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

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.

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

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.)

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

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.)

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

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

Physical measurements in Marcoule reactors (1962); Mesures physiques sur les reacteurs de Marcoule (1962)

Energy Technology Data Exchange (ETDEWEB)

Teste du Bailler, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1962-07-01

A brief description of the physical measurements in Marcoule reactors is given here. During commissioning and subsequent years of operation, various experiments ha been carried out to check design data, and improve the operating conditions and also test theoretical models for kinetic studies. (author) [French] On presente une rapide description des mesures physiques effectuees sur les reacteurs de Marcoule. Au cours du demarrage et pendant les premieres annees de fonctionnement de G-2 - G-3, de nombreuses experiences ont ete effectuees pour verifier les donnees du projet, ameliorer les conditions de fonctionnement et eprouver des modeles theoriques de calculs de cinetique. (auteur)

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)

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

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)

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

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.)

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.)

An economic study of the site of Marcoule

International Nuclear Information System (INIS)

Duprat, H.

1964-01-01

The study of this site of the Marcoule Center shows that its regional economical influence is limited to the buying power distributed among its personnel. This entails distortions between first this supplementary buying power and the overall markets within the possible Marcoule influence zone, and secondly the concentration on Bagnols-sur-Ceze and this town's normal extension possibilities. (author) [fr

A Solution for the Storage of Radioactive Sludge in the Ground at Marcoule; Une Solution de Stockage dans le Sol des Boues Radioactives de Marcoule; 0420 0415 0428 0414 ; Solucion para el Almacenamiento de Lodos Radiactivos en el Suelo de Marcoule

Energy Technology Data Exchange (ETDEWEB)

Cohen, P.; Gailledreau, C. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a L' Energie Atomique, Saclay (France)

1960-07-01

This paper deals with radioactive sludge from the radioactive effluents of the plant at Marcoule. The sludge is stored in drums, and the authors have investigated the hazard created at Marcoule by the seepage of this radioactive sludge through the soil with the gradual deterioration of the drums. This economic solution may be applicable in certain cases. (author) [French] Il s'agit de boues radioactives en provenance de la station des effluents radioactifs de Marcoule: ces boues sont stockees dans des futs, et nous avons etudie le danger presente par la percolation a travers le sol de Marcoule de ces boues radioactives apres degradation progressive du fut. Cette solution economique peut etre applicable dans certains cas. (author) [Spanish] Se trata de los lodos radiactivos procedentes de la estacion de efluentes radiactivos de Marcoule: los lodos se depositan en toneles, y el autor ha estudiado el peligro que ofrece la infiltracion de los lodos radiactivos a traves del suelo de Marcoule a causa del deterioro progresivo del tonel. Esta solucion economica se puede aplicar en determinados casos. (author) [Russian] V dannom doklade rassmatrivajutsja radioaktivnye grjazi, ishodjashhie iz stancii radioaktivnyh zhidkih othodov v Markule. Jeti grjazi zahoronjajutsja v cisternah; v svjazi s jetim izuchalas' opasnost', vyzyvaemaja perkoljaciej cherez pochvu Markulja jetih radioaktivnyh grjazej posle postepennoj porchi cistern. Jeto jekonomicheskoe reshenie mozhet primenjat'sja v otdel'nyh sotuchajah. (author)

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

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.)

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

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)

Physical measurements in Marcoule reactors (1962)

International Nuclear Information System (INIS)

Teste du Bailler, A.

1962-01-01

A brief description of the physical measurements in Marcoule reactors is given here. During commissioning and subsequent years of operation, various experiments ha been carried out to check design data, and improve the operating conditions and also test theoretical models for kinetic studies. (author) [fr

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)

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

Apparatus for examination of irradiated fuel elements of industrial reactors at Marcoule; Appareillage d'examen des elements combustibles des piles industrielles de Marcoule

Energy Technology Data Exchange (ETDEWEB)

Pesenti, P; Wallet, Ph [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

The authors describe a viewing and measurement cell for the slugs of Marcoule industrial reactors. This cell allows visual inspection, and photography of slugs. Length measurements are also made possible by horizontal motion of the slug both in translation and rotation. (author) [French] Les auteurs decrivent une cellule d'observation et de mesure des elements combustibles des piles industrielles de Marcoule. La cellule permet l'examen a vue, la photographie, la radioscopie et la radiographie des elements combustibles. Elle permet en outre la mesure de longueurs sur ces elements, ces derniers pouvant etre deplaces horizontalement en translation, et en rotation. (auteur)

A project for storing the radioactive sludges from Marcoule in the soil (1960); Une solution de stockage dans le sol des boues radioactives de Marcoule (1960)

Energy Technology Data Exchange (ETDEWEB)

Cohen, P; Gailledreau, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

A study of the feasibility of storing radioactive sludges in the soil. Special attention is paid to the case of the Marcoule plant, producing three kinds of sludges. The movement of the different fission products is given. (author) [French] Etude de la possibilite de stocker dans le sol des boues radioactives. Le cas de la station de traitement des effluents de Marcoule, produisant trois types de boues, est etudie plus specialement. Le mouvement des divers produits de fission est precise. (auteur)

A Solution for the Storage of Radioactive Sludge in the Ground at Marcoule

Energy Technology Data Exchange (ETDEWEB)

Cohen, P.; Gailledreau, C. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a L' Energie Atomique, Saclay (France)

1960-07-01

This paper deals with radioactive sludge from the radioactive effluents of the plant at Marcoule. The sludge is stored in drums, and the authors have investigated the hazard created at Marcoule by the seepage of this radioactive sludge through the soil with the gradual deterioration of the drums. This economic solution may be applicable in certain cases. (author)

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)

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

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)

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.)

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.)

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.)

Transparency and nuclear safety. Report 2009. INBs of the Marcoule Centre

International Nuclear Information System (INIS)

2009-01-01

After a general presentation of the Marcoule Centre (missions, dismantling works, activities, Basic Nuclear Installations or INBs for 'installations nucleaires de base'), this report describes the various measures regarding security and radioprotection applied at Marcoule. It reports significant events which occurred in 2009 as far as nuclear security and radioprotection are concerned. It presents results of measurements of liquid and gaseous dismissals and of their impact on the environment. It indicates measures implemented for environmental control and management, and also to limit the volume and impacts on health and environment of radioactive wastes stored in the Centre installations

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

Report transparency and nuclear safety 2007 CEA Marcoule; Rapport transparence et securite nucleaire 2007 CEA Marcoule

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

This report presents the activities of the CEA Center of Marcoule for the year 2007. Since its creation in 1955 the center realizes industrial and scientific activities relative to the civil and military applications of the radioactivity. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the following two base activities are detailed: Atalante and Phenix. (A.L.B.)

Apparatus of irradiation of steel test pieces in the Marcoule pile G 1; Dispositifs d'irradiation d'eprouvettes d'acier dans la pile G 1 de Marcoule

Energy Technology Data Exchange (ETDEWEB)

Marinot, R; Wallet, Ph [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

Test pieces of steel were irradiated in the reactor G1 at Marcoule, in convectors replacing fuel elements, and in vertical channels in furnace-heated containers. The apparatus designed for this irradiation is described: containers, converter-rods, suspension fixtures and clamps, temperature measurement devices, lead castles and unloading set-ups. (author) [French] Des eprouvettes d'acier ont ete irradiees dans le reacteur G1 de Marcoule dans des convertisseurs mis a la place d'elements combustibles, et dans des canaux verticaux, en conteneurs chauffes par four. Nous decrivons l'appareillage etudie pour cette irradiation: conteneurs, barreaux-convertisseurs, dispositifs de suspension et d'amarrage, dispositifs de regulation et de mesure de temperature, chateaux de plomb et montages de defournement. (auteur)

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

Incidence of malignant hemopathies and thyroid carcinomas in infants less than 15 years old around the nuclear site of Marcoule

International Nuclear Information System (INIS)

Bouges, S.; Daures, J.P.; Arthus, J.C.; Vidonne Sartre, O.

