, E.; Domage, M.; Bernard-Bruls, X.

    1995-01-01

    The final safe disposal of radwaste, in France and elsewhere, entails, for liquid effluents, their conversion to a stable solid form, hence implying their conditioning. The production of conditioned waste with the requisite quality, traceability of the characteristics of the packages produced, and safe operation of the conditioning processes, implies at least the accurate knowledge of the chemical and radiochemical properties of the effluents concerned. The problem in sampling the normally charged effluents is aggravated for effluents that have been stored for several years in very large tanks, without stirring and retrieval systems. In 1992, SGN was asked by Cogema to study the retrieval and conditioning of LL/ML chemical sludge and spent ion-exchange resins produced in the operation of the UP2 400 plant at La Hague, and stored temporarily in rectangular silos and tanks. The sampling aspect was crucial for validating the inventories, identifying the problems liable to arise in the aging of the effluents, dimensioning the retrieval systems and checking the transferability and compatibility with the downstream conditioning process. Two innovative self-contained systems were developed and built for sampling operations, positioned above the tanks concerned. Both systems have been operated in active conditions and have proved totally satisfactory for taking representative samples. Today SGN can propose industrially proven overall solutions, adaptable to the various constraints of many spent fuel cycle operators

  3. 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)

  4. 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)

  5. 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.)

  6. Development of a new neutron shielding material, TN trademark Resin Vyal for transport/storage casks for radioactive materials

    International Nuclear Information System (INIS)

    Abadie, P.

    2004-01-01

    TN trademark Resin Vyal, a patent pending composite, is a new neutron shielding material developed by COGEMA LOGISTICS for transport/storage casks of radioactive materials (spent fuel, reprocessed fuel,..). This material is composed of a thermosetting resin (vinylester resin in solution of styrene) and two mineral fillers (alumine hydrate and zinc borate). Its shielding ability for neutron radiation is related to a high hydrogen content (for slowing down neutrons) and a high boron content (for absorbing neutrons). Source of hydrogen is organic matrix (resin) and alumine hydrate; source of boron is zinc borate. Atomic concentrations are equal to 5.10 22 at/cm 3 for hydrogen and 9.10 20 at/cm 3 for boron. Due to the flame retardant character of components, the final material has a good fire resistance (it is auto-extinguishable). Its density is equal to 1,8. The manufacturing process of these material is easy: it consists in mixing the fillers and pouring in-situ (in cask); so, the curing of this composite, which leads to a three-dimensional structure, takes place at ambient temperature. Temperature resistance of this material was evaluated by performing exposition tests of samples at different temperatures (150 C to 170 C). According to tests results, its maximal temperature of use was confirmed equal to 160 C

  7. Status of the McClean project, Saskatchewan, Canada

    International Nuclear Information System (INIS)

    Giroux, M.

    1997-01-01

    The paper describes the status of development of the McClean Lake uranium production project. The project includes development of a new mine/mill complex located 10 kilometres west of the Rabbit Lake mine site, in the Athabaska region of northern Saskatchewan, Canada. This first Canadian uranium project since Key Lake was developed in the late 1970s, is planned to help provide the increasing need for uranium production during the rest of the 1990s and beyond. The report describes the geological model for the 6 unconformity-type uranium orebodies named: JEB; Sue A, B and C; and McClean Lake A and B. These deposits will be extracted using both open pit and underground mines. The report describes the history of exploration and development, as well as the progression of the environmental clearance process under the joint review panel of the Canadian and Saskatchewan governments. The Canadian $250 million project, operated by Cogema Resources, is jointly owned by Denison Mines Limited, Minatco Limited and OURD (Canada) Company Limited. It is scheduled to start producing uranium concentrate in 1997. (author). 1 ref., 10 figs

  8. Trace determination of Pu by LIF in an inductively coupled plasma

    International Nuclear Information System (INIS)

    Mauchien, P.; Briand, A.; Moulin, C.

    1989-01-01

    Inductively Coupled Plasma/Emission Spectrometry (ICP/ES) technique is largely used in the nuclear industry as an elementary analytical technique. Nevertheless, when the sample to analyse presents elements with a lot of emission spectral lines, spectral interferences lead to limited sensitivity. This is the case for Pu determination in presence of large U concentration. In pure aqueous solution, the limit of detection (LOD) for Pu is 10 μg/1. In presence of U, the LOD is determined by a ratio U/Pu = 1000. Pulsed Laser Induced Fluorescence (LIF) spectrometry is known to be a very selective technique when associated with an Inductively Coupled Plasma source. The absolute sensitivity is better by 2 or 3 orders of magnitude; its principle is based on selective excitation of the ionic species in the plasma followed by fluorescence radiation detection of these species; this radiation being practically free from spectral interferences, it is possible to improve the relative LOD. In this presentation, experimental results performed at Cogema/Marcoule laboratory are presented. After the experimental set-up description, first results of LIF are shown: - very good selectivity is effectively obtained, - a series of analytical results obtained with excitation scanning from the visible to the U.V. show that sensitivity of LIF technique is strictly related to the spectroscopic scheme

  9. 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

  10. Methodological approach of the North-Cotentin radioecological group in charge of the evaluation of doses and risks due to the radiations exposure of the North-Cotentin population

    International Nuclear Information System (INIS)

    Sugierr, A.

    1999-01-01

    The group has evaluated and validated the list and quantities of radioelements release(source term) for each of the four nuclear installations of the North Cotentin since their beginning of operation (the reprocessing plant of Cogema la Hague, the Flamanville nuclear power plant, the Manche storage plant and the arsenal of the Cherbourg harbour). The gathering of data relative to radionuclides in environment of the north Cotentin has allowed from one hand the publication of samples inventory and types of radioactivity measurements and in an other hand an analysis of the results. The intercomparison of transfer models in environment and the confrontation of their results with the measures have been used for the doses calculations to the references groups and to the children troop from the Beaumont-Hague district. Finally, the elements necessary to the doses and risks estimation have been itemized and validated. One of the questions that stands out of these works is this one of the aims of the surveillance and measurements in environment according to the different organisms that realize them. It is important to make the distinction between the routine measurements ( to be sure of the correct operation of the facility and that the authorized release limits are well respected) and the measurements that allow to reconstitute the dose to population groups. (N.C.)

  11. Coherence of reactor design and fuel element design

    International Nuclear Information System (INIS)

    Vom Scheidt, S.

    1995-01-01

    Its background of more than 25 years of experience makes Framatome the world's leading company in the design and sales of fuel elements for pressurized water reactors (PWR). In 1994, the fuel fabrication units were incorporated as subsidiaries, which further strengthens the company's position. The activities in the fuel sector comprise fuel element design, selection and sourcing of materials, fuel element fabrication, and the services associated with nuclear fuel. Design responsibility lies with the Design and sales Management, which closely cooperates with the engineers of the reactor plant for which the fuel elements are being designed, for fuel elements are inseparable parts of the respective reactors. The Design and Sales Management also has developed a complete line of services associated with fuel element inspection and repair. As far as fuel element sales are concerned, Framatome delivers the first core in order to be able to assume full responsibility vis-a-vis the customer for the performance of the nuclear steam supply system. Reloads are sold through the Fragema Association established by Framatome and Cogema. (orig.) [de

  12. Annual progress report 1980

    International Nuclear Information System (INIS)

    1981-01-01

    The technical support activities of the IPSN to competent administrations in 1980 has been marked: namely by the authorizations of divergence for 9 units EdF-PWR of 900 MW, the authorization project of creation and extension of reprocessing plant of COGEMA at the Hague UP 2 -800 and the authorization of starting up of the third unit of production of the EURODIF enrichment plant at Tricastin. On the other hand, IPSN has participated at the elaboration of a certain number of legislative and regulation texts relative to the control of nuclear matter, to radioprotection standards and to criteria of safety. For the safety of breeder, the test made at CABRI pile, in the international research program has given confirmation of the validity of theoretical models used in accidents calculations, hypothetical accidents which has allowed to reactualize safety criteria which have to be used for the development of this type of reactor. In worker radioprotection the results obtained in laboratory on the effect of radon, the progress made in personal dosimetry and the action of radioprotection undertaken in uranium mines constitutes a coherent effort. The deep drilling in granit (1000 m) and the experimental associated program which has finished the indispensable scientific data for the future policy in matter of storage of radioactives wastes. IPSN has contributed to progress made in the rules of exploitation of reactors, in the definition of wastes containment -specially at the output of reprocessing plant- in handling machines in hazardeous areas and in the study of environment [fr

  13. Potentialities of robots in major accident situations

    International Nuclear Information System (INIS)

    Chevallier, M.

    2013-01-01

    The INTRA group was founded in 1988, 2 years after the Chernobyl accident with the purpose of a cooperation between EDF, Cogema and CEA in order to develop and operate a fleet of robots able to intervene and replace man in a nuclear facility in case of major accident. Now INTRA disposes of 5 types of equipment: first, robots for the inside of buildings (they can overcome 40 cm high obstacles, open doors, go upstairs) they are wire-guided and enjoy a battery life of 6 to 8 hours. Secondly, robots for the open air that are able to move in very degraded grounds, they are remote controlled through radio-waves and their autonomy range nears 5 km. Thirdly, public works vehicles, INTRA has developed an excavator and a dump truck, both are remote controlled, they allow the making of any earth work. Fourthly, INTRA has developed 2 systems of contamination measurement: Skylink and Helinuc. Skylink is a system of 20 radiation monitors that can be dispatched on the contaminated zone, their data is collected through radio waves. Helinuc is a kind of gamma spectrometer that is helicopter-borne and can draw a map of the contamination around the installation. Fifthly, 2 drones are being tested, they will be fitted with radiation monitors. (A.C.)

  14. 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

  15. MIMAS, setting the world-wide standard for plutonium recycling

    International Nuclear Information System (INIS)

    Vandergheynst Alain; Yvon Vanderborck

    2005-01-01

    Deployment of MIMAS MOX fuel irradiation started in 1985 with loading and irradiation in French 900 MWe PWR of EDF. A 20-year comprehensive R and D programme preceded it. This success was greatly facilitated by some early strategy advantages: 1) Development and licensing of a 'UO 2 -like' MOX fuel rod fully interchangeable with UO 2 rods; 2) Joint SCK/BN operation of the BR2 (MTR) and BR3 (PWR) reactors, pilot and industrial MOX fuel plants, PIE hot laboratories in the Mol/Dessel site. The period since 1985 saw the occurrence of some concurrent facts, that have incontestably led MIMAS to the world-wide leader position (99 % of actual MOX fuel is MIMAS): 1) BN-MIMAS has been selected by Cogema for its plants MELOX and Cadarache and has demonstrated to be a flexible, scalable, and industrial process. 2) MIMAS has been further selected by JNFL for its Japanese domestic MOX plant (Rokkasho-mura) and by US-DOE for its domestic MOX plant (Savannah-NC) for the disposition of 34-ton weapon-Pu. 3) Satisfactory fabrication and irradiation over 1840 metric tons of MIMAS MOX fuel. In order to face the worldwide on-going electricity market liberalisation, MIMAS makers and vendors must definitely improve the MOX performances to compete with continuously improving UO 2 fuel. The facing of this continuous challenge is also reviewed in the paper. (authors)

  16. Certification testing of the MOX Fresh Fuel Package (MFFP)

    International Nuclear Information System (INIS)

    Nichols, J.C. III; Yapuncich, F.L.

    2004-01-01

    Packaging Technology, Inc. (PacTec) is designing the MFFP as part of the Duke, COGEMA, Stone and Webster (DCS) consortium. DCS is tasked with providing the Department of Energy (DOE) with domestic MOX fuel fabrication and reactor irradiation services for the purpose of disposing of surplus weapons usable plutonium. This paper will discuss the development of the MFFP certification test program. The MFFP was subjected to a total of eleven free and puncture drops of the course of the certification testing. Because of the plutonium content, the design must be a Type BF, which among other things requires a containment boundary with a tested leakage rate of 1 x 10 -7 cm 3 /s air at 1 atm absolute and 25 C, or less. Both economics (desire for maximized payload) and operational (conveyance mode restricts size and weight) constraints lead to a highly optimized design. The optimized package design led to a significant test program which needed to address the containment boundary stability, puncture resistance of the package and lid end impact limiter, structural performance of the light weight lid structure, and stability of the internal structures. The test program efficiently balanced the test objectives while minimizing the number of costly hardware items used during this destructive testing. This balance achieved by strategic replacement of mock and prototypic payloads, impact limiters, and by careful test order considerations. The paper will conclude with a selected summary of the testing and an assessment of the test programs thoroughness

  17. Characterisation of aerosols produced by laser cutting; Caracterisation de l'aerosol emis lors d'une decoupe laser

    Energy Technology Data Exchange (ETDEWEB)

    Fauvel, S.; Pilot, G. [Institut de Radioprotection et de Surete Nucleaire (IRSN), DRU/SERAC, Lab. de Physique et Metrologie des Aerosols, 91 - Gif sur Yvette (France); Dinechin, G. de [Groupe d' Interet Public Groupement d' Etudes et de Recherche pour les Applications Industrielles des Lasers de Puissance, 94 - Arcueil (France)]|[CEA Saclay, Dir. de la Recherche Technologique (DRT/LITEN), 91 - Gif sur Yvette (France); Gosse, X. [Cogema, Dir. de l' Assainissement et des Projets, Maitrise d' Oeuvre Projets, 30 - Marcoule (France); Arnaud, P. [Ligne de Produit Demantelement, SGN, 30 - Bagnols sur Ceze (France)

    2007-07-01

    Powerful lasers represent a promising alternative solution to traditional cutting processes used in dismantling nuclear equipments. The use of optical fibers has an unquestionable advantage when dealing with airtight workshops. A stuunded by COGEMA Marcoule was undertaken by IRSN/SERAC in collaboration with GIP/GERAILP in order to characterise the aerosols emitted by the cutting of evaporators elements with a 4 kW continuous wave Nd:YAG laser. For this study, laser cutting has been carried out in a tight room of 35 m{sup 3} connected to a particle sampling pipe. Iso-kinetic samplers allowed the measurement of the aerosol concentration. A diffusional and inertial spectrometer (SDI 2001) - an Andersen impinger coupled to a diffusion battery - provided the size distribution. An electrostatic filter used upstream a HEPA filter, itself placed before the extractor fan, collected the majority of the emitted aerosol. Its efficiency was measured and controlled throughout the experiments. The results show the influence of the cutting conditions on the characteristics of the aerosol, and allow a comparison with other cutting tools. (authors)

  18. Characterisation of aerosols produced by laser cutting

    International Nuclear Information System (INIS)

    Fauvel, S.; Pilot, G.; Dinechin, G. de; Gosse, X.; Arnaud, P.