1997-01-01

The objective was to determine, for the last ten years (1985-1995), the incidence of malignant blood diseases and thyroid carcinomas for children less than fifteen years old in a periphery of 35 km around the nuclear site of Marcoule. The conclusions are that it does not seem to exist a sur-incidence of these pathologies around Marcoule. But a surveillance register is placed for these carcinomas for the coming years, because of the choices made by the site of Marcoule and the expected developments. (N.C.)

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

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.)

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)

Apparatus of irradiation of steel test pieces in the Marcoule pile G 1; Dispositifs d'irradiation d'eprouvettes d'acier dans la pile G 1 de Marcoule

Energy Technology Data Exchange (ETDEWEB)

Marinot, R.; Wallet, Ph. [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

Test pieces of steel were irradiated in the reactor G1 at Marcoule, in convectors replacing fuel elements, and in vertical channels in furnace-heated containers. The apparatus designed for this irradiation is described: containers, converter-rods, suspension fixtures and clamps, temperature measurement devices, lead castles and unloading set-ups. (author) [French] Des eprouvettes d'acier ont ete irradiees dans le reacteur G1 de Marcoule dans des convertisseurs mis a la place d'elements combustibles, et dans des canaux verticaux, en conteneurs chauffes par four. Nous decrivons l'appareillage etudie pour cette irradiation: conteneurs, barreaux-convertisseurs, dispositifs de suspension et d'amarrage, dispositifs de regulation et de mesure de temperature, chateaux de plomb et montages de defournement. (auteur)

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)

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)

Report transparency and nuclear safety 2007 CEA Marcoule

International Nuclear Information System (INIS)

2007-01-01

This report presents the activities of the CEA Center of Marcoule for the year 2007. Since its creation in 1955 the center realizes industrial and scientific activities relative to the civil and military applications of the radioactivity. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the following two base activities are detailed: Atalante and Phenix. (A.L.B.)

Changes in the processing of heavy α-contaminated equipment at the Marcoule center

International Nuclear Information System (INIS)

Seyfried, P.

1969-01-01

The processing of heavy α-contaminated equipment at the Marcoule Centre has been carried out for a long time by a rather expensive 'manual' method. It has become necessary to reduce these costs by using more automated methods. Two studies which have been carried out have shown that when the amount of waste to be treated is large and is composed mainly of plastic material, it is possible to design economic installations using cooling and shock demolition, conventional compaction leading to rather poor results. For average quantities, a cutting-up reservoir, used also for other purposes, makes it possible to solve these processing problems at Marcoule. The costs involved are much lower than those previously required in the case of so-called 'manual' methods. (author) [fr

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)

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

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

Apparatus for examination of irradiated fuel elements of industrial reactors at Marcoule

International Nuclear Information System (INIS)

Pesenti, P.; Wallet, Ph.

1960-01-01

The authors describe a viewing and measurement cell for the slugs of Marcoule industrial reactors. This cell allows visual inspection, and photography of slugs. Length measurements are also made possible by horizontal motion of the slug both in translation and rotation. (author) [fr

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

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)

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

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.

A project for storing the radioactive sludges from Marcoule in the soil (1960)

International Nuclear Information System (INIS)

Cohen, P.; Gailledreau, C.

1960-01-01

A study of the feasibility of storing radioactive sludges in the soil. Special attention is paid to the case of the Marcoule plant, producing three kinds of sludges. The movement of the different fission products is given. (author) [fr

The Marcoule pilot plant

International Nuclear Information System (INIS)

Faugeras, P.; Calame Longjean, A.; Le Bouhellec, J.; Revol, G.

1986-06-01

The Marcoule spent fuel reprocessing pilot facility was built in 1960-1961 for extended testing of the PUREX process with various types of fuel under conditions similar to those encountered in a production plant. Extensive modification work was undertaken on the facility in 1983 in the scope of the TOR project, designed with the following objectives: - increase the throughput capacity to at least 5 metric tons of PHENIX equivalent fuel per year, - extend equipment and process R and D capability, - improve job safety by maximum use of remote handling facilities, - maximize waste conditioning treatments to produce waste forms suitable for direct storage, - provide a true industrial process demonstration in continuous operation under centralized control using computerized procedures. The redesigned plant is scheduled to begin operation during the second half of 1986. The proximity of the Industrial Prototypes Service and the ATALANTE radiochemical research laboratory scheduled to begin operation in 1990, will provide a synergistic environment in which R and D program may be carried out under exceptional conditions

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)

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

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.)

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

When Marcoule's radiation protection department was talking nuclear energy with comics.

International Nuclear Information System (INIS)

Portelli, Aurelien; Guarnieri, Franck; Parizel, Claire

2015-01-01

The radiation protection department (SPR) of the CEA Marcoule centre implemented in the beginning of the 1960's an information program aiming at counteracting the false ideas circulating about nuclear industry. The centre benefited from the artistic skill of Jacques Castan who made posters and comics to illustrate the safety campaigns of the SPR. This article analyses the methods used by Castan to promote nuclear industry to the general public

Apparatus of irradiation of steel test pieces in the Marcoule pile G 1

International Nuclear Information System (INIS)

Marinot, R.; Wallet, Ph.

1960-01-01

Test pieces of steel were irradiated in the reactor G1 at Marcoule, in convectors replacing fuel elements, and in vertical channels in furnace-heated containers. The apparatus designed for this irradiation is described: containers, converter-rods, suspension fixtures and clamps, temperature measurement devices, lead castles and unloading set-ups. (author) [fr

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)

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)

Dismantling of an alpha contaminated hot cell at the Marcoule Pilot Plant

International Nuclear Information System (INIS)

Tachon, M.

1988-01-01

For the remodeling of Marcoule Pilot Plant, the cell 82: old unit for plutonium solution purification by extraction, was dismantled. About 42 tons of wastes were evacuated. Some wastes wen decontaminated by mechanical means other wastes with higher residual activity were stored for subsequent processing. The operation shows that dismantling of a hot cell is possible even if incorporated in an operating plant [fr

Nuclab Marcoule: a dedicated waste management and dismantling support laboratory

International Nuclear Information System (INIS)

Dugne, Olivier; Bec-Espitalier, Lionel; Rosen, Jeremy

2014-01-01

Formerly dedicated to plutonium production support, NucLab was renovated to perform a wide range of analyses for dismantling, plant operation and process development activities mainly at Marcoule but also for external clients. The laboratory is a CEA entity in the Nuclear Energy Division. It provides services to several industrial operators (nuclear processes and power plants) in the fields of analytical chemistry, radioactivity measurements, in situ nuclear measurements, decontamination processes, industrial chemistry processes, and waste treatment. NucLab supports research, production, and dismantling activities in all areas of dismantling operations (authors)

Dissolution off-gases at the marcoule pilot facility: Iodine trapping and off-gas characterization unit

International Nuclear Information System (INIS)

Pouyat, D.; Vignau, B.; Roux, J.P.

1993-01-01

The Marcoule Pilot Reprocessing Facility (APM) reprocesses spent fuel from light water reactors and fast breeder reactors. A batch dissolution process is used with an annual throughput capacity of 5 metric tons. The off-gas treatment unit is described together with its characterization laboratory in order to highlight the functions and potential of the facilities. The objectives are consistent with the Marcoule site policy regarding diminished iodine release and investigation of the off-gas treatment process. The equipment used to meet these objectives is described from a functional standpoint. The facility implements measurement techniques to allow continuous quantitative measurements of nitrogen oxides, oxygen, iodine and krypton, as well as continuous monitoring of the demister inlet flow by γ spectrometry. Sorbents used for iodine trapping may be tested over a wide range of operating conditions (temperature, flow rate, iodine concentration) with representative dissolution off-gases. An X-ray and γ counting system is used to assess the activity of the adsorbed radionuclides, notably 129 I

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

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.

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)

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.)

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)

Screening level dose assessment of aquatic biota downstream of the Marcoule nuclear complex in southern France.

Science.gov (United States)

St-Pierre, S; Chambers, D B; Lowe, L M; Bontoux, J G

1999-09-01

Aquatic biota in the Rhone River downstream of the Marcoule nuclear complex in France are exposed to natural sources of radiation and to radioactivity released from the Marcoule complex. A simple conservative screening level model was used to estimate the range of concentrations in aquatic media (water, sediments, and aquatic organisms) of both artificial and natural radionuclides and the consequent absorbed (whole body) dose rates for aquatic organisms. Five categories of aquatic organisms were studied, namely, submerged aquatic plants (phanerogam), non-bottom-feeding fish, bottom-feeding fish, mollusca, and fish-eating birds. The analysis was based on the radionuclide concentrations reported in four consecutive annual radioecological monitoring reports published by French agencies with nuclear regulatory responsibilities. The results of this assessment were used to determine, qualitatively, the magnitude of any potential health impacts on each of the five categories of aquatic organisms studied. The range of dose rate estimates ranged over three orders of magnitude, with maximum dose rates estimated to be in the order of 1 to 10 microGy h(-1). These maximum dose rates are a factor 40 or more below the international guideline intended to ensure the protection of aquatic populations (about 400 microGy h(-1)), and a factor ten or more below the level which may trigger the need for a more detailed evaluation of potential ecological consequences to the exposed populations (about 100 microGy h(-1)). As a result, chronic levels of radioactivity, artificial and natural, measured in aquatic media downstream of Marcoule are unlikely to result in adverse health impacts on the categories and species of aquatic organisms studied. Thus, based on the screening level analysis discussed in this paper, a more detailed evaluation of the dose rates does not appear to be warranted.

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)

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

NucLab Marcoule. A laboratory facility dedicated to support dismantling operations

International Nuclear Information System (INIS)

Dugne, O.; Houssin, A.; Pierre, D.; Bec-Espitalier, L.

2013-06-01

Formerly dedicated to plutonium production support, NucLab was renovated to perform a wide range of analyses for dismantling, plant operation and process development activities mainly on Marcoule site but also outside (Veurey, Fontenay aux Roses). The Laboratory is under a CEA AREVA partnership as a CEA entity operated by AREVA employees. It provides services to several industrial operators (nuclear process and power plant) in the fields of analytical chemistry, radioactivity measurements, in situ nuclear measurements, decontamination processes and industrial chemistry processes, waste treatments to meet the following analysis requirements. NucLab today is able to support research, production and dismantling activities in all part of dismantling operations. (authors)

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)

Decommissioning, Dismantling and Disarming: a Unique Information Showroom Inside the G2 Reactor at Marcoule Centre (France) - 12068

Energy Technology Data Exchange (ETDEWEB)

Volant, Emmanuelle [CEA DAM, Bruyeres-le-Chatel (France); Garnier, Cedric [CEA DEN, Marcoule (France)

2012-07-01

The paper aims at presenting the new information showroom called 'Escom G2' (for 'Espace Communication') inaugurated by the French Atomic Energy and Alternative Energies Commission (CEA) in spring 2011. This showroom is settled directly inside the main building of the G2 nuclear reactor: a facility formerly dedicated to weapon-grade plutonium production since the late 1950's at the Marcoule nuclear centre, in south of France. After its shutdown, and reprocessing of the last spent fuels, a first dismantling step was successfully completed from 1986 to 1996. Unique in France and in Europe, Escom G2 is focused on France dismantling expertise and its action for disarmament. This showroom comprises of a 300-square meters permanent exhibition, organized around four themes: France strategy for disarmament, decommissioning and dismantling technical aspects, uranium and plutonium production cycles. Each of these topics is illustrated with posters, photos, models and technical pieces from the dismantled plants. It is now used to present France's action in disarmament to highly ranked audiences such as: state representatives, diplomats, journalists... The paper explains the background story of this original project. As a matter of fact, in 1996 France was the first nuclear state to decide to shut down and dismantle its fissile material production facilities for nuclear weapons. First, the paper presents the history of the G2 reactor in the early ages of Marcoule site, its operating highlights as well as its main dismantling operations, are presented. In Marcoule, where the three industrial-scale reactors G1, G2 and G3 used to be operated for plutonium production (to be then reprocessed in the nearby UP1 plant), the initial dismantling phase has now been completed (in 1980's for G1 and in 1996 for G2 and G3). The second phase, aimed at completely dismantling these three reactors, will restart in 2020, and is directly linked to the opening of

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

Marcoule pilot work-room: process automatic operation

International Nuclear Information System (INIS)

Mus, G.; Linger, C.

1987-01-01

Commissioned in the early 1960s, the Marcoule Pilot Plant has undergone a series of sweeping transformations. The Research and Development resources concerning irradiated fuel processing have been expanded and modified. Its reprocessing capacity has also been raised from 2 to 5 t/year. Simultaneously, the installation control system was completely remodelled. The control consoles, which were previously positioned locally near the different units, have been grouped together in a centralized control room. To do this, the measurement and operating circuits were replaced by new data acquisition and processing systems requiring the use of numerical algorithms. The management and control of certain units, including mechanical fuel preparation, sampling, and sample transport to the laboratories, have been entrusted to programmable automata. Certain unit operations, such as concentration by evaporation, are set up with complete automation. These new arrangements will expand the resources for analysing the operation of the Pilot Plant, while offering a more overall view of the operations. They have been made possible by a major effort in the development of sensors, and represent the indispensable prerequisite for the installation of expert systems [fr

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)

The functioning of the reactors G2-G3 at Marcoule and E.D.F. 1; Experience de fonctionnement des reacteurs G2-G3 de Marcoule et enseignements des essais de demarrage du reacteur E.D.F. 1 de Chinon

Energy Technology Data Exchange (ETDEWEB)

Boussard, R; Conte, F [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Stolz, J M [Electricite de France (EDF), 75 - Paris (France)

1964-07-01

After resuming briefly the characteristics of the installations G2-G3 at Marcoule and EDF 1 at Chinon, the authors review the main aspects of the tests, the starting and the exploitation of these reactors. Among the various points examined, particular emphasis is given to the devices of original nature such as tubular fuel elements, flattening of the neutron flux by stuffing, behaviour of the reactor tanks and the cooling circuits, the blowers, unloading devices, regulation and functioning of the informations. This analysis deals equally with the performances obtained and the difficulties and the various incidents experienced during the initial starting period. Among the more interesting results, the progressive increase in the power of the Marcoule reactors is mentioned, obtained through a better knowledge of the parameters covering the functioning of the reactors such as the distribution of the flux and the temperatures etc... acquired during the course of the exploitation of the reactor. The conclusion reached by the authors is that the experience gained on these installations has shown: - that during an initial period, adjustments became necessary, all of which turned out to be possible, - that an analysis of their functioning has permitted the progressive movement towards a truly industrial exploitation. (authors) [French] Les auteurs, apres un bref rappel des caracteristiques des installations G2 - G3 de MARCOULE et E.D.F. 1 de CHINON, passent en revue les principaux aspects des essais, de la mise en service et de l'exploitation de ces centrales. Parmi les divers points examines, une attention speciale est accordee aux dispositifs presentant un caractere original tels que elements combustibles tubulaires, aplatissement du flux neutronique par gavage, comportement des caissons des reacteurs et des circuits de refroidissement, soufflantes, appareils de dechargement, regulation et fonctionnement des informations. L'analyse presentee porte tant sur les

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

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)

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)

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)

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)

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)

Some analytical methods used by the Marcoule Centre for the control of radioactive effluents; Quelques methodes analytiques, utilisees sur le centre de Marcoule pour le controle radioactif des effluents

Energy Technology Data Exchange (ETDEWEB)

Scheidhauer, J.; Messainguiral, L.; Drogue, N.; Meiranesio, A. M.