    2007-01-01

    Powerful lasers represent a promising alternative solution to traditional cutting processes used in dismantling nuclear equipments. The use of optical fibers has an unquestionable advantage when dealing with airtight workshops. A study funded by COGEMA Marcoule was undertaken by IRSN/SERAC in collaboration with GIP/GERAILP in order to characterise the aerosols emitted by the cutting of evaporators elements with a 4 kW continuous wave Nd:YAG laser. For this study, laser cutting has been carried out in a tight room of 35 m 3 connected to a particle sampling pipe. Iso-kinetic samplers allowed the measurement of the aerosol concentration. A diffusional and inertial spectrometer (SDI 2001) - an Andersen impinger coupled to a diffusion battery - provided the size distribution. An electrostatic filter used upstream a HEPA filter, itself placed before the extractor fan, collected the majority of the emitted aerosol. Its efficiency was measured and controlled throughout the experiments. The results show the influence of the cutting conditions on the characteristics of the aerosol, and allow a comparison with other cutting tools. (authors)

  19. Dismantling of the 904 Cell at the HAO/Sud Facility - 13466

    Energy Technology Data Exchange (ETDEWEB)

    Vaudey, C.E.; Crosnier, S. [AREVA Clean-Up BU, 1 route de la Noue 91196 - Gif-sur-Yvette (France); Renouf, M.; Gaspard, N. [AREVA Clean-Up BU, Site de La Hague - BV 35 - 50444 Beaumont Hague (France); Pinot, L. [AREVA D and D BU, Site de La Hague - 50444 Beaumont Hague (France)

    2013-07-01

    La Hague facility, in France, is the spent fuel recycling plant wherein a part of the fuel coming from some of the French, German, Belgian, Swiss, Dutch and Japanese nuclear reactors is reprocessed before being recycled in order to separate certain radioactive elements. The facility has been successively handled by the CEA (1962-1978), Cogema (1978-2006), and AREVA NC (since 2006). La Hague facility is composed of 3 production units: The UP2-400 production unit started to be operated in 1966 for the reprocessing of UNGG metal fuel. In 1976, following the dropout of the graphite-gas technology by EDF, an HAO workshop to reprocess the fuel from the light water reactors is affiliated and then stopped in 2003. - UP2-400 is partially stopped in 2002 and then definitely the 1 January 2004 and is being dismantled - UP2-800, with the same capacity than UP3, started to be operated in 1994 and is still in operation. And UP3 - UP3 was implemented in 1990 with an annual reprocessing capacity of 800 tons of fuel and is still in operation The combined licensed capacity of UP2-800 and UP3 is 1,700 tons of used fuel. (authors)

  20. Specific application of burnup credit for MOX PWR fuels in the rotary dissolver

    International Nuclear Information System (INIS)

    Caplin, Gregory; Coulaud, Alexandre; Klenov, Pavel; Toubon, Herve

    2003-01-01

    In prospect of a Mixed OXide spent fuels processing in the rotary dissolver in COGEMA/La Hague plant, it is interesting to quantify the criticality-safety margins from the burnup credit. Using the current production computer codes and considering a minimal fuel irradiation of 3 200 megawatt-day per ton, this paper shows the impact of burnup credit on industrial parameters such as the permissible concentration in the dissolution solution or the permissible oxide mass in the rotary dissolver. Moreover, the burnup credit is broken down into five sequences in order to quantify the contribution of fissile nuclides decrease and of minor actinides and fission products formation. The implementation of the burnup credit in the criticality-safety analysis of the rotary dissolver may lead to workable industrial conditions for the particular MOX fuel studied. It can eventually be noticed that minor actinides contribution is negligible and that considering only the six major fission products is sufficient, owing to the weak fuel irradiation contemplated. (author)

  1. EDF, a utility and its own needs in the field of transport of nuclear materials

    International Nuclear Information System (INIS)

    Gouin, P.; Mignot, E.; Hoang, L.P.

    1989-01-01

    As one of the most important producers of nuclear electricity in the world, EDF is concerned by all the aspects of the transport of nuclear materials and more particularly by those related to the nuclear fuel cycle. EDF is not itself a specialist in this field and most of the transports along the nuclear fuel cycle is done for their own account by their usual partners such as COGEMA or TRANSNUCLEAIRE. Since the beginning of the French nuclear program, they have generally used for these transports casks that already exist on the market and which were well suited to their needs. Nevertheless, new and specific needs appeared during the progress of their nuclear program and have lead them to: study and build new casks or packages, use existing casks for new purposes, develop a device for the measurement of fuel assemblies burn up, develop a software to optimize the evacuation of irradiated fuel for reprocessing. The purpose of this paper is to describe these realization but as a preliminary, they will present briefly the importance of the transport of nuclear materials for EDF

  2. 15 years return transport of vitrified high-level waste from France. The long way from La Hague to Gorleben

    International Nuclear Information System (INIS)

    Horn, Thomas

    2012-01-01

    The operators of German nuclear power plants have contracts since 1977 with the French company AREVA NC (former COGEMA) and since 1980 with the British company NDA (former BNFL) for reprocessing of spent nuclear fuel. Since July 2005 the delivery of irradiated fuel element into a reprocessing plant is prohibited. Until 2005 fuel elements with about 6.080 tSM were shipped abroad, about 5.309 tSM to France. The contribution deals with the history of the transports from La Hague to Gorleben, including the contamination problems in 1988 that caused restrictions by the German authorities. A catalogue of safety requirements had to be fulfilled for the allowance of further return transports. The development of appropriate transport casks to cope with changing heat generation of the high-level waste is described. During the complete transport cycle extensive radiological measurements were performed. By the end of 2011 the HAW (high-level waste) glass coquilles were completely returned to Gorleben.

  3. Mimas, a mature and flexible process to convert the stockpiles of separated civil and weapon grade plutonium into MOX fuel for use in LWR's

    International Nuclear Information System (INIS)

    Vandergheynst, A.; Vanderborck, Y.

    2001-01-01

    The BELGONUCLEAIRE Dessel MOX fabrication plant started operation in 1973. The first ten years have laid down the bases for all the modifications and improvements in the field of fuel fabrication and quality control process and technology, waste management, safety and safeguards. In 1984, BELGONUCLEAIRE developed the MIMAS fabrication process and has used it on industrial scale to make MOX fuel complying with the most stringent fuel vendor specifications. From 1986 to 2000, more than 25 t Pu have been processed into more than 450 tHM of MIMAS fuel delivered in five countries. 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. The BELGONUCLEAIRE MIMAS MOX fuel fabrication process was selected by COGEMA in the late 80(tm)s for its MELOX and its Cadarache plants. In 1999, the MIMAS process was chosen by the US DOE for the new MOX fabrication plant to be built in Savannah (SC-USA) to ''demilitarize'' 25,6 tons of weapon grade plutonium originating from nuclear war- heads. Recently MIMAS was selected by Japan for its domestic MOX plant to be built in Rokkasho-mura. (author)

  4. MOX manufacturing perspectives in a fast growing future and the MELOX plant

    International Nuclear Information System (INIS)

    Bekiarian, A.; Le Bastard, G.

    1991-01-01

    The potential MOX fuel market will grow regularly in the nineties. In view of satisfying the needs of the market, mixed-oxide fuel manufacturers have a strong incentive to increase the capacity of existing facilities and to build new ones. The Belgonucleaire plant at Dessel has been in operation since 1973. It has been backfitted up to a capacity of 35 t/y of LWR fuel which is now fully available. To satisfy the need of MOX fuel it was equally decided to adapt facilities in Cadarache where a production line, with a capacity of 15 t/y, is now delivering its production. But planned production up to the end of the century implies further increases in manufacturing capacities : MELOX, a plant for 120 t/y is under construction on the COGEMA site of Marcoule as well as a further expansion of Belgonucleaire plant at Dessel (P1) is studied to reach 70 t/y on this site. Similar developments are also planned by SIEMENS for a new manufacturing capability at Hanau (Germany). MELOX as well as all the new facilities have to get high levels of safety concerning environment and personnel. This leads to largely automated operations, and a particular care for waste treatment. (author)

  5. Spent fuel transport in fuel cycle

    International Nuclear Information System (INIS)

    Labrousse, M.

    1977-01-01

    The transport of radioactive substances is a minor part of the fuel cycle because the quantities of matter involved are very small. However the length and complexity of the cycle, the weight of the packing, the respective distances between stations, enrichment plants and reprocessing plants are such that the problem is not negligible. In addition these transports have considerable psychological importance. The most interesting is spent fuel transport which requires exceptionally efficient packaging, especially where thermal and mechanical resistance are concerned. To meet the safety criteria necessary for the protection of both public and users it was decided to use the maximum capacity consistent with rail transport and to avoid coolant fluids under pressure. Since no single type of packing is suitable for all existing stations an effort has been made to standardise handling accessories, and future trands are towards maximum automation. A discussion on the various technical solutions available for the construction of these packing systems is followed by a description of those used for the two types of packaging ordered by COGEMA [fr

  6. New developments in transportation for research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Mondanel, J.L. [Transnucleaire, F-75008 Paris (France)

    1998-07-01

    For more than 30 years, Transnucleaire has been performing safely a large number of national and international transports of radioactive material. Transnucleaire has also designed and supplied numerous packagings for all types of nuclear fuel cycle radioactive materials: for front-end and back-end products and for power and research reactors. Since the last meeting held in Bruges, Transnucleaire has been continuously involved in transportation activities for fresh and irradiated materials for research reactors. We are pleased to take the opportunity in this meeting to share with reactor operators, official bodies and other partners, the on-going developments in transportation and associated services. Special attention will be paid to the starting of transports of MTR spent fuel elements to the La Hague reprocessing plant where COGEMA offers reprocessing services on a long-term basis to reactors operators. Detailed information is provided on regulatory issues, which may affect transport activities: evolution of the regulations, real experiences of recent transportation and development of new packaging designs. Options and solutions will be proposed by Transnucleaire to improve the situation for continuation of national and international transports at an acceptable price whilst maintaining an ultimate level of safety (author)

  7. Review of annual radioecological studies carried out since 1991 in the French nuclear power plants environment

    International Nuclear Information System (INIS)

    Duffa, C.; Gontier, G.; Renaud, P.

    2004-01-01

    Since 1991, the IRSN carries out annual radioecological studies in the environment of the French Nuclear Power Plants. More than 5,000 samples, collected in terrestrial and aquatic ecosystems around the 20 studied plants, have been analysed by low-level gamma spectrometry. This paper presents the main goals and methods for such studies, and the lessons learnt from 11 years results. The French NPP routine atmospheric releases do not lead to detectable radioactive inputs into their surroundings. For this reason, IRSN decided to reduce the number of analysis concerning terrestrial samples since 2000. On the other hand, NPP liquid discharges into rivers are responsible for the presence of low 60 Co, 58 Co, 110m Ag and 54 Mn activities and significant difference in 137 Cs/ 134 Cs activity ratios measured in aquatic compartments. Radioactive discharges of artificial gamma emitters are also detectable in the Channel marine environment around NPP. Nevertheless, this influence is often concealed by radionuclides released by COGEMA-La Hague nuclear reprocessing plant. Beyond important evaluations concerning the presence of artificial radionuclides in NPP's environment, studies conducted since 1991 give us an important database that can be used for a better knowledge of transfers and distribution of radioactivity through the environment. (author)

  8. Evaluation of E/EV/SE aptitude to very long duration. Final report of working groups

    International Nuclear Information System (INIS)

    Leroy, C.; Bouniol, P.; Arrighi; Cellier; Gallois; Grandjean, J.P.; Mazaudier, F.; Siboulet, B.; Bouniol, P.

    2000-01-01

    A joint COGEMA/CEA action aims at evaluating the conditions allowing the extension beyond 50 years of the exploitation of the E/EV/SE vitrified wastes storage facility of the UP3 factory of La Hague (France). The approach considered consists in analysing the technical and administrative aspects of the facility in order to determine the changes to be implemented for its qualification as very long storage facility. Three target characteristics have been identified as priorities for this analysis: safety, civil engineering, and cooling ventilation of wells, and thus three working groups have been created. According to works carried out, facilities like the E/EV/SE one are designed in such a way that their durability can reach the century scale: the robustness of the cooling process, the passiveness of most equipments and the limitation of components functions are the main strong points. Service life limitations come mainly from the thermal evolution of waste packages and the aging of components under the climate conditions: risk of atmospheric corrosion of the bottom part of wells under the effect of water condensation, and risk of corrosion of concrete reinforcements. Suggestions of improvement of the quantification and understanding of phenomena influencing the lifetime limitation are made, and some possible technical solutions are proposed. (J.S.)

  9. Industrial tests of rhodium self-powered detectors: the Golfech 2 experimentation

    International Nuclear Information System (INIS)

    Mourlevat, J.L.; Janvier, D.; Warren, H.D.

    2000-01-01

    In co-operation with Electricite de France (EDF), FRAMATOME has been testing two in-core strings which are equipped with rhodium self-powered detectors (SPDs) in the Golfech Unit 2 reactor (1300 MW, 4L plant) since August 1997. The rhodium SPDs and the strings which support them were designed and built by the US FRAMATOME subsidiary FRAMATOME-COGEMA-FUEL (FCF). The rhodium signals and some other plant parameters are acquired through the use of a specific device designed by the CEA (Commissariat a l'Energie Atomique) and are processed off-line by FRAMATOME. This demonstration test is planned to last until mid-2000. The following presentation is focused on the results obtained during the first demonstration cycle (from 08/97 to 12/98). The tests that have been conducted consist of checking the rhodium depletion and of comparing the rhodium signals to the movable probes. In order to compensate for the delay in the rhodium signals, a deconvolution algorithm has also been tested. Up to now, the results are very satisfactory and a future large scale industrial application is being discussed with the EDF. The main objective of the next experimentation phase is to test - under industrial conditions - a prototype of an on-line monitoring unit known as the Partial In-Core Monitoring System (PIMS). This system will include 16 rhodium in-core strings and will use an on-line 3-D core model. (authors)

  10. Contribution to the modeling of elaborate cement barriers behaviour with respect to radioelements migration by the study of ancient analogue materials

    International Nuclear Information System (INIS)

    Rougeau, P.

    1994-01-01

    The durability of cement matrices and their capacity of radioelements retention are determining factors for their use as elaborate barriers in radioactive waste disposal facilities. This study focusses on the observation of concretes in real situation of alteration or in contact with radioelements for predictive modelling. Two materials have been selected. One is a concrete from a gallery wall of the Margnac uranium mine (Cogema, France) submitted to uranium-rich infiltration waters. The alteration concentrates in two characteristic successive zones: the first is composed of calcium depleted and aluminum enriched calcite and calcium hydro-silicates and the second, between the first zone and the sound matrix, is characterized by a self-filling in process due to massive ettringite precipitation induced by sulfate ions transport. Uranium migration depends closely on the fissures and porosity of the cement matrix. The second series of samples correspond to 2000 years old archaeological cements from Pompei (Italy) made of volcanic ashes and carrying uranium traces. These samples were submitted to burying and alteration is characterized by a carbonation of the cement matrix. The mineralogy is closed to the one defined in the first alteration zone of the uranium mine concrete. Both studies demonstrate that the presence of carbonate ions in the percolation water plays a major role in the alteration process. Sulfate reactions must be considered too and tend to diminish the materials porosity and to increase the delay in radionuclides migration processes. (J.S.). 131 refs., 92 figs., 55 tabs., 51 photos., 15 appends

  11. Plutonium and minor actinides recycling in PWRs with new APA concepts

    International Nuclear Information System (INIS)

    Golfier, H.; Rohart, M.; Aniel, S.; Bergeron, J.; Deffain, J.P.