1962-07-09

After three years of operation, the authors propose a review of the various methods used to determine the radioactivity of wastewaters released by the Marcoule Centre Laboratory. They describe the three main steps of this control: firstly, measurements of the global alpha radioactivity and beta radioactivity (principle and measurement method), secondly, dosing of strontium 89 and strontium 90 (principle, used reactants, operation mode for nitric compound precipitation, ferric decontamination, separation of barium 140, oxalic precipitation, precipitate counting, exploitation of counting results), and thirdly, the possible dosing of other fission products present in the effluents: cerium 144, plutonium (by two different methods), natural uranium, caesium 137, zirconium 95, niobium 95, ruthenium 103 and 106, iodine 131. The principle, reactants, operational mode with different precipitations, measurement devices are indicated for each of these radio-elements.

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)

Report on nuclear safety and transparency 2011 - NBI operated by the CEA in Marcoule

International Nuclear Information System (INIS)

2012-06-01

After a brief presentation of the Marcoule CEA centre, this report indicates the different safety measures related to different risks, to emergency situations, to inspections and audits, and to nuclear base installations (INB). It describes measures related to radiation protection and some remarkable facts which occurred in 2010. It presents the different significant events which occurred in 2011 and were declared to the ASN. It discusses the results of measurements of releases from the installations and their impact on the environment. It addresses the radioactive wastes which are warehoused on the site (measures to limit their volume and to limit their impact on health and on the environment, notably on water and soils)

Decontamination of material in the Marcoule plutonium producing centre (1961); La decontamination du materiel dans le centre de production du plutonium de Marcoule (1961)

Energy Technology Data Exchange (ETDEWEB)

Rodier, J; Bouzigues, H; Boutot, P [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1961-07-01

The decontamination of material in an atomic centre is an essential operation in view of the cost and the difficulties of replacement. It also makes it possible to reduce the storage of radio-active materials always an expensive task. Surfaces are contaminated by retention of radioactive products and the mechanism of the bounding forces can be explained in terms of chemical, mechanical, electrostatic and surface tension phenomena. The methods used for decontamination are either physical (section, abrasion, steam, ultrasonics) or chemical (acids, alkalis, detergents, reducing and oxidising agents). At Marcoule, chemical methods of treatment are used. This is effected in tanks, the exact composition of the liquids being regulated from a control panel. Working experience has shown that the fact of operating in humid conditions eliminates all problems of atmospheric contamination; as a result it is possible for the personnel to work without any special protective devices. Almost all the material can be re-utilized and the operations produce only a small volume of liquid waste. The decontamination workshop is operated by a small number of workers. The working costs, including capital repayment and treatment of the waste, do not exceed 15 per cent of the value of the apparatus treated. (authors) [French] La decontamination du materiel dans un centre atomique est une operation indispensable etant donne le cout et les difficultes du remplacement. Elle contribue aussi a diminuer les stockages toujours onereux des materiaux radioactifs. Les surfaces se contaminent par retention de corps radioactifs, l'origine des forces de liaison devant etre recherchee dans les phenomenes chimiques, mecaniques, electro-statiques ou de tensions superficielles. Les methodes de decontamination peuvent etre physiques (aspiration, abrasion, vapeur, ultra-sons) ou chimiques (acides, alcalins, detergents, reducteurs, oxydants). Sur le centre de Marcoule, la methode des traitements chimiques a ete

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)

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

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

Additional safety assessment of common means or support of the Marcoule centre

International Nuclear Information System (INIS)

2012-01-01

This report first presents some characteristics of the Marcoule centre: location and environment, base nuclear installations and other installations, technical installations and installations classified for protection of the environment which could affect the safety of nearby installations, demographic and industrial environment and risks generated for the site's installations, general description of crisis management means. The second part addresses situations to be considered, functional needs related to additional safety assessments, needs in terms of support functions, and critical structures and equipment. The next parts address the seismic risk (structure and equipment sizing, margin assessment, flooding due to an earthquake, loss of electric supply due to an earthquake), the flooding risk (flooding sources, main alarm measures, structure and equipment sizing and availability for crisis management during a flooding from different origins), other extreme phenomena (lightning, hail, wind, external fire), the loss of electric supplies and the loss of cooling systems, the organisation of accident management, and subcontracting practices

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

Complex fluids, divided solids and their interfaces: Open scientific questions addressed at the Institute of Separation Chemistry of Marcoule for a sustainable nuclear energy

International Nuclear Information System (INIS)

Leroy, M.; Henge-Napoli, M.H.; Zemb, Th.

2007-01-01

Key issues in radiochemistry, physical chemistry of separation and chemistry of materials needed for a sustainable nuclear energy production are described. These driving questions are at the origin of the creation of the Institute of Separation Chemistry at Marcoule. Each of the domains has been described extensively in recent reports for science and technology of the French academy of Science. (authors)

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

Operating experience of centrifugal contactors used in a third plutonium purification cycle at the Marcoule reprocessing plant

International Nuclear Information System (INIS)

Coste, J.A.; Breschet, C.A.; Delafontaine, G.L.

1991-01-01

Multistage centrifugal contactors of the type SGN-ROBATEL LX 208 NSC are used in a third plutonium cycle at the Marcoule Reprocessing Plant, they have been smooth-running since the commissioning in 1984. The four centrifugal contactors, totalling 32 stages, are used for Extraction. Scrub and Acidic Strip, and a bank of three flat mixer-settlers is used for plutonium blocking, and soda washing of the solvent. The plutonium product, the residual activity of which is less than one microcurie per gram, is diluent washed in a bank of three flat mixer-settlers, before been concentrated in a zirconium evaporator to 200 g. 1 -1

Decontamination of material in the Marcoule plutonium producing centre (1961)

International Nuclear Information System (INIS)

Rodier, J.; Bouzigues, H.; Boutot, P.

1961-01-01

The decontamination of material in an atomic centre is an essential operation in view of the cost and the difficulties of replacement. It also makes it possible to reduce the storage of radio-active materials always an expensive task. Surfaces are contaminated by retention of radioactive products and the mechanism of the bounding forces can be explained in terms of chemical, mechanical, electrostatic and surface tension phenomena. The methods used for decontamination are either physical (section, abrasion, steam, ultrasonics) or chemical (acids, alkalis, detergents, reducing and oxidising agents). At Marcoule, chemical methods of treatment are used. This is effected in tanks, the exact composition of the liquids being regulated from a control panel. Working experience has shown that the fact of operating in humid conditions eliminates all problems of atmospheric contamination; as a result it is possible for the personnel to work without any special protective devices. Almost all the material can be re-utilized and the operations produce only a small volume of liquid waste. The decontamination workshop is operated by a small number of workers. The working costs, including capital repayment and treatment of the waste, do not exceed 15 per cent of the value of the apparatus treated. (authors) [fr

Return on experience by the Marcoule-Gard CLI in the management of a post-accident situation following a nuclear or radiological event; Retour d'experience de la CLI Marcoule-Gard dans la gestion d'une situation post-accidentelle, faisant suite a un evenement nucleaire ou radiologique

Energy Technology Data Exchange (ETDEWEB)

Charre, J.P. [Vice-President de la CLI Marcoule-Gard et Maire d' Orsan, Mairie - 30200 Orsan (France)

2010-07-01

After having recalled the legal framework which strengthens the roles and responsibilities of local authorities with respect to natural or technological risks, this short report describes the activity of the Marcoule-Gard CLI (Commission locale d'information, information local commission) in the management of a post-accident situation during a nuclear crisis. This commission notably participates to several work groups, and to some exercises (two examples - a simulated crisis and a real one - are briefly reported and analyzed)

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

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

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.)

Return on experience by the Marcoule-Gard CLI in the management of a post-accident situation following a nuclear or radiological event

International Nuclear Information System (INIS)

Charre, J.P.

2010-01-01

After having recalled the legal framework which strengthens the roles and responsibilities of local authorities with respect to natural or technological risks, this short report describes the activity of the Marcoule-Gard CLI (Commission locale d'information, information local commission) in the management of a post-accident situation during a nuclear crisis. This commission notably participates to several work groups, and to some exercises (two examples - a simulated crisis and a real one - are briefly reported and analyzed)

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

Marcoule and the tritium. Information by the CRIIRAD after the article published in 'La Provence' of September 6, 2008 and entitled: 'Gard: for an environmentalist militant, the outer Marcoule's ground water is polluted'. CRIIRAD Note N.08-159 October 2008

International Nuclear Information System (INIS)

2009-01-01

This document recalls that nuclear installations are allowed to release some quantities of radioactive pollutants in the atmosphere and in surface waters. It also notes that the allowed level for radioactive tritium by the Marcoule nuclear site is much higher than that of nuclear power plants. It recalls and comments the results of investigations performed by the CRIIRAD which revealed the pollution of ground waters and of the whole food chain. It also notes that, even though theses release became less important, their level remained rather high, still higher than that of nuclear plants: exceeding levels of tritium have been detected in rain waters, ground waters, fruits and vegetables, and other farm productions

Report on transparency and nuclear safety - 2013. Nuclear facilities exploited by CEA Marcoule

International Nuclear Information System (INIS)

2014-01-01

This report presents the different basic nuclear installations (INB) of the Marcoule CEA centre, gives an overview of measures regarding safety within these installations (organisation, general arrangements, arrangements related to different risks, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings) and of measures related to radiation protection (organisation and results, main events). It reports the significant events related to safety and radiation protection which occurred in 2013 and were declared to the ASN, and discusses how the return-on-experience has been used. It reports and comments the results of measurements of gaseous and liquid effluents, of their impact on the environment, and of surveys of the environment. It also presents the environmental management approach. The next part addresses the management of radioactive wastes which are warehoused on this site: arrangements aimed at limiting their volume, and at limiting their impact on health and on the environment, nature and quantities of warehoused wastes. Remarks and recommendations of the CHSCT are given

Report on transparency and nuclear safety - 2015. Nuclear facilities exploited by CEA Marcoule

International Nuclear Information System (INIS)

Guiberteau, Philippe

2016-01-01

This report presents the different basic nuclear installations (INB) of the Marcoule CEA centre, gives an overview of measures regarding safety within these installations (organisation, general arrangements, arrangements related to different risks, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings) and of measures related to radiation protection (organisation and results, main events). It reports the significant events related to safety and radiation protection which occurred in 2015 and which were declared to the nuclear safety authority (ASN), and discusses how experience feedback has been used. It reports and comments the results of measurements of gaseous and liquid effluents, of their impact on the environment, and of surveys of the environment. It also presents the environmental management approach. The next part addresses the management of radioactive wastes which are warehoused on this site: arrangements aimed at limiting their volume, and at limiting their impact on health and on the environment, nature and quantities of warehoused wastes. Remarks and recommendations of the health, safety and work conditions committee (CHSCT) are given

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.)

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

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

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.

Maintenance of a high activity level reprocessing cell in the Marcoule pilot plant by mean of a Ma23 electronic telemanipulator

International Nuclear Information System (INIS)

Guay, P.; Roux, J.P.; Streiff, G.; Hancok, H.

1990-01-01

The Marcoule Pilot Facility (APM) is used to test reprocessing methods and equipment under actual operating conditions with spent fuel at semi-industrial throughput rates and during demonstration runs of significant duration. In addition to the general objective of continuous long-term operation, the facility is also used for radioactive testing and qualification of specific process equipment items for planned or future reprocessing plants. This pilot function covers not only process operations but also other areas including remote manipulation. A remote manipulation system using an MA23 M electronic telemanipulator will be submitted to qualification testing in this way under actual operating conditions exposed to high irradiation levels together with numerous mechanical devices

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.)

Marcoule institute for separation chemistry - ICSM. Scientific report 2007 - 2010

International Nuclear Information System (INIS)

2010-01-01

The mixed research unit 'Institute for Separation Chemistry' was created jointly by CEA, CNRS, University of Montpellier and Ecole Nationale superieure de Chimie de Montpellier has obtained authorisation to start experiments including a few grams of depleted uranium and natural thorium in January 2010. Last takeoff was from our theory group, who started in October 2009. But the unit 'Institut de Chimie separative de Marcoule' existed as a team scattered in several places in France since 2007. At that time, monthly meetings gathered people for full days of open discussion every month, as 'Point ICSM', where colleagues from R/D Departments of the centre of Marcoule composed half of the audience. Scientific activity began in 2007 with progressive joining of ICSM of team leaders, co-workers, technicians and students, today with 38 permanent staff and 29 nonpermanent scientists and students. Most of the staff joined ICSM after or before participating to the European practical summer school in Analytical and separation chemistry, hold yearly for a full week including practical sessions since the first edition 2006 in Montpellier. Resources in Uranium are scarce, if only the 235 isotope is used. Wastes related to nuclear energy production are potentially dangerous. Since fifty years, the chemistry associated to nuclear energy production always followed the principles of green chemistry. Permanent attention in devoted to closing the life-cycle of materials and fuel, minimize wastes and ascertain the acceptability by a society via knowledge of chemistry and physical chemistry involved in the chemistry used for separation. Developing knowledge in order to propose new separation processes is the central aim of the ICSM. Enlarging this central goal to surfaces of materials, sono-chemistry as an example of green chemistry, chemistry and physical chemistry specific to actinides complete this picture. Thus, the ICSM is devoted to chemistry at the service of the nuclear energy of

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)

A Study Of The Dilution Of Radio-Active Waste In The Rhone (1961); Etude de la dilution dans le rhone des effluents radioactifs du Centre de Marcoule (1961)

Energy Technology Data Exchange (ETDEWEB)

Rodier, J; Scheidhauer, J; Marichal, M; Court, R [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1961-07-01

The discharge into the Rhone of liquid radio-active waste from the Marcoule Centre necessitates a large number of measurements, in particular chemical and radio-chemical analysis of the waste, itself and of the waters of the Rhone both above arid below the point of discharge. The results thus obtained during 1960 made it possible to evaluate the total amount of active waste discharged and its dilution in the receiving medium. A statistical study of the results of the analysis of the Rhone waters shows that a satisfactory dilution of the waste occurs rapidly; the experimental results obtained with an experimental discharge of rhodamine are thus confirmed. (authors) [French] Le rejet au Rhone des effluents radioactifs liquides produits sur le Centre de Marcoule donne lieu a un grand nombre de mesures et en particulier d'analyses chimiques et radio-chimiques des effluents eux-memes ainsi que des eaux du Rhone avant et apres rejet. Au cours de l'annee 1960, l'ensemble des resultats ainsi obtenus a permis de dresser un bilan des activites rejetees et de leur dispersion dans le milieu recepteur. Une etude statistique des resultats d'analyses des eaux du Rhone montre qu'une dilution satisfaisante des effluents s'effectue rapidement confirmant ainsi les resultats obtenus lors d'un rejet experimental de rhodamine. (auteurs)

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)

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)

Six years working experience of the Marcoule plant for treatment of irradiated fuel; Experience de 6 annees de fonctionnement de l'usine de retraitement de Marcoule

Energy Technology Data Exchange (ETDEWEB)

Jouannaud, C [CEA Marcoule, Centre de Production de Plutonium, 30 (France)

1964-07-01

The irradiated fuel treatment plant at Marcoule began treating rods from the pile G 1 in July 1958. These six years experience of the plant in operation have led to the confirmation or revision of the original ideas concerning the process as well as the technology or methods of exploitation. The process as a whole has suffered little modification, the performances having proved better than originally foreseen; the only alterations made were justified by greater simplicity of operation, better nuclear security (criticality) or for technological reasons. The processes of plutonium reduction from valency IV to valency III by uranium IV, and of concentration of fission product solutions in the presence of formaldehyde, have always given complete satisfaction. The initial concept of direct maintenance of the installations has been justified by experience. Certain maintenance jobs, originally considered impossible after the start of operations, have proved feasible and have been carried out under acceptable conditions; a number of examples are given. From experience it has been possible to define optimal conditions for the design of these installations such as to provide a maximum in robustness and ease of maintenance. The advantages of continuously-operating equipment have been shown. Certain installations have been altered in accordance with these new ideas. Analytical checking in the laboratory has been profoundly modified, and the plans adopted are such that complete safety in work on radioactive solutions is compatible with a very good working speed. Experience has also shown the advantages of having a group on the spot to carry out short-term applied studies. Finally, a strict working discipline and excellent collaboration with the radiation protection service have enabled us to reach the end of these six years, during some of which the exploitation was intensive, without irradiation accident. (authors) [French] L'usine de traitement des combustibles irradies de

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)

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

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.)