    2001-01-01

    In the frame of the studies required by the French law of 1991, CEA have launched a wide range of assessments on waste management for different reactors (PWR, FBR). Considerable R and D work has already been performed in order to improve the use of Plutonium (Pu) in PWRs. In this context, the Advanced Plutonium Assembly (APA) aims to improve the use of Plutonium (Pu) in PWRs while minimizing Minor Actinides (MA) production, with only slight modifications of the core design. From a neutronic point of view, the overall studied cases lead to the stabilization of the Pu inventory with approximately 30% of the park refueled with APA assemblies in full APA cores. Multi-recycling could satisfy the stabilization of Pu+ (Am+Cm) inventory by the implementation of approximately 40% APA reactors in a conventional PWRs park. After 7 or 8 recycles, the equilibrium is reached. The Pu inventory in the fuel cycle ranges from 210 tons to 270 tons for Pu multi-recycling, and from 240 tons to 290 tons for Pu+(Am+Cm) multi-recycling. The saving in Natural Uranium and Separative Work Units (SWU) due to the use of APA reactors would be between 30% and 15% in comparison with the UO 2 open cycle. This paper presents a selection of the main preliminary Pu recycling results of the joint study program COGEMA-CEA. (author)

  12. Calculation code evaluating the confinement of a nuclear facility in case of fires

    Energy Technology Data Exchange (ETDEWEB)

    Laborde, J.C.; Prevost, C.; Vendel, J. [and others

    1995-02-01

    Accident events involving fire are quite frequent and could have a severe effect on the safety of nuclear facilities. As confinement must be maintained, the ventilation and filtration systems have to be designed to limit radioactive release to the environment. To determine and analyse the consequences of a fire on the contamination confinement, IPSN, COGEMA and SGN are participating in development of a calculation code based on introduction, in the SIMEVENT ventilation code, of various models associated to fire risk and mass transfer in the ventilation networks. This calculation code results from the coupling of the SIMEVENT code with several models describing the temperature in a room resulting of a fire, the temperatures along the ventilation ducts, the contamination transfers through out the ventilation equipments (ducts, dampers, valves, air cleaning systems) and the High Efficiency Particulate Air (HEPA) filters clogging. The paper proposed presents the current level of progress in development of this calculation code. It describes, in particular, the empirical model used for the clogging of HEPA filters by the aerosols derived from the combustion of standard materials used in the nuclear industry. It describes, also, the specific models used to take into account the mass transfers and resulting from the basic mechanisms of aerosols physics. In addition, an assessment of this code is given using the example of a simple laboratory installation.

  13. The French centralized low level radwaste treatment centre named CENTRACO

    International Nuclear Information System (INIS)

    Barnes, C.; Sixou, Y.

    1996-01-01

    Socodei, a subsidiary company of EdF and Cogema is commissioned to design, finance, build and operate two low level radwaste treatment facilities: a contaminated scrap metal melting unit, and a solid and liquid waste incinerator. These units frame a low level radwaste treatment centre named Centraco, located near Marcoule in the south of France, and will receive in 1998 waste coming from dismantling, maintenance and operating works of French and foreign nuclear sites. The decision to create this centre is due to the low density and large variety of low level radwaste which take a volume out of proportion with their activity, specially in the surface storage centre. Up to now, all low level radwaste were sent and stored with no treatment optimization in surface storage centres. Socodei proposes in one single site, to optimize low level radwaste management and reduce the volume of ultimate waste to be stored: in a ratio of one to ten by casting ingots coming from melting contaminated scrap metals; in a ratio of one to twenty by encapsulating earth ashes and ashes resulting from incineration of solid and liquid waste. This is a centralized treatment centre and that's why Centraco is a new waste management system. Getting together all means in one place reduces costs, avoids mismanagement and risk increase, and allows consistency in safety, environmental impact, transport and personnel radioprotection. (author)

  14. 15 years return transport of vitrified high-level waste from France. The long way from La Hague to Gorleben; 15 Jahre Rueckfuehrung von verglasten hochaktiven Abfaellen aus Frankreich. Der lange Weg von La Hague nach Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Horn, Thomas [GNS Gesellschaft fuer Nuklear Service mbH, Essen (Germany)

    2012-11-01

    The operators of German nuclear power plants have contracts since 1977 with the French company AREVA NC (former COGEMA) and since 1980 with the British company NDA (former BNFL) for reprocessing of spent nuclear fuel. Since July 2005 the delivery of irradiated fuel element into a reprocessing plant is prohibited. Until 2005 fuel elements with about 6.080 tSM were shipped abroad, about 5.309 tSM to France. The contribution deals with the history of the transports from La Hague to Gorleben, including the contamination problems in 1988 that caused restrictions by the German authorities. A catalogue of safety requirements had to be fulfilled for the allowance of further return transports. The development of appropriate transport casks to cope with changing heat generation of the high-level waste is described. During the complete transport cycle extensive radiological measurements were performed. By the end of 2011 the HAW (high-level waste) glass coquilles were completely returned to Gorleben.

  15. 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

  16. Transport experience of new ''TNF-XI'' powder package

    International Nuclear Information System (INIS)

    Nomura, I.; Fujiwara, T.; Naigeon, P.

    2004-01-01

    Since the Tokai criticality accident in 1999, there has been no specialized manufacturer conducting uranium re-conversion in Japan. For this reason, Nuclear Fuel Industries, Ltd. (NFI) imports from overseas almost all the uranium oxide powder used for manufacturing pellets for nuclear fuel assemblies. To date, an NT-IX package has been used for transporting the uranium oxide powder. However, due to the adoption of IAEA TS-R-1 into Japanese domestic regulations, we have begun to use a new TNF-XI powder package because the NT-IX package can suffer major deformation under the drop test III condition. The TNF-XI package was jointly developed by COGEMA LOGISTICS of France and NFI from 2000, and started to be used for actual transportation in 2003. This package has improved transport efficiency, handling operability and safety performance in comparison to its predecessor. This paper describes the characteristics of the new TNF-XI package and its actual transportation records and performance

  17. The LWRs Fuel Cycle/What Could Change in the 90's

    International Nuclear Information System (INIS)

    Lamorlette, G.

    1990-01-01

    One of the main characteristics of the nuclear power industry is the size of its investments and the time it takes to build its facilities. They must operate long enough to yield a return on the sums invested while producing electricity at a competitive price. A recent study by OECD/N/A and the International Energy Agency shows that in most countries committed to long-term nuclear programmes, the nuclear kWh has a significant economic edge over the oil-generated kWh. Most of these countries are poor in natural resources, and this inspired their commitment. After one or two decades, nuclear power is proving to be a good choice. The nuclear fuel cycle industry has the same characteristics. From the discovery of a Uranium deposit to the opening of mine takes ten years, another the years to build a reprocessing plant. But a closer analysis of products and services are well known, the way in which producers will be able to meet them, and the utilities' procurement strategy, are today still hard to predict. We shall here attempt to identify, in the light of the experience of the 1980s, a few events that might lead to major changes in trade in products and services in three fields with which Cogema is quite familiar : Uranium, enrichment and the spent fuels management

  18. 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

  19. Hair dosimetry following neutron irradiation.

    Science.gov (United States)

    Lebaron-Jacobs, L; Gaillard-Lecanu, E; Briot, F; Distinguin, S; Boisson, P; Exmelin, L; Racine, Y; Berard, P; Flüry-Herard, A; Miele, A; Fottorino, R

    2007-05-01

    Use of hair as a biological dosimeter of neutron exposure was proposed a few years ago. To date, the (32)S(n,p)(32)P reaction in hair with a threshold of 2.5 MeV is the best choice to determine the fast neutron dose using body activation. This information is essential with regards to the heterogeneity of the neutron transfer to the organism. This is a very important parameter for individual dose reconstruction from the surface to the deeper tissues. This evaluation is essential to the adapted management of irradiated victims by specialized medical staff. Comparison exercises between clinical biochemistry laboratories from French sites (the CEA and COGEMA) and from the IRSN were carried out to validate the measurement of (32)P activity in hair and to improve the techniques used to perform this examination. Hair was placed on a phantom and was irradiated at different doses in the SILENE reactor (Valduc, France). Different parameters were tested: variation of hair type, minimum weight of hair sample, hair wash before measurement, delivery period of results, and different irradiation configurations. The results obtained in these comparison exercises by the different laboratories showed an excellent correlation. This allowed the assessment of a dose-activity relationship and confirmed the feasibility and the interest of (32)P measurement in hair following fast neutron irradiation.

  20. Nuclear power, society and environment

    International Nuclear Information System (INIS)

    Fouchet, N.

    1997-01-01

    This rubric reports on 12 short notes about scientific facts, and sociological, political and environmental aspects of nuclear power in France and other countries: a new micro-beam line for the nuclear micro-probe of Pierre Sue laboratory; the French government gives permission for the filling up of the Carnet swampy site for the possible sitting of a future nuclear power plant in the Loire river estuary; incident simulation exercise at Chooz B1 in January 1997: radioactive leak and population under shelter; about Superphenix, 'Le Monde' newspaper disseminates false information; the anti-Superphenix lobby; Georges Charpak's opinion about anti-nuclear propaganda; gamma radiation in the help of cultural heritage; a new ionizing particle detector developed by the CEA; dismantling of the FR-2 experimental reactor (Karlsruhe, Germany) and the safe confinement of the reactor vessel; the Russian specialists' proposal for the transformation of Tchernobyl's sarcophagus into a monolith of concrete; Cogema's support to scientific research devoted to environment and public health; three new member countries in the World Council of Nuclear Workers (WONUC). (J.S.)

  1. Travel to France as Chief US Delegate at a meeting of International Standards Organization ISO/TC-85, ``Nuclear Technology``. Foreign trip report, March 17--March 26, 1994

    Energy Technology Data Exchange (ETDEWEB)

    Westfall, R.M.

    1994-04-11

    As overall US Advisor for ISO/TC-85, SC-5, Dr. Westfall met with (1) Work Group 1, ``Measurement Techniques for the Chemical and Physical Characterization of UF{sub 6}, UO{sub 2}, and Mixed Oxide,`` on Monday, March 21, (2) Work Group 5, ``Standardization of Measurement Methods for the Characterization of Solid and Solidified Waste Forms, and for the Corrosion of their Primary Containers,`` on Tuesday, March 22; and (3) the full Subcommittee-5 on Wednesday, March 23. The status of work by all seven work groups in SC-5 was reported. Those having to do with nuclear fuel transportation (WG-4: UF, Containers, WG-9: Cask Trunnions, and WG-10: Cask Confinement) either have approved standards or drafts at an advanced stage of development. These work group convenors were asked to maintain their membership and establish new work areas in the field of nuclear fuel packaging. Definition of scope for new work is to be done in coordination with the interested staff members of the International Atomic Energy Agency, Vienna, Austria. On Thursday, March 24, the Cogema-Marcoule Plant staff hosted the SC-5 members to technical tours of their nuclear fuel reprocessing and waste vitrification and storage facilities.

  2. ''Cold crucible'' vitrification projects for low and high active waste

    International Nuclear Information System (INIS)

    Roux, P.; Jouan, A.

    1998-01-01

    In continuity of the CEA HLW vitrification process experienced for more than 20 years in industrial operations in Cogema reprocessing plants (Marcoule and La Hague), CEA has developed an advanced extended performance cold crucible glass melter to address a wider range of waste like LLW, ILW and in particular waste with very corrosive species or requiring glass with higher elaboration temperature. In the cold crucible melter the bath of molten glass is directly heated by induction while the walls are cooled in order to freeze a protective glass layer. This technology subsequently allows high glass throughput while keeping the flexibility, the maintainability and low secondary waste generation related to a small metallic melter. Its recent use in the glass industry and the thousands of hours of pilot tests performed on inactive surrogates have demonstrated the maturity of this technology and its flexibility of use for processing most of the waste generated at nuclear facilities. SGN has therefore proposed this technology in Italy and Korea and in USA in the frame of the Hanford Privatization phase 1 A feasibility study. Main features of this study but also tests results with Hanford surrogates and active samples are discussed. (author)

  3. Rokkasho low-level radioactive waste disposal in Japan

    International Nuclear Information System (INIS)

    Takahashi, Y.

    1994-01-01

    Japan Nuclear Fuel Limited commenced the operation of the shallow land disposal of low-level radioactive waste from reactor operation, in 1992 at Rokkasho site in Aomori Prefecture. JNFL is private company whose main activities within the responsibility of JNFL are: 1) Disposal of low-level radioactive waste, 2) Uranium enrichment, 3) Reprocessing of spent nuclear fuels, 4) Temporary storage of returned wastes from COGEMA and BNFL by reprocessing contracts, prior to disposal. JNFL selected the site for the disposal of LLW at Rokkasho in Aomori Prefecture, then bought land of 3.4 million m 2 . Among waste spectrum, LLWs from nuclear power plants, from uranium enrichment and from reprocessing are to be managed by JNFL, including dismantling of these facilities, and JNFL has plan to dispose about 600 thousand m 3 of wastes ultimately. On the middle of November 1990 JNFL got the permission of the application for 40 thousand m 3 (equivalent to 200,000 drums each with a 200-liter capacity) of reactor operating wastes which is solidified with cement, bitumen or plastics as a first stage. And after the construction work for about 2 years, the operations started at Dec. 8th, 1992. The Disposal center has already accepted about 24,000 LLW drums as of the end of February, 1994. (author)

  4. Production and validation of nuclear data for reactor and fuel cycle applications; Production et validation des donnees nucleaires pour les applications reacteurs et cycle du combustible

    Energy Technology Data Exchange (ETDEWEB)

    Trakas, C [Framatome ANP GmbH NBTT, Erlangen (Germany); Verwaerde, D [Electricite de France EDF, 75 - Paris (France); Toubon, H [Cogema, 78 - Velizy Villacoublay (France); and others

    2002-07-01

    The aim of this technical meeting is the improvement of the existing nuclear data and the production of new data of interest for the upstream and downstream of the fuel cycle (enrichment, fabrication, management, storage, transport, reprocessing), for the industrial reactors, the research reactors and the new reactor concepts (criticality, dimensioning, exploitation), for the instrumentation systems (external and internal sensors), the radioprotection, the residual power, the structures (neutron bombardment effect on vessels, rods etc..), and for the activation of steel structures (Fr, Ni, Co). The expected result is the collection of more reliable and accurate data in a wider spectrum of energies and temperatures thanks to more precise computer codes and measurement techniques. This document brings together the communications presented at this meeting and dealing with: the process of production and validation of nuclear data; the measurement facilities and the big international programs; the users needs and the industrial priorities; the basic nuclear data (BND) needs at Cogema; the expression and evaluation of BND; the evaluation work: the efficient cross-sections; the processing of data and the creation of activation libraries; from the integral measurement to the qualification and the feedback on nuclear data. (J.S.)

  5. Development and experimental qualification of the new safety-criticality CRISTAL package; Developpement et qualification experimentale du nouveau formulaire de surete-criticite Cristal

    Energy Technology Data Exchange (ETDEWEB)

    Mattera, Ch

    1998-11-01

    This thesis is concerned with Criticality-Safety studies related to the French Nuclear Fuel Cycle. We first describe the steps in the nuclear fuel cycle and the specific characteristics of these studies compared with those performed in Reactor Physics. In order to respond to the future requirements of the French Nuclear Program, we have developed a new package CRISTAL based on a recent cross sections library (CEA 93) and the newest accurate codes (APOLLO 2, MORET 4, TRIPOLI 4). The CRISTAL system includes two calculations routes: a design route which will be used by French Industry (COGEMA/SGN) and a reference route. To transfer this package to the French industry, we have elaborated calculation schemes for fissile solutions, dissolver media, transport casks and storage pools. Afterwards, these schemes have been used for the CRISTAL experimental validation. We have also contributed to the CRISTAL experimental database by reevaluating a French storage pool experiment: the CRISTO II experiment. This revaluation has been submitted to the OECD working group in order that this experiment can be used by international criticality safety engineers to validate calculations methods. This work represents a large contribution to the recommendation of accurate calculation schemes and to the experimental validation of the CRISTAL package. These studies came up to the French Industry expectations. (author)

  6. Production and validation of nuclear data for reactor and fuel cycle applications

    International Nuclear Information System (INIS)

    Trakas, C.; Verwaerde, D.; Toubon, H.

    2002-01-01

    The aim of this technical meeting is the improvement of the existing nuclear data and the production of new data of interest for the upstream and downstream of the fuel cycle (enrichment, fabrication, management, storage, transport, reprocessing), for the industrial reactors, the research reactors and the new reactor concepts (criticality, dimensioning, exploitation), for the instrumentation systems (external and internal sensors), the radioprotection, the residual power, the structures (neutron bombardment effect on vessels, rods etc..), and for the activation of steel structures (Fr, Ni, Co). The expected result is the collection of more reliable and accurate data in a wider spectrum of energies and temperatures thanks to more precise computer codes and measurement techniques. This document brings together the communications presented at this meeting and dealing with: the process of production and validation of nuclear data; the measurement facilities and the big international programs; the users needs and the industrial priorities; the basic nuclear data (BND) needs at Cogema; the expression and evaluation of BND; the evaluation work: the efficient cross-sections; the processing of data and the creation of activation libraries; from the integral measurement to the qualification and the feedback on nuclear data. (J.S.)

  7. Development and experimental qualification of the new safety-criticality CRISTAL package

    International Nuclear Information System (INIS)

    Mattera, Ch.

    1998-11-01

    This thesis is concerned with Criticality-Safety studies related to the French Nuclear Fuel Cycle. We first describe the steps in the nuclear fuel cycle and the specific characteristics of these studies compared with those performed in Reactor Physics. In order to respond to the future requirements of the French Nuclear Program, we have developed a new package CRISTAL based on a recent cross sections library (CEA 93) and the newest accurate codes (APOLLO 2, MORET 4, TRIPOLI 4). The CRISTAL system includes two calculations routes: a design route which will be used by French Industry (COGEMA/SGN) and a reference route. To transfer this package to the French industry, we have elaborated calculation schemes for fissile solutions, dissolver media, transport casks and storage pools. Afterwards, these schemes have been used for the CRISTAL experimental validation. We have also contributed to the CRISTAL experimental database by reevaluating a French storage pool experiment: the CRISTO II experiment. This revaluation has been submitted to the OECD working group in order that this experiment can be used by international criticality safety engineers to validate calculations methods. This work represents a large contribution to the recommendation of accurate calculation schemes and to the experimental validation of the CRISTAL package. These studies came up to the French Industry expectations. (author)

  8. Development and experimental testing of the new safety-criticality Cristal package; Developpement et qualification experimentale du nouveau formulaire de surete-criticite Cristal

    Energy Technology Data Exchange (ETDEWEB)

    Mattera, Ch

    1998-11-10

    This thesis is concerned with Criticality-Safety studies related to the French Nuclear Fuel Cycle. We first describe the steps in the nuclear fuel cycle and the specific characteristics of these studies compared with those performed in Reactor Physics. In order to respond to the future requirements of the French Nuclear Program, we have developed a new package CRISTAL based on a recent cross sections library (CEA93) and the newest accurate codes (APOLLO2, MORET4, TRIPOLI4). The cristal system includes two calculations routes: a design route which will be used by French Industry (COGEMA/SGN) and a reference route.) To transfer this package to the French industry, we have elaborated calculation schemes for fissile solutions, dissolver media, transport casks and storage pools. Afterwards, these schemes have been used for the CRISTAL experimental validation. We have also contributed to the CRISTAL experimental database by reevaluating a French storage pool experiment: the CRISTO II experiment. This revaluation has been submitted to the OCDE working group in order that this experiment can be used by international criticality safety engineers to validate calculations methods. This work represents a large contribution to the recommendation of accurate calculation schemes and to the experimental validation of the CRISTAL package. These studies came up to the French Industry expectations. (author) 70 refs.

  9. Development and experimental testing of the new safety-criticality Cristal package

    International Nuclear Information System (INIS)

    Mattera, Ch.

    1998-01-01

    This thesis is concerned with Criticality-Safety studies related to the French Nuclear Fuel Cycle. We first describe the steps in the nuclear fuel cycle and the specific characteristics of these studies compared with those performed in Reactor Physics. In order to respond to the future requirements of the French Nuclear Program, we have developed a new package CRISTAL based on a recent cross sections library (CEA93) and the newest accurate codes (APOLLO2, MORET4, TRIPOLI4). The cristal system includes two calculations routes: a design route which will be used by French Industry (COGEMA/SGN) and a reference route.) To transfer this package to the French industry, we have elaborated calculation schemes for fissile solutions, dissolver media, transport casks and storage pools. Afterwards, these schemes have been used for the CRISTAL experimental validation. We have also contributed to the CRISTAL experimental database by reevaluating a French storage pool experiment: the CRISTO II experiment. This revaluation has been submitted to the OCDE working group in order that this experiment can be used by international criticality safety engineers to validate calculations methods. This work represents a large contribution to the recommendation of accurate calculation schemes and to the experimental validation of the CRISTAL package. These studies came up to the French Industry expectations. (author)

  10. The nymphea concept: a new way for using ion exchange in the decontamination of radioactive liquid wastes with low salt content

    International Nuclear Information System (INIS)

    Pierlas, R.; Nicoud, R.; Schweich, D.; Kalimbadjian, M.; Dozol, J.F.

    1986-09-01

    SGN has undertaken the development of a new equipment ''NYMPHEA'', specially fitted for the purification of the pool water in spent fuel storage facilities. Based on ion-exchange process, these immersed units are working with high flow rate and a small thickness of the resins bed. Cogema has selected these ionic ''NYMPHEA'' for installation in the new storage basins already built or in construction in the new french reprocessing plant UP3 in La Hague (France). Together with the necessary and complementary hot tests in CEA laboratories (CADARACHE), a basic research has been started in cooperation with the Chemical Engineering Science Laboratory (LSGC Nancy) and the results already achieved are presented in this paper. Since two years, the ''NYMPHEA'' are into operation at La Hague (pool C), fulfilling all the required performances. This new and promising concept could, in the future, be extended to other applications, for the treatment of low salt content solutions, in the nuclear waste processing field, as well as for various chemical separations

  11. Mechanism of the rapid dissolution of Pu02 under oxidizing conditions and applications

    International Nuclear Information System (INIS)

    Madic, C.; Lecomte, M.; Bourges, J.; Koehly, G.

    1991-01-01

    Until the recent years, plutonium dioxide was known to be among the metallic oxides the most difficult to dissolve. From thermodynamic calculations it can be predicted that PuO 2 will dissolve under oxidizing conditions. This can be achieved using Ag(II) species possibly regenerated by electrochemical means. The mechanism of such a process has been elucidated using carbon paste electrochemistry and 18 O labelling. These studies demonstrate that the chemical reaction limiting the overall proces is located on the surface of the solid PuO 2 , and that the first step consists in the oxidation of the plutonium into Pu(V) species. Applications of the dissolution process of PuO 2 by electrogenerated Ag(II) were growing in the recent years in FRANCE. These applications developed often in collaboration with SGN and COGEMA, concern the treatment of: out of specifications PuO 2 , incineration ashes, wastes produced during MOX fuel fabrication, and during the dismantling of old nuclear facilities. A general overview of these different applications is given

  12. Design of an experiment to measure the decay heat of an irradiated PWR fuel: MERCI experiment; Conception d'une experience de mesure de la puissance residuelle d'un combustible irradie: l'experience MERCI

    Energy Technology Data Exchange (ETDEWEB)

    Bourganel, St

    2002-11-01

    After a reactor shutdown, a significant quantity of energy known as 'decay heat' continues to be generated from the irradiated fuel. This heat source is due to the disintegration energy of fission products and actinides. Decay heat determination of an irradiated fuel is of the utmost importance for safety analysis as the design cooling systems, spent fuel transport, or handling. Furthermore, the uncertainty on decay heat has a straight economic impact. The unloading fuel spent time is an example. The purpose of MERCI experiment (irradiated fuel decay heat measurement) consists in qualifying computer codes, particularly the DARWIN code system developed by the CEA in relation to industrial organizations, as EDF, FRAMATOME and COGEMA. To achieve this goal, a UOX fuel is irradiated in the vicinity of the OSIRIS research reactor, and then the decay heat is measured by using a calorimeter. The objective is to reduce the decay heat uncertainties from 8% to 3 or 4% at short cooling times. A full simulation on computer of the MERCI experiment has been achieved: fuel irradiation analysis is performed using transport code TRIPOLI4 and evolution code DARWIN/PEPIN2, and heat transfer with CASTEM2000 code. The results obtained are used for the design of this experiment. Moreover, we propose a calibration procedure decreasing the influence of uncertainty measurements and an interpretation method of the experimental results and evaluation of associated uncertainties. (author)

  13. Improvements in techniques and processes

    International Nuclear Information System (INIS)

    Cairon, B.; Nolin, D.

    2003-01-01

    The paper presents the De-construction And Decontamination Techniques used at COGEMA-La Hague for dismantling and decontamination of plant UP2 400. Intervention under water particularly intervention from the edge of the pool are described while significant radiological constraints due to the presence of fuel are observed. The Under water fuel operations were undertaking to recover pieces of UNGG fuel and miscellaneous technological waste under 5 m of water and with reduced visibility. Here remote works implying reduced dosimetry and increased security were carried out. Specific issues concerning tools and procedures are addressed as fallows: Pendulous telescopic tool holder on runway channel 215.40; HP cutting under water; Cutting machine set up in the facility; Suction of sludge; Gripping and handling system for the slider and lid; Dredging the Sludge; tests in facility; Control console; Shock absorbing units; Moving the shock absorbing mattresses using slings; Decontamination of large areas of stainless steel walls; Cutting bulky parts in air; Cutting a tubular structure under water; Compacting the drums; Concrete skinning using skinning machines; Concrete skinning using the BRH, hydraulic rock breaker; Concrete skinning using shot blasting; Dismantling the process cell using the 'ATENA' remote power carrier; Removing openings through dry core sample drilling; Removing openings through demolition

  14. On confirmation of abandonment of imported waste (glass solidified bodies) outside business places

    International Nuclear Information System (INIS)

    1996-01-01

    Electric power companies entrust the reprocessing of spent fuel generated from nuclear power stations to COGEMA in France, and in April, 1995, 28 high level radioactive wastes (glass solidified bodies) generated by the reprocessing were returned. When these glass solidified wastes are abandoned in the waste management facility of Japan Nuclear Fuel Service Co., it was decided to receive the confirmation of the prime minister on the measures based on the relevant law. Four electric power companies submitted the application and the explanation paper. As to the contents of the glass solidified wastes, the technical inspection was carried out by Bureau Veritas. Considering that this import of glass solidified wastes is the first in Japan, Science and Technology Agency carried out the measurement of all 28 wastes. The results are reported. It was confirmed that the measures for the abandonment taken by four electric power companies conform to the stipulation. The contents of the confirmation are reported in the order of the stipulation. These wastes were solidified with borosilicate glass in 5 mm thick stainless steel vessels, and the welding was done properly. (K.I.)

  15. UP1 decommissioning project: initial review of lessons learned

    International Nuclear Information System (INIS)

    Fontana, Ph.; Fraize, G.; Seurat, Ph.

    2008-01-01

    The very first French electricity-generating nuclear reactors (3 gas-graphite reactors operated between 1956 and 1984) and spent fuel reprocessing plant (UP1 and ancillary facilities operated from 1958 to 1997) were located at Marcoule, in southern France. These historic facilities, together with the research labs that contributed to the development and commissioning of the processes implemented, are being decontaminated and dismantled. Other facilities near these nuclear plants will also be shut down in the next few years: the Phenix fast breeder reactor, the Celestin reactors and other ancillary units. Because the UP1 reprocessing plant and its related facilities were used for both commercial and defense activities, a dedicated group comprising three state-owned or private companies (CEA, EdF and COGEMA) was set up as the contracting authority from 1996 to 2004. Today the CEA is the contracting authority at Marcoule and has replaced AREVA NC as the site nuclear operator. AREVA acts as prime contractor for both operation of the main facilities and engineering of the dismantling projects. (authors)

  16. UP1 decommissioning project: initial review of lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Fontana, Ph.; Fraize, G. [CEA Valrho, Dir. de l' Energie Nucleaire (DEN/DPAD), 30 - Marcoule (France); Seurat, Ph. [AREVA NC, 75 - Paris (France)

    2008-07-01

    The very first French electricity-generating nuclear reactors (3 gas-graphite reactors operated between 1956 and 1984) and spent fuel reprocessing plant (UP1 and ancillary facilities operated from 1958 to 1997) were located at Marcoule, in southern France. These historic facilities, together with the research labs that contributed to the development and commissioning of the processes implemented, are being decontaminated and dismantled. Other facilities near these nuclear plants will also be shut down in the next few years: the Phenix fast breeder reactor, the Celestin reactors and other ancillary units. Because the UP1 reprocessing plant and its related facilities were used for both commercial and defense activities, a dedicated group comprising three state-owned or private companies (CEA, EdF and COGEMA) was set up as the contracting authority from 1996 to 2004. Today the CEA is the contracting authority at Marcoule and has replaced AREVA NC as the site nuclear operator. AREVA acts as prime contractor for both operation of the main facilities and engineering of the dismantling projects. (authors)

  17. RERTR programme. French situation in 1996

    International Nuclear Information System (INIS)

    Guidez, J.; Ballagny, A.