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

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

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.)

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.)

Incidence of leukemia, lymphoma and thyroid cancers in children under 15 years old in the vicinity of Marcoule nuclear plant, 1985-95

International Nuclear Information System (INIS)

Bouges, S.; Daures, J.P.; Hebrard, M.

1999-01-01

The aim of this investigation was to report incidence of childhood leukemia, lymphoma and thyroid neoplasms in children under 15 years of age living in the vicinity of the French Marcoule nuclear reprocessing plant. This exhaustive and retrospective survey was carried out between 1985 and 1995 in children aged under 14 at the time of diagnosis and living inside a 35 kilometer zone around the nuclear site. 656 practitioners, 109 medical analysis laboratories and 5 hospitals or cancer institutes were investigated. A panel of experts checked each case. 48 cases of acute leukemia (39 acute lymphoid leukemia and 9 acute myeloid leukemia), 15 cases of lymphoma (8 Hodgkin lymphomas - 53 % - and 7 non hodgkinian lymphomas including 5 Burkitt lymphomas), 1 case of chronic myeloid leukemia and 1 case of papillary thyroid cancer, appeared among the 1,116,442 children-years followed. The total incidences of leukemias and lymphomas were respectively 4.12 and 1.29.10 -5 . Standardised Incidence Ratios, calculated according to Poisson methods and Bayesian inference, with various reference rates did not show any excess of risk: 100.67 (95 % confidence interval 72-131) for leukemia. Children under 5 years old and living in non exposed areas to dominant winds or downstream Rhodanian water drawing presented a 3 or 4 fold decreased risk of leukemia than others (the latter still having an identical risk to that of the general population). This was not true for lymphomas, nor for the other age groups. Over the entire zone, children do not have an increased risk of malignant hematology disease but health monitoring by a systematic collection of cases remains useful around Marcoule. The assumption of aquiferous or air contamination thus still remains questionable: further studies investigating models of contamination are needed to take into account all other nonionizing leukemogenic factors (benzene and viral infection in particular) or correlation studies between health indicators and

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

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

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.)

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)

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)

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)

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)

Six years working experience of the Marcoule plant for treatment of irradiated fuel

International Nuclear Information System (INIS)

Jouannaud, C.

1964-01-01

The irradiated fuel treatment plant at Marcoule began treating rods from the pile G 1 in July 1958. These six years experience of the plant in operation have led to the confirmation or revision of the original ideas concerning the process as well as the technology or methods of exploitation. The process as a whole has suffered little modification, the performances having proved better than originally foreseen; the only alterations made were justified by greater simplicity of operation, better nuclear security (criticality) or for technological reasons. The processes of plutonium reduction from valency IV to valency III by uranium IV, and of concentration of fission product solutions in the presence of formaldehyde, have always given complete satisfaction. The initial concept of direct maintenance of the installations has been justified by experience. Certain maintenance jobs, originally considered impossible after the start of operations, have proved feasible and have been carried out under acceptable conditions; a number of examples are given. From experience it has been possible to define optimal conditions for the design of these installations such as to provide a maximum in robustness and ease of maintenance. The advantages of continuously-operating equipment have been shown. Certain installations have been altered in accordance with these new ideas. Analytical checking in the laboratory has been profoundly modified, and the plans adopted are such that complete safety in work on radioactive solutions is compatible with a very good working speed. Experience has also shown the advantages of having a group on the spot to carry out short-term applied studies. Finally, a strict working discipline and excellent collaboration with the radiation protection service have enabled us to reach the end of these six years, during some of which the exploitation was intensive, without irradiation accident. (authors) [fr

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)

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)

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

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

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.

''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)

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.)

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.)

Annex I.G. Demolition of the G1 stack at Marcoule by toppling

International Nuclear Information System (INIS)

2005-01-01

The G1 stack at Marcoule was constructed during the first half of 1956 as a ventilation outlet for the G1 reactor, which is cooled by air. After the G1 reactor was decommissioned, the G1 stack served as a ventilation outlet for two new nuclear facilities on the site. Being no longer in compliance with regulations and having many inadequacies and uncertainties in terms of the prestressed concrete, the stack posed a potential damage risk in extreme wind or in the event of an earthquake. In 1994 it was decided that a new stack would be built to act as an outlet for the existing nuclear facilities, and that the old one would be demolished. The G1 stack was 100 m in height, 10 m in diameter and constructed with 24 vertically stacked concrete rings consisting of nine prefabricated sections, each 3.6 m in height. It was capped by a metal deflector (about 6 m in height and weighing 50 t). The inside consisted of nine semicircular tubes constructed of steel sheet metal weighing 120 t. The base of the stack consisted of the foundation, a plate and a base plate which were constructed at the site. The barrel sections were prefabricated. Construction lasted from January 1956 to June 1956. At the base, the cylindrical portion of the stack widened to form three feet extending to a depth of 7.5 m. The base plate of the stack was formed onsite to the height of 16.7 m and then prestressed using cables. A repair carried out in 1964 included adding a concrete lining of the initial rings of the cylinder up to a level of 22.1 m. Additional prestressing with the base plate and repair of the horizontal and vertical prestressing of the barrel were also carried out, leaving only 22 rings and 43 visible cables. The total mass of the stack was 2170 t, including: - Concrete: cylinder 800 t, base plate 1200 t; - Steel: internal structures 120 t, deflector 50 t. The main radiological risk was the presence of traces of tritium. The radioactive inventory for the entire stack was estimated in 2000

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

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)

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)

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.

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

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)

Feedback from the operation of the ISOCS in support to the plutonium facility decommissioning project at the Marcoule UP1 reprocessing plant (France) and possible gain for new projects with new CANBERRA systems

International Nuclear Information System (INIS)

Dogny, S.; Toubon, H.

2009-01-01

After the decision was taken in 1998 to shut-down the operations of the UP1 reprocessing plant in Marcoule (France), where more than 19,000 metric tons of spent nuclear fuel have been reprocessed, decommissioning projects started in the various buildings, particularly in the Plutonium Facility. In this facility many glove boxes had to be decontaminated before dismantling. To have waste compatible with surface storage, the main objective was to prove that each glove box had on hold up of less than 37 GBq (about 10 g) and to determine the corresponding Pu isotopic composition. Historically the method used for such characterisation was based on smears and dose rate measurements to extrapolate the mass of Pu in the glove boxes with a very high uncertainty. In 1998 AREVA-NC decided to deploy new characterization tools to meet the performance goals of the Plutonium Facility Decommissioning Project. These tools consist on portable Germanium gamma spectrometer coupled with MGA Pu isotopic composition and ISOCS 3D modelling codes. (authors)

Review of safety precautions derived from six-year experience of a spent fuel reprocessing plant - Centre de Marcoule; Elements de securite tires de six annees d'exploitation de l'usine de traitement de combustibles irradies du Centre de Marcoule

Energy Technology Data Exchange (ETDEWEB)