    1996-01-01

    This paper summarizes the status of the RERTR Programme in France in 1996. The reactors which are affected by the RERTR Programme are those that consume a considerable amount of fuel. These are the neutron beam reactors Orphee (at Saclay) and RHF (at Grenoble) and the irradiation reactors Osiris (at Saclay) and Siloe (at Grenoble). Plans to construct a new 100 MW, multi-purpose MTR reactor using LEU fuel at the Atomic Research Center at Cadarache are described. Two main topics of fuel research and development are summarized: (1) improving knowledge on the reference silicide fuel, including optimization of the manufacturing process, thermal properties, behavior with cladding failure, etc., and (2) research into low-enriched uranium fuel with a higher U-235 content in order to limit fuel assembly consumption and to improve performance levels. Tests planned in the research and development programme for the silicide fuel are tabulated. The fuel cycle option adopted by the CEA to get rid of spent fuel elements is reprocessing. The 'Caramel' fuel elements consumed in the Osiris reactor until 1995 are currently being reprocessed in CEA facilities at Marcoule. The UAl and UAlx fuel elements irradiated in Siloe and Orphee are currently being reprocessed in the Cogema facilities at Marcoule (Plant UP1). However, the U3Si2 fuel elements irradiated in the Osiris reactor since 1995 will be progressively sent to interim storage dry facilities located at Cadarache. (author)

  18. Mortality risk in the french cohort of uranium miners: extended follow-up 1946-1999

    International Nuclear Information System (INIS)

    Blandine Vacquier; Dominique Laurier; Sylvaine Caer; Benoit Quesne

    2006-01-01

    Since the 1970's, exposure to radon and to its radioactive decay products has been studied in relation to lung cancer risk among cohorts of miners [1-3]. These studies concluded that cumulative exposure to radon was associated with an increased risk of death from lung cancer. In 1988, the International Agency for Research on Cancer (IARC) classified radon as a known pulmonary human carcinogen [4]. The French cohort of uranium miners has been established in order to assess the mortality risk of miners exposed to low levels of radon and its decay products as well as to other occupational hazards. The primary aim of the cohort study is the quantification of the relationship between cumulated radon exposure and risk of lung cancer death. The study has been conducted by the Institut de Radioprotection et de Surete Nucleaire (IRSN) since 1982, in collaboration with the Occupational Medical Service of COGEMA. The French Data Protection Authority (CNIL) gave approval for this study. Previous analyses have demonstrated an excess of lung cancer death associated with radon exposure. These results regarding lung cancer have been presented in several publications and congress [5-11]. In 2004, the follow-up of this cohort was extended from 31 December 1994 through 31 December 1999. The extension of the follow-up increases the statistical power of the cohort. The present article describes the extended cohort and the analysis of mortality based on the follow-up of the cohort to end of 1999. (authors)

  19. Carbon 14

    International Nuclear Information System (INIS)

    2002-03-01

    Carbon 14 is one of the most abundant radionuclides of natural and artificial origin in the environment. The aim of this conference day organized by the French society of radioprotection (SFRP) was to take stock of our knowledge about this radionuclide (origins, production, measurement, management, effects on health..): state-of-the-art of 14 C metrology; dating use of 14 C; 14 C management and monitoring of the Hague site environment; Electricite de France (EdF) and 14 C; radiological and sanitary impact of 14 C contamination at the Ganagobie site (Haute-Provence, France); metabolism and biological effects of 14 C; 14 C behaviour in the marine environment near Cogema-La Hague plant; distribution of 14 C activities in waters, mud and sediments of the Loire river estuary; dynamical modeling of transfers in the aquatic and terrestrial environment of 14 C released by nuclear power plants in normal operation: human dose calculation using the Calvados model and application to the Loire river; 14 C distribution in continents; modeling of 14 C transfers in the terrestrial environment from atmospheric sources. (J.S.)

  20. 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.)

  1. Chemistry of actinides and fission products in the nuclear-fuel cycle

    International Nuclear Information System (INIS)

    Anon.

    2004-01-01

    This colloquium was held under the auspices of the French and Russian Academies of Sciences, from 21 to 23 May 2003, at the 'Ecole nationale superieure de chimie de Paris' (ENSCP), under the cooperative framework agreed between the two Academies. Fifteen specialists from each country were brought together to present their results concerning research in their respective fields (industrial considerations, fundamental chemistry, the environment, new conditioning systems, hydro- and pyro-chemical separation techniques), situating the results in the general context of the two countries'common strategy for closing the nuclear fuel cycle and for the management of radioactive waste. The colloquium brought together 26 oral presentations, and three round table discussions (theoretical chemistry and modelling, the frontiers of research on the nuclear cycle, elemental characterisation). The speakers chosen represented a large section of the organisations involved in the research on these topics, from each country. This thematic issue of the Comptes Rendus Chimie presents some new insights into these topics and some original results. The colloquium was supported financially par the DRI of the French Academy des sciences, CNRS, IN2P3, CEA, Cogema, EDF, and ENSCP. (authors)

  2. SGN's Dismantling and Decommissioning engineering, projects experience and capabilities

    International Nuclear Information System (INIS)

    Destrait, L.

    1998-01-01

    Its experience in waste treatment, conditioning, storage and disposal, its cooperation with CEA and COGEMA Group in license agreements give SGN expertise in the decommissioning field. SGN's experience and background in all areas of nuclear facility decommissioning, such as chemical and mechanical cells, nuclear advanced reactors, reprocessing facilities result in fruitful references to the customers. The poster is presenting different achievements and projects with SGN's participation such as: - The decommissioning of Windscale Advanced Gas cooled Reactors (WAGR), in particular providing methodology and equipment to dismantle the Pressure and Insulation Vessel of the reactor. - The decommissioning plan of Ignalina (Lithuania) and Paldiski (Estonia), defining strategies, scenarios, necessary equipments and tools and choosing the best solutions to decommission the site under different influencing parameters such as cost, dose rate exposure, etc... - Th One Site Assistance Team (OSAT) at Chernobyl regarding the preparation works for the waste management and decommissioning of the plant. - The decommissioning of French nuclear facilities such as reprocessing (UP1) and reactor (EL4) plants. The important experience acquired during the facility management and during the first dismantling and decommissioning operations is an important factor for the smooth running of these techniques for the future. The challenge to come is to control all the operations, the choice of strategies, the waste management, the efficiency of tools and equipments, and to provide nuclear operators with a full range of proven techniques to optimise costs and minimize decommissioning personnel exposure. (Author)

  3. The use of the average plutonium-content for criticality evaluation of boiling water reactor mixed oxide-fuel transport and storage packages

    International Nuclear Information System (INIS)

    Mattera, C.

    2003-01-01

    Currently in France, criticality studies in transport configurations for Boiling Water Reactor Mixed Oxide fuel assemblies are based on conservative hypothesis assuming that all rods (Mixed Oxide (Uranium and Plutonium), Uranium Oxide, Uranium and (Gadolinium Oxide rods) are Mixed Oxide rods with the same Plutonium-content, corresponding to the maximum value. In that way, the real heterogeneous mapping of the assembly is masked and covered by an homogenous Plutonium-content assembly, enriched at the maximum value. As this calculation hypothesis is extremely conservative, Cogema Logistics (formerly Transnucleaire) has studied a new calculation method based on the use of the average Plutonium-content in the criticality studies. The use of the average Plutonium-content instead of the real Plutonium-content profiles provides a highest reactivity value that makes it globally conservative. This method can be applied for all Boiling Water Reactor Mixed Oxide complete fuel assemblies of type 8 x 8, 9 x 9 and 10 x 10 which Plutonium-content in mass weight does not exceed 15%; it provides advantages which are discussed in the paper. (author)

  4. BWR-spent fuel transport and storage with the TN trademark 9/4 and TN trademark 24BH casks

    International Nuclear Information System (INIS)

    Wattez, L.; Marguerat, Y.; Hoesli, C.

    2004-01-01

    The Swiss Nuclear Utilities have started in 2001 to store spent fuel in dry metallic dual-purpose casks in ZWILAG, the Swiss interim storage facility. BKW FMB Energy Ltd., as Muehleberg Nuclear Power Plant owner, is involved in this process and has selected to store its spent fuel, a new high capacity dual-purpose cask, the TN trademark 24BH. For the transport in a medium size cask, COGEMA LOGISTICS has developed a new cask, the TN trademark 9/4, to replace the NTL9 cask, which performed numerous transports of BWR spent fuel in the past decades. Licensed IAEA 1996, the TN trademark 9/4 is a 40 ton transport cask, for 7 BWR high burn-up spent fuel assemblies. The spent fuel assemblies can be transferred in the ZWILAG hot cell in the TN trademark 24BH cask. The first use of these casks took place in 2003. Ten TN trademark 9/4 transports were performed, and one TN trademark 24BH was loaded. After a brief presentation of the operational aspects, the paper will focus on the TN trademark 24BH high capacity dual purpose cask, the TN trademark 9/4 transport cask and describe in detail their characteristics and possibilities

  5. Status and prospects for spent fuel management in France

    International Nuclear Information System (INIS)

    Kaplan, P.

    1998-01-01

    The 70's oil crisis has shown that the energy resource dependence of France was too high. The decision was made by the French government to accelerate the implementation of an ambitious nuclear power programme, based on Light Water Reactors, and to do the utmost to reuse the energy bearing material included in the spent fuel. The French nuclear policy has not changed since then. This paper is aimed at describing the present status of implementation of this policy, and the associated prospects. It will first sum up the presentation made in 1995 to the Regular Advisory Group of IAEA on Spent Fuel Management. Then, it will update the situation of the main actors of the spent fuel management policy in France: EDF, the national utility; COGEMA, world leader on almost all the steps of the fuel cycle; CEA, the national research body in the field of nuclear science and its applications; ANDRA, national body in charge of the management of the waste arising from the nuclear activities in France, final disposal included. (author)

  6. National School of Dismantling

    International Nuclear Information System (INIS)

    Ivaldi, Fabienne

    2003-01-01

    The National Institut of Nuclear Sciences and Techniques founded of 2001 a National School of Dismantling, NSD, at the end, which was validated by CEA, COGEMA, EDF and ANDRA. This school addresses four major issues: Decontamination; Dismantling; Demolition and waste Disposal (4D). Dedicated for instructing scientific and technical knowledge and know-how, needed in dismantling the nuclear installations, NSD has as targets: - personnel at engineering and operational level; - personnel occupied with involved trades from conception through intervention; - students and employees on leave; - employees while training on the job. Initial basic education for students in collaboration with schools and universities concerns: - master degree in radioactive waste management; - master degree in dismantling; - professional license in 3 D; - pro 4 D graduation. NSD is also engaged in continual formation for employees qualified, or not, adapted to the needs generated by the following tasks and personnel: - introduction in dismantling; - project team; - specialist engineer; - team head; - agent for remedial action; - agent for dismantling. The National School of Dismantling joins a network of human and technological capabilities confined within the 4 D frame, namely: - scientific and technical competencies (experts, instructors working in the nuclear field and dismantling); - pedagogical competence (professionals from basic and continual education); - specific material means such as those used by construction site schools, mock-ups, rooms for practical training etc

  7. 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

  8. Radon exposure and mortality among the French cohort of uranium miners: 1946-1999

    International Nuclear Information System (INIS)

    Vacquier, B.; Tirmarche, M.; Laurier, D.; Caer, S.; Quesne, B.

    2006-01-01

    Full text of publication follows: The French cohort of uranium miners aims at evaluating the mortality risk of miners exposed to low levels of radon and its decay products and to other occupational hazards. Its primary aim is the quantification of the relationship between cumulated radon exposure and the risk of lung cancer death. However this study also allows to analyse risks for causes of death other than lung cancer. We present a new analysis of the mortality based on an extended follow-up of the cohort to end of 1999. Materials and methods: The French cohort of uranium miners has been followed by the Institut de Radioprotection et de Surete Nucleaire (I.R.S.N.) since the 1980's, in collaboration with the Occupational Medical Service of Compagnie Generale des Matieres Nucleaires (Cogema). The cohort was recently enlarged and the follow-up extended up to 1999. It includes men employed as miners for at least 1 year since 1946 at the Commissariat a l Energie Atomique (Cea) or at the Cogema. Individual vital status was ascertained through a national database and causes of death were determined according to death certificates. For each miner, yearly radon exposures was reconstructed and expressed in working level month (W.L.M.). Risk of death was estimated relatively to external reference rates from the general French male population. The classical method of standardized mortality ratios (S.M.R.s) was used to adjust for age and calendar year. Exposure-risk relationships have been estimated by Poisson regression, using a linear excess relative risk (E.R.R.) model with a lag time of 5 years. Results: The cohort comprises 5,098 miners. The mean duration of follow -up is 30.1 years (total of 153,272 person-years). The number of radon exposed miners is 4,134 with an average cumulative radon exposure of 36.5 W.L.M.. Miners lost to follow-up represent 1.4% of the cohort. A total of 1,471 deaths before age 85 is observed up to 1999. The analysis shows no excess for all

  9. MELOX fuel fabrication plant: Operational feedback and future prospects

    International Nuclear Information System (INIS)

    Hugelmann, D.; Greneche, D.

    2000-01-01

    As of December 1, 1998, 32 Europeans LWRs are loaded with MOX fuel. It clearly means that plutonium recycling in MOX fuels is a mature industry, with successful operational experience in fabrication plants in some European countries, especially in France. Indeed, the recycling of plutonium generated in LWRs is one of the objectives of the full Reprocessing-Conditioning-Recycling (RCR) strategy chosen by France in the 70's. The most impressive results of this strategy, is the fact that 31 of the 32 reactors are loaded with MOX fuels supplied by the COGEMA Group from the same efficient fabrication process, the MIMAS process, improved for the MELOX plant to become the A-MIMAS process. In France, 17 reactors are already loaded and 11 additional reactors are technically suited to do so. Indeed, the EDF MOX program plans to use MOX in 28 of its 57 reactors. An EDF 900 MWe reactor core contains 157 assemblies of 264 rods each. 52 fuel assemblies per year are necessary for a 'UO 2 3-batches-MOX 3-batches' core management. In this case, a third of the UO 2 and a third of the MOX assemblies are replaced yearly, that means 36 UO 2 fuel assemblies and 16 MOX fuel assemblies. Some MOX fuelled reactors have now switched from the previously described core management to a so-called 'hybrid core management'. In this case, a quarter of UO 2 assemblies is replaced yearly. The first EDF reactor loaded with MOX fuel was Saint-Laurent B1, in 1987. The in-core experience, based on several hundred assemblies loaded, with reloading on a 1/3 cycle basis, shows that there is no operational difference between UO 2 and MOX fuels, both in terms of performance and safety. MOX fueling of 900 MWe EDF's PWRs, with a limited in-core MOX ratio of 30%, has needed only minor adaptations, such as addition of control rods, modification of the boron concentration in the cooling system and precaution against radiation exposure, easy to set up (optimisation of the fresh MOX fuel handling process, remote

  10. Potentiality of hydroxylamine nitrate as a scrubbing reagent to trap iodine and nitrogen oxides in nuclear spent fuel dissolution off-gas

    International Nuclear Information System (INIS)

    Cau Dit Coumes, C.

    1998-01-01

    The management of low and medium-level radioactive effluents, newly implemented in Cogema-La Hague plants, foresee to replace tarring by vitrification. This process change imposes to greatly reduce the saline content of the effluents and in particular the sodium content to improve the leaching resistance of glass. Studies have been carried out to find a substitute to soda, today used to trap iodine and nitrogen oxides by counterflow washing of spent fuel dissolution gases. The aim of this work is to evaluate the potentialities of hydroxylamine nitrate. After a presentation of the chemistry of iodine and inorganic nitrogenous compounds, the reactions susceptible to take place inside the washing column are identified. An experimental study of of the reactions of hydroxylamine with molecular iodine, methyl iodide, nitrous acid, and nitrogen oxides (NO, NO 2 , N 2 O 3 and N 2 O 4 ) has permitted to precise in each case, the products, the stoichiometry, the kinetics and the reaction mechanisms. The results obtained show that only an hydroxylamine acid solution allows to simultaneously reduce iodine into iodide and to eliminate the nitrous acid formed by the hydrolysis of nitrogen oxides. Two models of the iodine/iodide/nitrous acid/hydroxylamine reaction system are proposed in acid environment. The first one, established from the kinetic laws of the reactions involved, has only a restricted domain of validity. The second one, obtained by applying the experimental research methodology, is valid over a wider experimental domain and has been used to determine the favorable conditions for the simultaneous and fast reduction of iodine and nitrous acid by hydroxylamine. (J.S.)

  11. TECHNICAL ASSESSMENT OF FRACTIONAL CRYSTALLIZATION FOR TANK WASTE PRETREATMENT AT THE DOE HANFORD SITE

    Energy Technology Data Exchange (ETDEWEB)

    HAMILTON, D.W.

    2006-01-03

    Radioactive wastes from one hundred seventy-seven underground storage tanks in the 200 Area of the Department of Energy (DOE) Hanford Site in Washington State will be retrieved, treated and stored either on site or at an approved off-site repository. DOE is currently planning to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions, which would be treated and permanently disposed in separate facilities. A significant volume of the wastes in the Hanford tanks is currently classified as medium Curie waste, which will require separation and treatment at the Waste Treatment Plant (WTP). Because of the specific challenges associated with treating this waste stream, DOE EM-21 funded a project to investigate the feasibility of using fractional crystallization as a supplemental pretreatment technology. The two process requirements for fractional crystallization to be successfully applied to Hanford waste include: (1) evaporation of water from the aqueous solution to enrich the activity of soluble {sup 137}Cs, resulting in a higher activity stream to be sent to the WTP, and (2) separation of the crystalline salts that are enriched in sodium, carbonate, sulfate, and phosphate and sufficiently depleted in {sup 137}Cs, to produce a second stream to be sent to Bulk Vitrification. Phase I of this project has just been completed by COGEMA/Georgia Institute of Technology. The purpose of this report is to document an independent expert review of the Phase I results with recommendations for future testing. A team of experts with significant experience at both the Hanford and Savannah River Sites was convened to conduct the review at Richland, Washington the week of November 14, 2005.

  12. Report of activity, July 1993 - June 1995; Rapport d`activite, Juillet 1993 - Juin 1995

    Energy Technology Data Exchange (ETDEWEB)

    Le Brun, C. [Lab. de Physique Corpusculaire, Caen Univ., 14 (France)

    1998-04-01

    This report presents the activity of `Laboratoire de Physique Corpusculaire` of Caen from July 1993 to June 1995. From its inception, at GANIL the nuclear physicists aimed at creating far off-equilibrium nuclear systems in order to obtain a better understanding of their properties as well as of nuclear matter. The first direction of research was the study of the excited nuclear matter i.e. the way in which the energy of heavy ion collisions is deposed in the compound system and nuclear fragments and the corresponding channels of their de-excitation. By means of NAUTILUS data and from comparisons of data with simulations it is now possible to measure life-times (down to 10{sup -22} s), the nuclear flow and the form of fragment emitters. These methods will be extensively used in the analysis of data taken with INDRA, which already has made evident a vaporization threshold. A second direction of research is based on the possibility to produce by fragmentation nuclei with a very anomalous neutron and proton composition. LISE, SISSI, and SPIRAL are used to re-accelerate the exotic or radioactive ions. By utilisation of DEMON the neutron halos of several nuclei has been studied, among which the one-neutron halo in {sup 19}C. The laboratory has participated also in large collaborations (NEMO) which investigated the neutrino nature and its rest mass which are important problems related to the validity of the particle physics standard model and, in turn, to the problem of the dark matter of the universe. A significant effort was attached to the realization of the utilized detectors and associated electronics. A special neutron detector was conceived and certified for COGEMA. The help of other institutions among which IN2P3, an CNRS institute, is acknowledged. There financial support as well as that obtained through ISMRA and the university has permitted the fruitful integration of LPC Caen in large national and international collaborations

  13. 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.)

  14. Monthly Record Tables, December 1998, with Supplement for the 4. quarter 1998

    International Nuclear Information System (INIS)

    1998-12-01

    This report, issued under the aegis of O.P.R.I. (Office of protection against ionizing radiations), contains the activity level measurements of the radiation monitoring units throughout the country recorded in December 1998. A supplement contains the data relative to the 4. quarter is also added. Data relative to atmospheric sampling refer to surface and high altitude air as well as to atmospheric tritium concentration at Valduc. For rain water, dry fallout and deposition at soil level weekly sampling were carried out and monthly surveillance is reported. The drinking, surface and ground water measurements are reported for nuclear and non-nuclear sites. Measurement on food chains refer to cow milk, thyroids of horned cattle and fishes in the national market. Activity levels of given radioisotopes are given for vegetables and coastal sea waters as well as for waste and rain waters. Surveillance of wastes from facilities other than basic nuclear units (hospitals, research units, etc) was measured downstream to large cities in waste waters, rivers, sediments and aquatic flora. Sanitary controls on food and environment are reported as well as those carried out on workers and on operators implied in 6 nuclear incidents without consequences which occurred in December 1998 in French NPPs. The quarterly results refer to the following 16 items: 1. Radioactivity inventory in feedwater (Calvados); 2.Drinking waters; 3.Hydro-mineral sources; 4.Sea medium at Nord-Cotentin; 5.Surveillance of major National Navy facilities; 6.Surveillance of CNPE at Gravelines; 7. Surveillance of CNPE at Civaux; 8.Surveillance of COGEMA site at Marcoule; 9.Marine fauna and flora; 10.Surveillance of rice fields at Camargue; 11.Surveillance of sea sediments in Seine mouth; 12.Controlled releases; 13.Food chains; 14.Animal bones; 15.Soils; 16.Integrating dosemeters

  15. Stochastic rat lung dosimetry for inhaled radon progeny: a surrogate for the human lung for lung cancer risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    Winkler-Heil, R.; Hofmann, W. [University of Salzburg, Division of Physics and Biophysics, Department of Materials Research and Physics, Salzburg (Austria); Hussain, M. [University of Salzburg, Division of Physics and Biophysics, Department of Materials Research and Physics, Salzburg (Austria); Higher Education Commission of Pakistan, Islamabad (Pakistan)

    2015-05-15

    Laboratory rats are frequently used in inhalation studies as a surrogate for human exposures. The objective of the present study was therefore to develop a stochastic dosimetry model for inhaled radon progeny in the rat lung, to predict bronchial dose distributions and to compare them with corresponding dose distributions in the human lung. The most significant difference between human and rat lungs is the branching structure of the bronchial tree, which is relatively symmetric in the human lung, but monopodial in the rat lung. Radon progeny aerosol characteristics used in the present study encompass conditions typical for PNNL and COGEMA rat inhalation studies, as well as uranium miners and human indoor exposure conditions. It is shown here that depending on exposure conditions and modeling assumptions, average bronchial doses in the rat lung ranged from 5.4 to 7.3 mGy WLM{sup -1}. If plotted as a function of airway generation, bronchial dose distributions exhibit a significant maximum in large bronchial airways. If, however, plotted as a function of airway diameter, then bronchial doses are much more uniformly distributed throughout the bronchial tree. Comparisons between human and rat exposures indicate that rat bronchial doses are slightly higher than human bronchial doses by about a factor of 1.3, while lung doses, averaged over the bronchial (BB), bronchiolar (bb) and alveolar-interstitial (AI) regions, are higher by about a factor of about 1.6. This supports the current view that the rat lung is indeed an appropriate surrogate for the human lung in case of radon-induced lung cancers. Furthermore, airway diameter seems to be a more appropriate morphometric parameter than airway generations to relate bronchial doses to bronchial carcinomas. (orig.)

  16. Comparison of the local-scale atmospheric dispersion model Cedrat with 85KR measurements

    International Nuclear Information System (INIS)

    Rennesson, M.; Devin, P.; Maro, D.; Fitamant, M.L.; Bouland, P.

    2004-01-01

    An accurate model of atmospheric dispersion of radionuclides over the complex terrain of the La Hague reprocessing plant (North Cotentin, France) has been developed by COGEMA, in partnership with Paris VI University. This model, called CEDRAT 1.0.1 (operational since October 2002), takes into account areas typically outside the validity limits of Gaussian models: relief and building influence, short-distance (beyond 500 m from the release point) and stable atmospheric conditions. The modelling tool is based on an original method: a 2D-meshed model for flow resolution at permanent rate in the prevailing wind direction, and a 3D description of the dispersion phenomena, taking into account wet and dry deposits, at permanent or transitory rate. This leads to an effective compromise between rapidity (45 min on a 6000 nodes grid, with a standard PC), robustness and accuracy, coupled with a user-friendly interface. Primarily the validation process consisted of a comparison with the 3D complex dispersion reference model MERCURE, developed by EDF. Then, MERCURE and CEDRAT results were compared on real release scenario basis, for which actual meteorological conditions and tracer data collected at monitoring stations around the site were known. To enlarge this validation process, a second level of comparison was made in collaboration with a IRSN Cherbourg team, through different field experiments, which provided both ground and elevated level measurements (collected with a captive balloon), for different stability classes of the atmosphere. The plume tracer is krypton 85, an inert gas released from a height of 100 m. Thus, the aim of this paper is to present the original method to describe short distance dispersion over complex terrain and its validation enrichment for stability conditions and areas not yet observed, through wind and cross-wind Atmospheric Transfer Coefficients comparisons, at both ground and elevated levels. (author)

  17. Cross border transport of vitrified residues from France to Germany

    International Nuclear Information System (INIS)

    Graf, W.; Jussofie, A.

    2016-01-01

    Until 1994 reprocessing was the only legal way to manage German spent fuel. Since in 1984 the national reprocessing concept was abandoned the reprocessing abroad was the only existing disposal route. With the amendment of the Atomic Energy Act in 2002 spent fuel management changed completely since from 1 June 2005 any delivery of spent fuel to reprocessing plants was prohibited and the direct disposal of spent fuel became mandatory. Until 2005 the total amount of spent fuel to be reprocessed abroad added up to 6080 t HM, 5309 t HM thereof in France. According to the commercial contracts signed between the German utilities and COGEMA, now AREVA NC, in France and BNFL, now INS in UK, and to the intergovernmental agreements concluded between Germany and France or UK the waste generated from reprocessing has to be returned to Germany. The return of high active vitrified waste from La Hague to the interim storage facility at Gorleben was not only demanding from the view of safety ensured by the cask design but especially for security reasons since the Gorleben area served as a target for nuclear opponents from the first transport in 1996 to the latest one in 2010. The protection against sabotage of the railway lines and mass protests needed improved security measures. Special working forces and projects have been set up in France and Germany to cope with this situation. A complex transport organization was necessary to involve all parties in line with the German and French security requirements during transport. All transports have been completed successfully so far thus confirming the efficiency of the applied measures. (author)

  18. Fresh MOX fuel transport in Germany: experience for using the MX6

    Energy Technology Data Exchange (ETDEWEB)

    Lallemant, T. [COGEMA Logistics (AREVA Group), Bagnols/sur Ceze (France); Marien, L. [FBFC-I (AREVA Group), Dessel (Belgium); Wagner, R. [RWE, Gundremmingen (Germany); Jahreiss, W. [FRAMATOME ANP GmbH (AREVA Group), Erlangen (Germany); Tschiesche, H. [NCS, Hanau (Germany)

    2004-07-01

    The MX6 packaging developed by COGEMA LOGISTICS replaces the BWR SIEMENS packaging and SIEMENS III packaging for the transport of either BWR or PWR fresh MOX assemblies. It is licensed in France, Germany and Belgium according to TS-R-1 requirements (IAEA 1996). The associated security transport system was developed in co-operation with NCS (Nuclear Cargo + Service GmbH). The MX6 packaging is based on innovative solutions implemented at each step of the design. In 2004, RWE GUNDREMMINGEN Nuclear Power Plant (NPP) will be the first NPP delivered with the MX6 system and MOX assemblies manufactured by BELGONUCLEAIRE and FBFC in Belgium. Before this first transport, successful cold tests were performed for qualification of the whole system with the participation of all parties involved: NPP, carrier, fuel supplier and local Authorities. These tests were conducted by the NPP's operators in FBFC and GUNDREMMINGEN facilities and lead to the validation of the operating manual. Specific conditions for the return of the empty MX6 were also agreed between all parties. Similar operation will be conducted in each NPP before the first use of the MX 6. The large payload of the MX6: - 16 BWR MOX assemblies in one packaging instead of 2 - 6 PWR MOX assemblies in one packaging instead of 3 contributes to the optimisation of the dose uptake during unloading in the NPP. In this paper, the main contributors to the first MOX transport to Germany with the MX6 will present their involvement and feedback at each step of the transport of this new type of packaging, including loading and unloading operations. The use of the MX6 will be extended to other German NPP's from the next year. After FBFC in Belgium, MELOX in France will load the MX6 as well as the current MX8 packaging for the delivery to the French NPP's.

  19. Country nuclear fuel cycle profile: Netherlands

    International Nuclear Information System (INIS)

    2005-01-01

    In 2002, the Netherlands' only reactor, the 449 MW(e) PWR at Borssele, provided 3.6 TW·h of electricity, equivalent to 4% of domestic electricity output. Two successive governments ordered the Borssele nuclear power plant to shut down by December 2003, earlier than had originally been foreseen. However, the Government that came into office at the beginning of August 2002 has agreed to postpone closure of this plant, as it said 'taking into account the Kyoto obligations, it would not be sensible to close Borssele prematurely'. The new Cabinet will consult with the owner of the plant to seek an agreement on continuing its operation, taking into account its economic and technical lifetime. Uranium enrichment is carried out by Urenco Nederland B.V., which is located in Almelo. Urenco Nederland is owned by the multinational company Urenco Ltd, which is located in Marlow (UK) and which has three shareholders holding equal shares: Ultra Centrifuge Nederland (UCN) in the Netherlands, Uranit (Germany) and BNFL. The Government of the Netherlands owns 99% of the shares in UCN. The current capacity of Urenco Nederland is 1850 t SWU/a. However, in 1999 the company obtained a licence to expand its capacity to 2500 t SWU/a, for which a fifth enrichment plant has been built at the Almelo site. In early 2003 a new nuclear licence was issued to increase capacity to 2800 t SWU/a. Urenco uses advanced gas ultracentrifuge technology for the enrichment of uranium. Spent fuel is being reprocessed at the BNFL reprocessing facility in the UK and at the Cogema reprocessing facility in France

  20. German research reactor back-end provisions

    International Nuclear Information System (INIS)

    Koester, Siegfried; Gruber, Gerhard

    2002-01-01

    Germany has several types of Research Reactors in operation. These reactors use fuel containing uranium of U.S. origin. Basically all the fuel which will be spent until May 2006 will be returned to the U.S. under existing contracts with the U.S. Department of Energy. The contracts are based on the U.S. FRR SNF (Foreign Research Reactor Spent Nuclear Fuel) Program which started in May 1996 and which will last for 10 years. In 1990, the German Federal Government started a program to long-term store (approx. 40 years) and finally dispose of spent fuel in Germany after the so-called U.S. fuel return window will be closed. In order to long-term store the fuel, a special container was designed which covers all different types of spent fuel from the Research Reactors. The container called 'CASTOR MTR 2' is basically licensed and is already in use for the spent fuel of Russian origin from the 'Research Reactor Rossendorf' in the eastern part of Germany. All that fuel is expected to be stored in the existing intermediate storage facility, the so-called BZA (Brennelemente Zwischenlager Ahaus). BZA already accomodates spent fuel from the former THTR-300 high temperature reactor. A final repository does not yet exist in Germany. Alternative provisions to close the back-end of the Research Reactor fuel cycle are reprocessing at COGEMA (France) or in Russian facilities, perspectively. Waste return in a form to be agreed will be mandatory, at least in France. (author)

  1. Gamma spectroscopy modelization intercomparison of the modelization results using two different codes (MCNP, and Pascalys-mercure)

    International Nuclear Information System (INIS)

    Luneville, L.; Chiron, M.; Toubon, H.; Dogny, S.; Huver, M.; Berger, L.