Rodier, J [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1964-07-01

In a center for the processing of irradiated fuels, as in any other factory, continuity of production can only be achieved through constant effort to maintain the standard of safety. The authors examine the safety elements inherent in the design of the installations, from the point of view of both radioactive and conventional protection. It is clear that in the nuclear industry it is not sufficient merely to adopt the usual precautions against the risks of explosion, fire, etc...; but great attention must be paid to the problems arising from the confinement of materials, radioactivity and the risks of criticality. The general principles of the technical prevention of radioactive risks are now well known. They must be applied as soon as the plans are drawn up for the installations, by taking into account : - the design and construction of the installations with respect to the risks mentioned above - the division of the plant into zones - the circulation of personnel and material - ventilation and purification of the air. The technical safety factors however, are not sufficient in themselves. However good the material and the degree of automation achieved, the smooth running of a factory depends on the man responsible for supervision and repair work or who takes initiatives. Technical safety is never definitive and must be continually maintained. The collaboration of the workers is necessary to its efficiency. Psychological measures must thus be taken as an addition to the technical precautions. This psychological prevention is based on: - education of the personnel - organization of the work and definition of the safety rules - checking on obedience to the rules and behaviour of the personnel - constant reminders of the necessity for the prevention of radioactive risks. Six years operation of the irradiated fuel processing plant at Marcoule have shown the importance of close collaboration between workers and technique. The authors analyse the results obtained from

The dismantling of nuclear installations: The dismantling of nuclear installations at the CEA's Directorate for nuclear energy; The CEA's sanitation and dismantling works: example of one of the Marcoule UP1 program lots; Research and innovation in sanitation-dismantling; Global optimisation of the management of dismantling radioactive wastes

International Nuclear Information System (INIS)

Hauet, Jean-Pierre; Piketty, Laurence; Moitrier, Cyril; Blanchard, Samuel; Soulabaille, Yves; Georges, Christine; Dutzer, Michel; Legee, Frederic

2016-01-01

This publication proposes a set of four articles which addresses issues related to the dismantling of nuclear installations in France, notably for the different involved actors such as the CEA and the ANDRA. The authors more particularly address the issue and the general strategy of dismantling within the Directorate for nuclear energy of the CEA; comment the example of one of the Marcoule UP1 program lots to highlight sanitation and dismantling works performed by the CEA; discuss current research and innovation activities within the CEA regarding sanitation and dismantling; and comment how to globally optimise the management of radioactive wastes produced by dismantling activities

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)

Review of safety precautions derived from six-year experience of a spent fuel reprocessing plant - Centre de Marcoule

International Nuclear Information System (INIS)

Rodier, J.

1964-01-01

In a center for the processing of irradiated fuels, as in any other factory, continuity of production can only be achieved through constant effort to maintain the standard of safety. The authors examine the safety elements inherent in the design of the installations, from the point of view of both radioactive and conventional protection. It is clear that in the nuclear industry it is not sufficient merely to adopt the usual precautions against the risks of explosion, fire, etc...; but great attention must be paid to the problems arising from the confinement of materials, radioactivity and the risks of criticality. The general principles of the technical prevention of radioactive risks are now well known. They must be applied as soon as the plans are drawn up for the installations, by taking into account : - the design and construction of the installations with respect to the risks mentioned above - the division of the plant into zones - the circulation of personnel and material - ventilation and purification of the air. The technical safety factors however, are not sufficient in themselves. However good the material and the degree of automation achieved, the smooth running of a factory depends on the man responsible for supervision and repair work or who takes initiatives. Technical safety is never definitive and must be continually maintained. The collaboration of the workers is necessary to its efficiency. Psychological measures must thus be taken as an addition to the technical precautions. This psychological prevention is based on: - education of the personnel - organization of the work and definition of the safety rules - checking on obedience to the rules and behaviour of the personnel - constant reminders of the necessity for the prevention of radioactive risks. Six years operation of the irradiated fuel processing plant at Marcoule have shown the importance of close collaboration between workers and technique. The authors analyse the results obtained from

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

International Nuclear Information System (INIS)

Megy, J.

1983-06-01

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

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

Vitrification of high level wastes in France

International Nuclear Information System (INIS)

Sombret, C.

1984-02-01

A brief historical background of the research and development work conducted in France over 25 years is first presented. Then, the papers deals with the vitrification at (1) the UP1 reprocessing plant (Marcoule) and (2) the UP2 and UP3 reprocessing plants (La Hague). 1) The properties of glass required for high-level radioactive waste vitrification are recalled. The vitrification process and facility of Marcoule are presented. (2) The average characteristics (chemical composition, activity) of LWR fission product solution are given. The glass formulations developed to solidify LWR waste solution must meet the same requirements as those used in the UP1 facility at Marcoule. Three important aspects must be considered with respect to the glass fabrication process: corrosiveness of the molten glass with regard to metals, viscosity of the molten glass, and, volatization during glass fabrication. The glass properties required in view of interim storage and long-term disposal are then largely developed. Two identical vitrification facilities are planned for the site: T7, to process the UP2 throughput, and T7 for the UP3 plant. A prototype unit was built and operated at Marcoule

Low-level radioactive waste management in EDF nuclear power plants (FRANCE)

International Nuclear Information System (INIS)

Boussard, C.

1991-01-01

This paper shows some recent examples of Low-level radioactive waste management in EDF nuclear power plants: - Radioactive liquid wastes proceeding from steam generators leaching (NOGENT SUR SEINE-1 REACTOR) - Thermal insulation proceeding from heat exchanger and blower (CHINON-2 REACTOR) - Old iron from reactor dismantling (CHINON-3 REACTOR, MARCOULE G1 REACTOR, MARCOULE G2-G3 REACTORS) - fresh air filter and fire detector - CHINON-2 REACTOR breaker chambers

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.)

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)

Dismantling of Evaporators by Laser Cutting Measurement of Secondary Emissions

International Nuclear Information System (INIS)

Pilot, Guy; Fauvel, Sylvain; Gosse, Xavier; De Dinechin, Guillaume

2006-01-01

In order to dismantle the evaporators of an obsolete reprocessing plant in Marcoule, studies were carried out by IRSN (Institut de Radioprotection et de Surete Nucleaire) / DSU/SERAC in cooperation with CEA (power laser group) on the laser cutting of steel structures, on the request of COGEMA (now AREVA NC) /Marcoule (UP1 dismantling project manager) and CEA/UMODD (UP1 dismantling owner). The aim of these studies was: - to quantify and to characterize the secondary emissions produced by Nd-YAG laser cutting of Uranus 65 steel pieces representative of UP1 evaporator elements and to examine the influence of different parameters, - to qualify a pre-filtration technique and particularly an electrostatic precipitator, - to compare the Nd-YAG used with other cutting tools previously studied. The experiments, which took place in a 35 m 3 ventilated cutting cell, allow to underline the following points: for the Uranus 65 steel, the sedimented dross, the deposits on the walls of the cutting cell and the aerosols drawn in the ventilation exhaust duct (∼ 275 m 3 /h), represent respectively between 92% and 99%, between 0.01% and 0.25% and between 1% and 8% of the total collected mass, the attached slag varies much from one configuration to the other and can sometimes amount to a relatively important fraction of the total mass, the kerves vary from 2 mm up to 7 mm for the Uranus 65 steel plates (thickness: 13.8 mm for the single plate and 12.8 + 3.5 mm for the double plate), the exhausted aerosol mass per cut length (g/m) decreases with the cutting speed, varies neither with the stand-off nor with the gas pressure, is dependent upon the gas nature (for the double plate), increases with the laser power, is strongly affected by the nature of the steel (stainless steel or mild steel) and is independent upon the plate position, the size distribution of aerosols is multimodal with a main mode often around 0.45 μm, the electrostatic precipitator has been a satisfactory prefilter

The CO{sub 2} cooling gas for the reactors G2/G3 (leaking, analysis, activity); Le CO{sub 2} de refroidissement des reacteurs G2/G3 (fuites, analyse, activite)

Energy Technology Data Exchange (ETDEWEB)

Meiffren, J; Dupay, F [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1965-07-01

The main objective of this study is to publicise the data obtained during five years operation of the reactor G2 and G3 at Marcoule as far as the cooling gas is concerned, from storage of reserves up to its slow escape into the atmosphere, and including all the stages of its practical use, its chemical examination, its nuclear behaviour and its possible physicochemical transformation. This work can not only yield information about the operations carried out at Marcoule but can also provide useful suggestions for improving the sealing and for decreasing the activity of the pressurized gas circuits in reactors similar to G2/G3. (authors) [French] Le but principal de cette etude est de diffuser les connaissances acquises au cours de cinq annees d'exploitation des reacteurs G2 et G3 de Marcoule en ce qui concerne le gaz de refroidissement, depuis son stockage d'appoint jusqu'a son echappement lent dans l'atmosphere, en passant par tous les stades de son utilisation pratique, de son etude chimique, de son comportement nucleaire, eventuellement de ses transformations physico-chimiques. Cette etude peut, non seulement renseigner sur les operations effectuees couramment a Marcoule, mais egalement donner des suggestions interessantes pour l'amelioration de l'etancheite et la diminution de l'activite des circuits de gaz en pression dans des reacteurs analogues a G2/G3. (auteurs)

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.)