    2001-01-01

    The research performed in common these last 3 years by the French Atomic Commission CEA, COGEMA and Eurisys Mesures had for main subject the realization of a complete tool of modelization for the largest range of realistic cases, the Pascalys modelization software. The main purpose of the modelization was to calculate the global measurement efficiency, which delivers the most accurate relationship between the photons emitted by the nuclear source in volume, punctual or deposited form and the germanium hyper pure detector, which detects and analyzes the received photons. It has been stated since long time that experimental global measurement efficiency becomes more and more difficult to address especially for complex scene as we can find in decommissioning and dismantling or in case of high activities for which the use of high activity reference sources become difficult to use for both health physics point of view and regulations. The choice of a calculation code is fundamental if accurate modelization is searched. MCNP represents the reference code but its use is long time calculation consuming and then not practicable in line on the field. Direct line-of-sight point kernel code as the French Atomic Commission 3-D analysis Mercure code can represent the practicable compromise between the most accurate MCNP reference code and the realistic performances needed in modelization. The comparison between the results of Pascalys-Mercure and MCNP code taking in account the last improvements of Mercure in the low energy range where the most important errors can occur, is presented in this paper, Mercure code being supported in line by the recent Pascalys 3-D modelization scene software. The incidence of the intrinsic efficiency of the Germanium detector is also approached for the total efficiency of measurement. (authors)

  2. Force-feedback tele operation of industrial robots a cost effective solution for decontamination of nuclear plants

    International Nuclear Information System (INIS)

    Desbats, P.; Andriot, C.; Gicquel, P.; Viallesoubranne, J.P.; Souche, C.

    1998-01-01

    Decontamination and maintenance in hot cells are some new emerging applications of industrial robots in the nuclear fuel cycle plants. Industrial robots are low cost, accurate and reliable manipulator arms which are used in manufacturing industries usually. Thanks to the recent evolution of robotics technologies, some industrial robots may be adapted to nuclear environment. These robots are transportable, sealed and can be decontaminated, and they may be 'hardened' up to a level of irradiation dose sufficient for operation in low and medium irradiating/contaminating environments. Although industrial robots are usually programmed to perform specific and repetitive tasks, they may be remotely tele-operated by human operators as well. This allows industrial robots to perform usual tele-manipulation tasks encountered in the nuclear plants and more. The paper presents the computer based tele-operation control system TAO2000 TM , developed by the Tele-operation and Robotics Service of CEA, which has been applied to the RX90 TM industrial robot from ST-UBLI company. This robot has been selected in order to perform various maintenance and decontamination tasks in COGEMA plants. TAO2000 provides the overall tele-robotic and robotic functions necessary to perform any remote tele-operation application in hostile environment: force-feedback master-slave control; computer- assisted tele-operation of mechanical processes; trajectory programming as well as various robotics functions; graphical modelling of working environment and simulation; automatic path planning with obstacle avoidance; man-machine interface for tasks programming and mission execution. Experimental results reported in the paper demonstrate the feasibility of force-feedback master-slave control of standard industrial robots. Finally, the design of new, cost effective. tele-operation systems based on industrial robots may be intended for nuclear plants maintenance. (author)

  3. SMOPY, a new NDA tool for safeguards of LEU and MOX spent fuel

    International Nuclear Information System (INIS)

    Lebrun, A.; Merelli, M.; Szabo, J.-L.; Huver, M.; Arenas-Carrasco, J.

    2001-01-01

    Upon IAEA request, the French support program to IAEA Safeguards has developed a new device for control of the irradiated LEU and MOX fuels. The Safeguards Mox Python (SMOPY) is the achievement of a 4 years R and D program supported by CEA and COGEMA in partnership with Eurisys Mesures. The SMOPY system is based on the combination of 2 NDA techniques (passive neutron and room temperature gamma spectrometry) and on line interpretation tools (automatic gamma spectrum interpretation, depletion code EVO). Through the measurement managing software, all this contributes to the fully automatic measurement, interpretation and characterization of any kind of spent fuel. The device is transportable (50 kg, 60 cm) and is composed of four parts: 1. the measurement head with one high efficiency fission chamber and a micro room temperature gamma spectrometric probe; 2. the carrier which carries the measurement head. The carrier bottom fits the racks for accurate positioning and its top fits operator's fuel moving tool; 3. the portable electronic cabinet which includes both neutron and gamma electronic cards; 4. the portable PC which gets inspectors data, controls the measurement, get measured values, interprets them and immediately provides the inspector with worthwhile info for appropriate on the field decisions. Main features of SMOPY are: Discrimination of MOX versus LEU irradiated fuels in any case (conservative case is one cycle MOX versus three cycles LEU after short cooling time); Full characterization of irradiated LEU (burnup, cooling time, Pu amounts ...); Partial Defect Test on LEU fuels. A first version of SMOPY has been tested in industrial condition during summer 2000. This tests shown a need of shielding improvement around the gamma detector. A new version has been build a will be qualified during a new field test and then the system will be ready for routine operation in IAEA and commercial delivery. After giving details about the system itself, this paper

  4. TECHNICAL ASSESSMENT OF FRACTIONAL CRYSTALLIZATION FOR TANK WASTE PRETREATMENT AT THE DOE HANFORD SITE

    International Nuclear Information System (INIS)

    HAMILTON, D.W.

    2006-01-01

    Radioactive wastes from one hundred seventy-seven underground storage tanks in the 200 Area of the Department of Energy (DOE) Hanford Site in Washington State will be retrieved, treated and stored either on site or at an approved off-site repository. DOE is currently planning to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions, which would be treated and permanently disposed in separate facilities. A significant volume of the wastes in the Hanford tanks is currently classified as medium Curie waste, which will require separation and treatment at the Waste Treatment Plant (WTP). Because of the specific challenges associated with treating this waste stream, DOE EM-21 funded a project to investigate the feasibility of using fractional crystallization as a supplemental pretreatment technology. The two process requirements for fractional crystallization to be successfully applied to Hanford waste include: (1) evaporation of water from the aqueous solution to enrich the activity of soluble 137 Cs, resulting in a higher activity stream to be sent to the WTP, and (2) separation of the crystalline salts that are enriched in sodium, carbonate, sulfate, and phosphate and sufficiently depleted in 137 Cs, to produce a second stream to be sent to Bulk Vitrification. Phase I of this project has just been completed by COGEMA/Georgia Institute of Technology. The purpose of this report is to document an independent expert review of the Phase I results with recommendations for future testing. A team of experts with significant experience at both the Hanford and Savannah River Sites was convened to conduct the review at Richland, Washington the week of November 14, 2005

  5. Surface contamination of spent fuel convoys - resumption of transport in France

    International Nuclear Information System (INIS)

    Pertuis, V.

    2000-01-01

    In France, 1998 was marked by the transport of spent fuel from EDF plants being suspended and then resumed. From the time the first inspections were carried out by the Nuclear Installations Safety Directorate (NISD), in charge of monitoring radioactive and fissile material for civil use since June 1997, surface contamination was found in a high percentage of packages and/or wagons containing spent fuel. The different expert appraisals showed that this had no consequences for the health of the public or of workers. Aiming at the resumption of transport, EDF and Cogema presented to the safety authority a plan of action including an increase in monitoring (number of points and cross-checking by SGS Qualitest), more widespread observance of good practices resulting from analyses by EDF and conclusions of its nuclear inspectorate, and an improvement in radiological cleanliness in the area where casks were loaded. During the inspections carried out at EDF plants, the NISD verified the application of this plan. Several observations were, nevertheless, made regarding maintenance of equipment, failure to apply procedures on a corporate level and the traceability of certain operations. The measures taken to sufficiently inform the public were applied. The NISD is continuing its monitoring actions to ensure that all EDF plants adopt best practices. However, the overall clean-up of EDF plants is a long-term operation. Finally, the NISD is continuing its monitoring of the different stages of spent fuel transport as well as other types of transport of radioactive materials associated with nuclear activities. (author)

  6. Within AREVA, FRAMATOME ANP and its worldwide experience with PWR and BWR fuels

    International Nuclear Information System (INIS)

    Watteau, Michel; Esteve, Bernard; Giese, Ulrich; Matheson, John

    2002-01-01

    Faced with obvious energy procurement security needs and the increasing concern about global warming, many countries are making a lucid analysis of their energy situation and reconsidering the multiple assets of nuclear energy. After the European Commission's Green Paper evaluation which was endorsed by the European Parliament, the United States gave a strong signal to the whole world by deciding to extent the operating life time of its existing NPPs and by envisioning the construction of new ones. In Asia, here in Korea, and in Japan, the People's Republic of China, Taiwan, large-scale nuclear power plant programs are being pursued. It was in this context, with the aim of ever-greater competitiveness, that the AREVA group was conceived. The aim is for all our skills to have a higher profile on the international markets, so that we are in a stronger position to develop a leadership in our two main high tech sectors of interconnect - electronics and nuclear. In the nuclear sector, the pooling of the Cogema and Framatome ANP forces is enabling AREVA to offer a comprehensive service package ranging from uranium mining to decommissioning, encompassing the design and construction of plants and their fuel; AREVA's experience is grounded in unequalled know-how. Further, with the CEA, a multidisciplinary research organization in charge of anticipating the emerging technologies, as a close partner, AREVA has a unique strategic vision. With this set-up, AREVA has the financial resources it needs to forge the alliances necessary for its development, so that it can best confront international competition and meet the requirements of its customers world-wide

  7. France without nuclear power

    International Nuclear Information System (INIS)

    Barre, B.; Charmant, A.; Devezeaux, J.G.; Ladoux, N.; Vielle, M.

    1995-01-01

    As environmental issues (particularly questions associated with the greenhouse effect) become a matter of increasing current concern, the French nuclear power programme can, in retrospect, be seen to have had a highly positive impact upon emissions of atmospheric pollutants. The most spectacular effect of this programme was the reduction of carbon dioxide emissions from 530 million tonnes per annum in 1973 to 387 million tonnes per annum today. Obviously, this result cannot be considered in isolation from the economic consequences of the nuclear power programme, which have been highly significant.The most obvious consequence of nuclear power has been the production of cheap electricity, while a further consequence has been the stability of electricity prices resulting from the increasing self-sufficiency of France in energy supplies (from 22% in 1973 to 49.% in 1992). Moreover, French nuclear industry exports. In 1993, 61.7 TW·h from nuclear production were exported, which contributed F.Fr. 14.2 billion to the credit side of the balance of payment. For the same year, Framatome exports are assessed at about F.Fr. 2 billion, corresponding to manufacturing and erection of heavy components, and maintenance services. Cogema, the French nuclear fuel operator, sold nuclear materials and services for F.Fr. 9.3 billion. Thus, nuclear activities contributed more than F.Fr. 25 billion to the balance of payment. Therefore, a numerical assessment of the macroeconomic impact of the nuclear power programme is essential for any accurate evaluation of the environmental consequences of that programme. For this assessment, which is presented in the paper, the Micro-Melodie macroeconomic and energy supply model developed by the Commissariat a l'energie atomique has been used. (author). 6 refs, 4 figs, 1 tab

  8. Neutron absorber qualification and acceptance testing from the designer's perspective

    Energy Technology Data Exchange (ETDEWEB)

    Bracey, W. [Transnuclear, Inc, Hawthorne, NY (United States); Chiocca, R. [Cogema Logistics, St. Quentin en Yvelines (France)

    2004-07-01

    Starting in the mid 1990's, the USNRC began to require less than 100% credit for the 10B present in fixed neutron absorbers spent fuel transport packages. The current practice in the US is to use only 75% of the specified 10B in criticality safety calculations unless extensive acceptance testing demonstrates both the presence of the 10B and uniformity of its distribution. In practice, the NRC has accepted no more than 90% credit for 10B in recent years, while other national competent authorities continue to accept 100%. More recently, with the introduction of new neutron absorber materials, particularly aluminum / boron carbide metal matrix composites, the NRC has also expressed expectations for qualification testing, based in large part on Transnuclear's successful application to use a new composite material in the TN-68 storage / transport cask. The difficulty is that adding more boron than is really necessary to a metal has some negative effects on the material, reducing the ductility and the thermal conductivity, and increasing the cost. Excessive testing requirements can have the undesired effect of keeping superior materials out of spent fuel package designs, without a corresponding justification based on public safety. In European countries and especially in France, 100% credit has been accepted up to now with materials controls specified in the Safety Analysis Report (SAR): Manufacturing process approved by qualification testing Materials manufacturing controlled under a Quality Assurance system. During fabrication, acceptance testing directly on products or on representative samples. Acceptance criteria taking into account a statistical uncertainty corresponding to 3{sigma}. The original and current bases for the reduced {sup 10}B credit, the design requirements for neutron absorber materials, and the experience of Transnuclear and Cogema Logistics with neutron absorber testing are examined. Guidelines for qualification and acceptance testing and

  9. K-infinite trends with burnup, enrichment, and cooling time for BWR fuel assemblies

    International Nuclear Information System (INIS)

    Broadhead, B.L.

    1998-08-01

    This report documents the work performed by ORNL for the Yucca Mountain project (YMP) M and O contractor, Framatome Cogema Fuels. The goal of this work was to obtain k inf values for infinite arrays of flooded boiling-water-reactor (BWR) fuel assemblies as a function of various burnup/enrichment and cooling-time combinations. These scenarios simulate expected limiting criticality loading conditions (for a given assembly type) for drift emplacements in a repository. Upon consultation with the YMP staff, a Quad Cities BWR fuel assembly was selected as a baseline assembly. This design consists of seven axial enrichment zones, three of which contain natural uranium oxide. No attempt was made to find a bounding or even typical assembly design due to the wide variety in fuel assembly designs necessary for consideration. The current work concentrates on establishing a baseline analysis, along with a small number of sensitivity studies which can be expected later if desired. As a result of similar studies of this nature, several effects are known to be important in the determination of the final k inf for spent fuel in a cask-like geometry. For a given enrichment there is an optimal burnup: for lower burnups, excess energy (and corresponding excess reactivity) is present in the fuel assembly; for larger burnups, the assembly is overburned and essentially driven by neighboring fuel assemblies. The majority of the burnup/enrichment scenarios included in this study were for some near-optimum burnup/enrichment combinations as determined from Energy Information Administration (EIA) data. Several calculations were performed for under- and over-burned fuel to show these effects

  10. An example of R and D on safety assessment: study of a prolonged loss of cooling of halw (beyond design accident)

    International Nuclear Information System (INIS)

    Mercier, J.P.; Bonneval, F.; Martineau, D.; Gue, J.P.; Philippe, M.

    1991-01-01

    The consequences of a loss of cooling of storage tanks of fission products concentrated solutions were studied, for a variable period, in the context, of the safety analysis of the COGEMA spent fuel reprocessing plants of La Hague. As a result of fission products-induced heat emission, a prolonger loss of cooling could involve the progressive evaporation of solutions up to dryout and lead to the formation of radioactive aerosols and then of volatile species of ruthenium likely to be released in off gas circuits of the tanks. With the aim of determining the radioactivity fraction likely to be transferred throughout the loss of cooling out of the storage tanks, an extensive R and D programme was performed, including the main following stages: - experimental determination of the factor of radioactivity transfer through aerosols out of the tanks; - modelling, by means of a calculation code, of the aerosols transfer into the off gas circuits; - experimental study of the ruthenium behaviour with tests carried out in laboratory, by evaporation of samples representative of nitric solutions of fission products. The main conclusions can be summarized as follows (by assuming a heat power density of 10 watts per litre of solution and a storage system completely adiabatic): - the evaporation of solutions starts more than 5 hours after the total loss of cooling, the 10 -4 value being an over-estimated value of the factor of radioactivity transfer by aerosols out of the tanks; - transfer factor through the off gas circuits varies, according to the physical characteristics of aerosols, from 0 to 8.10 -2 ; - ruthenium volatilized only during the final stage of evaporation, shortly before dryout; the minimum time to reach dryness is about 90 hours

  11. Field test demonstration of emplacement feasibility of precompacted clay buffer materials in a granitic medium

    International Nuclear Information System (INIS)

    Jorda, M.; Lajudie, A.; Gatabin, C.; Atabek, R.

    1992-01-01

    Field test demonstration of emplacement feasibility of precompacted clay buffer materials in a granitic medium has been successfully carried out in February 1990 at the mining centre of FANAY. SILORD site was selected allowing the drilling through the 'Raise Boring' technique of pits of 30 m depth minimum between two pre-existent galleries. Two pits of 37 m depth were drilled and characterized in detail: mean diameter and vertical deviation measurements, valuation of the surface condition (rugosity) and cracking. The pit which was the most regular was selected for the feasibility test it-self. In parallel, manufacturing and handling techniques for the engineered barrier were improved. The bricks were made from a powdered mixture of clay and 10% sand and formed the barrier which was installed in the pit using iron baskets. The technique used was compacting by uniaxial pressing at 64 MPa. Twenty eight baskets containing the engineered barrier were fabricated at LIBOS (refractory manufactory of CTE Group) and taken to FANAY-SILORD. A maximal diameter of 96.03 cm was determined for the basket passing through (basket height = 1.335 m) and verified by the lowering of basket gauges in the pit. The baskets were stacked up in the pit, without any difficulty, with a mean radial gap of 1.6 cm (for a pit mean diameter of 99.3 cm). Three simulated COGEMA waste containers were then satisfactorily installed. The real volume to be sealed, including residual voids, was estimated at 21.47 m 3 . The engineered barrier weight after emplacement came to 36280 kg leading to a dry density in service, i.e. after the engineered barrier swelling, of 1.69. 30 figs

  12. An example of nuclear co-operation: The Republic of Korea and France

    International Nuclear Information System (INIS)

    Lebreton, G.

    1983-01-01

    France and the Republic of Korea are pursuing the same objectives: they have decided to meet a large part of their electricity needs with nuclear power, and thereby increase their independence in energy matters. Both began ambitious national nuclear programmes some years ago, and it is natural that they should whish to co-operate. In November 1980, the Korean Electric Company (KEPCO) signed two contracts with French industry: one with Framatome for the supply of two nuclear islands and two 900 MW(e) PWR units (KNU 9 and 10); and one with Cogema for the supply of enriched uranium. These contracts were supplemented in February 1982 by a third contract, signed with Alsthom-Atlantique for the supply of two conventional islands. The three contracts are enabling the Republic of Korea to diversify its sources of supply and to have access to French experience. Under these projects the envisaged collaboration, which will entail the presence of some hundreds of French engineers in the Republic of Korea and also citizens of the latter in France and thereby forge firm and beneficial links, will apply to the following fields: project organization and management; nuclear engineering proper; manufacture of equipment; and training of staff of the Republic of Korea. However, it is hoped that nuclear co-operation between these two countries will extend much further. The competent French authorities are ready to work with the Republic of Korea to provide in full the setting needed for the development of an ambitious nuclear programme, in particular in aspects such as the adoption of codes and standards, safety authorities, the fuel cycle, and research and development. Finally, French industry is prepared to join the industrial efforts which the Republic of Korea wishes to undertake in order to set up a modern and efficient national industry. (author)

  13. 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)

  14. Method of impact evaluation of storage sites for uranium ore tailings

    International Nuclear Information System (INIS)

    Servant, A.C.; Cessac, B.

    2001-11-01

    Mining and ore processing generate liquid effluents and solid waste ( tailings) in important quantities. On fifty years exploitation, 50 millions tons of tailings have been stored on twenty sites in France. From a radiological point of view, the uranium tailings contain only natural radioisotopes, daughters of 238 U and 235 U families and for a low part daughter's of 232 Th family. Their activity stay low to very low, under the ore activity. It decreases very slowly because of the long period of some radionuclides ( 230 Th, 75 000 years, 226 Ra, 1600 years). generally stored on the exploitation site, these tailings constitute a radiological source term of which it is necessary to evaluate the impact on man and environment. At close-down of an uranium ore exploitation site, the operator is required to give to the prefect of his region a file of rehabilitation with the dispositions to take to limit the radiological impact of the storage. It is in this frame that the direction of pollutions and risks prevention (D.P.P.R.) from the Minister of Territory landscaping and the Institute of protection and nuclear safety (I.R.S.N.) established a convention, reference 56/2000, relative to investigations in matter of radiological impact evaluation of uranium tailings storage sites, in order to supply a document allowing to judge the pertinence of the different files made by Cogema in the frame of tailings storage of uranium ore processing. The present document constitutes the report planned at the 3. article ( 3. paragraph) of the convention. It gives the information necessary to the evaluation of impact studies for the sites in question. (N.C.)

  15. Detectors - Electronics

    International Nuclear Information System (INIS)

    Bregeault, J.; Gabriel, J.L.; Hierle, G.; Lebotlan, P.; Leconte, A.; Lelandais, J.; Mosrin, P.; Munsch, P.; Saur, H.; Tillier, J.

    1998-01-01

    The reports presents the main results obtained in the fields of radiation detectors and associated electronics. In the domain of X-ray gas detectors for the keV range efforts were undertaken to rise the detector efficiency. Multiple gap parallel plate chambers of different types as well as different types of X → e - converters were tested to improve the efficiency (values of 2.4% at 60 KeV were reached). In the field of scintillators a study of new crystals has been carried out (among which Lutetium orthosilicate). CdTe diode strips for obtaining X-ray imaging were studied. The complete study of a linear array of 8 CdTe pixels has been performed and certified. The results are encouraging and point to this method as a satisfying solution. Also, a large dimension programmable chamber was used to study the influence of temperature on the inorganic scintillators in an interval from -40 deg. C to +150 deg. C. Temperature effects on other detectors and electronic circuits were also investigated. In the report mentioned is also the work carried out for the realization of the DEMON neutron multidetector. For neutron halo experiments different large area Si detectors associated with solid and gas position detectors were realized. In the frame of a contract with COGEMA a systematic study of Li doped glasses was undertaken aiming at replacing with a neutron probe the 3 He counters presently utilized in pollution monitoring. An industrial prototype has been realised. Other studies were related to integrated analog chains, materials for Cherenkov detectors, scintillation probes for experiments on fundamental processes, gas position sensitive detectors, etc. In the field of associated electronics there are mentioned the works related to the multidetector INDRA, data acquisition, software gamma spectrometry, automatic gas pressure regulation in detectors, etc

  16. Detectors - Electronics; Detecteurs - Electronique

    Energy Technology Data Exchange (ETDEWEB)

    Bregeault, J.; Gabriel, J.L.; Hierle, G.; Lebotlan, P.; Leconte, A.; Lelandais, J.; Mosrin, P.; Munsch, P.; Saur, H.; Tillier, J. [Lab. de Physique Corpusculaire, Caen Univ., 14 (France)

    1998-04-01

    The reports presents the main results obtained in the fields of radiation detectors and associated electronics. In the domain of X-ray gas detectors for the keV range efforts were undertaken to rise the detector efficiency. Multiple gap parallel plate chambers of different types as well as different types of X {yields} e{sup -} converters were tested to improve the efficiency (values of 2.4% at 60 KeV were reached). In the field of scintillators a study of new crystals has been carried out (among which Lutetium orthosilicate). CdTe diode strips for obtaining X-ray imaging were studied. The complete study of a linear array of 8 CdTe pixels has been performed and certified. The results are encouraging and point to this method as a satisfying solution. Also, a large dimension programmable chamber was used to study the influence of temperature on the inorganic scintillators in an interval from -40 deg. C to +150 deg. C. Temperature effects on other detectors and electronic circuits were also investigated. In the report mentioned is also the work carried out for the realization of the DEMON neutron multidetector. For neutron halo experiments different large area Si detectors associated with solid and gas position detectors were realized. In the frame of a contract with COGEMA a systematic study of Li doped glasses was undertaken aiming at replacing with a neutron probe the {sup 3}He counters presently utilized in pollution monitoring. An industrial prototype has been realised. Other studies were related to integrated analog chains, materials for Cherenkov detectors, scintillation probes for experiments on fundamental processes, gas position sensitive detectors, etc. In the field of associated electronics there are mentioned the works related to the multidetector INDRA, data acquisition, software gamma spectrometry, automatic gas pressure regulation in detectors, etc

  17. 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

  18. Development opportunities for northern aboriginal communities from Saskatchewan's uranium mining industry

    International Nuclear Information System (INIS)

    Richards, A.

    2003-01-01

    A. Richards, a public relations specialist from Cogema Resources Inc., discussed the programmes for human resource and community development in northern Saskatchewan. This region has the world's largest known high-grade deposits of uranium as well as a high level of provincial, public and northern community support. A mainly Aboriginal population of around 35 000 with a very high proportion of young persons entering the work force, lives in small, dispersed communities in a landscape of forest and lakes. All of the uranium mines are in remote locations with 'local impact' communities often several hundred kilometres away. In the late 1970's a public board of inquiry set none operating conditions that included maximizing opportunities for northern business and employment. Dozens of joint initiatives have since been developed and resulted in innovative hiring, training and transportation programmes, as well as support programmes to improve health, education, professional and business development and quality of life in the communities. Residents of northern Saskatchewan, like all other Canadians, are not prepared to accept environmental risks in return for economic opportunities. Three regional Environmental Quality Committees, with representatives froth all of the northern communities, work with Provincial agencies and the uranium mining industry to ensure community concerns are included in decisions. Northern hunters and fishermen, whose close links with the land are respected, provide relevant data to the Environmental Monitoring Program. Mutual trust is developed through constant interaction and dialogue in one-to-one relationships. Traditional activities like trapping are given their full importance. A Community Vitality Project jointly monitors social well being as defined by northern interests and culture. Compensations and company donations in some cases provide resources for community activities. (author)

  19. High burnup MOX fuel assembly

    International Nuclear Information System (INIS)

    Blanpain, P.; Brunel, L.

    1999-01-01

    From the outset, the MOX product was required to have the same performance as UO 2 in terms of burnup and operational flexibility. In fact during the first years the UO 2 managements could not be applied to MOX. The changeover to an AFA 2G type fuel allowed an improvement in NPP operational flexibility. The move to the AFA 3G design fuel will enable an increase in the burnup of the MOX assemblies to the level of the UO 2 ones ('MOX Parity' project). But the FRAMATOME fuel development objective does not stop at the obtaining of parity between the current MOX and UO 2 products: this parity must remain guaranteed and the MOX managements must evolve in the same way as the UO 2 managements. The goal of the MOX product development programmes underway with COGEMA and the CEA is the demonstration over the next 10 years of a fuel capable of reaching burnups of 70 GWD/T. The research programmes focus on the fission gas release aspect, with three issues explored: optimization of pellet microstructures and validation in experimental reactor ; build-up of experience feedback from fission gas release at elevated burnups in commercial reactors, both for current and experimental products; adaptation and qualification of the design models and tools, over the ranges and for the products concerned. The product arising from these development programmes should be offered on the market around 2010. While meeting safety requirements, it will cater for the needs of the utilities in terms of product reliability, personnel dosimetry and kWh output costs (increase in burnup, NPP maneuverability and availability, minimization of process waste). (authors)

  20. Report of Activity - 1997

    International Nuclear Information System (INIS)

    Hammer, Philippe

    1999-01-01

    The Report of Activity on 1997 published by Waste Management Division (Direction chargee de la Gestion des Dechets) of French Atomic Energy Authority (Commissariat a l'Energie Atomique) presents the current activity in the framework of CEA Recovery Plan for Civil Centers initiated in 1991, aiming at managing all the radioactive problems issued from its Research and Development Activities. This plan covers three principal directions: management of radioactive wastes resulting from CEA research activities, reprocessing or storing the spent or un-used fuel resulting from research or prototype reactors, recovery measures and dismantling of nuclear facilities. In the field of radioactive waste management important projects, assuring the waste processing equipment, were developed in 1997 at Saclay (STELLA Installation), Cadarache (AGATE Installation) and Marcoule (ATENA Installation). The Radioactive Waste Storage TFA was put into operation at Cadarache. In the field of out-of-use fuel, in 1997 the fuel reprocessing units CARAMEL and UNGG were finished while as temporary storage for fuels waiting to be processed the CASCAD facility at Cadarache was assigned. Finally, concerning the recovery/dismantling activities, priority was granted to recover: the Radiochemical Lab. at Fontenay, the pilot workshop and UP1 plant of COGEMA at Marcoule, the EL4 reactor (in a joint action with EDF), and the AT1 pilot workshop at Cherbourg. The report is structured on five chapters with the following content: 1. The radioactive wastes; 2. The out-of-use fuels; 3. The dismantling of the definitively stopped installations; 4. The waste management at DAM (Direction des Applications Militaires); 5. Recovery activities at Marcoule