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.)

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)

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

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.

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)

Ha waste conditioning

International Nuclear Information System (INIS)

Damette, G.

1986-01-01

In this report are given a full account of the choice and developments which have led to the continuous vitrification process implemented on industrial scale in the French vitrification facility at MARCOULE (AVM) and in several other installations now at design or construction phase by SGN (Societe Generale des Techniques Nouvelles). Advantages specific to this process are enumerated as well as practical lessons drawn from six years of continuous active operation at MARCOULE. The account concludes with brief description of installations presently being built [fr

Operational experience of the Marcoule reactors; Experience d'exploitation des reacteurs de Marcoule

Energy Technology Data Exchange (ETDEWEB)

Conte, F [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1963-07-01

The results obtaining from three years operation of the reactors G-2, G-3 have made it possible to accumulate a considerable amount of operational experience of these reactors. The main original points: - the pre-stressed concrete casing - the possibility of loading while under power - automatic temperature control have been perfectly justified by the results of operation. The author confirms the importance of these original solutions and draws conclusions concerning the study of future nuclear power stations. (author) [French] Les resultats atteints apres trois ans de fonctionnement des reacteurs G-2/G-3 permettent une accumulation considerable de l'experience d'exploitation de ces reacteurs. Les principales originalites: - caisson en beton precontraint - chargement en marche - surveillance automatique des temperatures sont largement justifiees par l'exploitation actuelle. L'auteur confirme l'interet de ces solutions d'avant-garde et en tire des conclusions pour les etudes de futures centrales nucleaires. (auteur)

The effluent problem in a plutonium production centre; Probleme des effluents d'un centre de production de plutonium

Energy Technology Data Exchange (ETDEWEB)

Galley, R; Cantel, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

The first part of the report is devoted to generalities: the geographical situation of the Marcoule Centre, the sources of radio-active effluent, methods of treating this effluent. In the second part the authors gives a detailed description of the various installations in the Radio-active Effluent Treatment Station at the Marcoule Centre, and outline the conditions governing the rejection of treated effluent into the Rhone. A few lines are given to comparisons between the results obtained from the use of these installations up till may 1959 and the expected results published by the same authors at the Brussels Conference (1956). In conclusion the authors lay down some of the essential principles, applicable to the study of new installations. (author) [French] La premiere partie du rapport est consacree a quelques generalites: situation geographique du Centre de Marcoule, provenance des effluents radioactifs, methodes de traitement de ces effluents. Dans la seconde partie, les auteurs presentent une description detaillee des diverses installations de la Station de Traitement des Effluents radioactifs du Centre de Marcoule et precisent les conditions de rejet dans le Rhone des effluents radioactifs traites. Quelques lignes sont consacrees aux comparaisons entre les resultats de l'exploitation des installations jusqu'en mai 1959 et les previsions publiees par les memes auteurs a l'occasion de la Conference de Bruxelles (1956). En conclusion, les auteurs donnent quelques principes essentiels, applicables a l'etude de nouvelles installations. (auteur)

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.)

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)

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.)

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)

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

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)

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.

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.)

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.

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

Monthly Record Tables, December 1998, with Supplement for the 4. quarter 1998; Tableaux mensuels des mesures, Decembre 1998, avec supplement relatif au 4-eme trimestre 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

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 toatmospheric 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.

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

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.)

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)

Spatial and temporal variations of plutonium isotopes (238Pu and 239,240Pu) in sediments off the Rhone River mouth (NW Mediterranean)

International Nuclear Information System (INIS)

Lansard, B.; Charmasson, S.; Gasco, C.; Anton, M.P.; Grenz, C.; Arnaud, M.

2007-01-01

The dispersion and fate of the Rhone River inputs to the Gulf of Lions (Northwestern Mediterranean Sea) have been studied through the spatial and temporal distributions of plutonium isotopes in continental shelf sediments. Plutonium isotopes ( 238 Pu and 239,240 Pu) are appropriate tracers to follow the dispersion of particulate matter due both to their high affinity for particles and their long half-lives. In the Rhone River valley, plutonium isotopes originate from both the weathering of the catchment basin contaminated by global atmospheric fallout, and the liquid effluents released from the Marcoule reprocessing plant since 1961. This work presents a first detailed study on 238 Pu and 239,240 Pu distributions in sediments from the Rhone prodelta to the adjacent continental shelf, since the decommissioning of Marcoule in 1997. The vertical distribution of Pu isotopes has been analysed in a 4.75 m long core sampled in 2001 at the Rhone mouth. Despite this length, plutonium is found at the last 10 cm, manifesting the high sedimentation rate of the prodeltaic area and its ability for trapping fine-grained sediments and associated contaminants. The highest 238 Pu and 239,240 Pu concentrations reached 1.26 and 5.97 Bq kg -1 respectively and were found within the layer 280-290 cm. The 238 Pu/ 239,240 Pu activity ratios (AR) demonstrated an efficient and huge trapping of the Pu isotopes derived from Marcoule. The fresh sediments, located on the top of the core, show lower plutonium activity concentrations and lower 238 Pu/ 239,240 Pu ratios. This decrease is in close relation with the shut down of the Marcoule reprocessing plant in 1997. In 2001, plutonium isotopes were also analysed in 21 surface sediments located offshore and concentrations ranged from 0.03 to 0.17 Bq kg -1 for 238 Pu and from 0.33 to 1.72 Bq kg -1 for 239,240 Pu. The 238 Pu/ 239,240 Pu AR ranged from 0.24 close to the river mouth to 0.06 southwards, indicating the decreasing influence of the

Safety apparatus for serious radioactive accidents (1962); Materiel d'intervention en cas d'accident radioactif grave (1962)

Energy Technology Data Exchange (ETDEWEB)

Estournel, R; Rodier, J [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1962-07-01

In the case of a serious radioactive accident, radioactive dust and gases may be released into the atmosphere. It is therefore necessary to be able to evaluate rapidly the importance of the risk to the surrounding population, and to be able to ensure, even in the event of an evacuation of the Centre, the continuation of the radioactivity analyses and the decontamination of the personnel. For this, the Anti-radiation Protection Service at Marcoule has organised mobile detection teams and designed a mobile laboratory and a mobile shower-unit. After describing the duty of the mobile teams, the report gives a description of the apparatus which would be used at the Marcoule Centre in the case of a serious radioactive accident. The method of using this apparatus is given. (authors) [French] Lors d'un accident radioactif grave, des poussieres et des gaz radioactifs peuvent etre relaches dans l'atmosphere. II est alors indispensable d'evaluer rapidement l'importance du risque couru par les populations environnantes, et de pouvoir assurer, meme dans le cas de l'evacuation du Centre, la poursuite des analyses radioactives et la decontamination du personnel. Pour cela, le Service de Protection contre les Radiations du Centre de Marcoule a mis sur pied des equipes mobiles de detection et realise une semi-remorque laboratoire ainsi qu'une semi-remorque douches. Apres avoir defini la mission des equipes mobiles, le rapport donne la description du materiel d'intervention qui serait mis en oeuvre par le Centre de Marcoule dans le cas d'un accident radioactif grave. Il precis le mode d'utilisation de ce materiel. (auteurs)

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)

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)

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)

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.)

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.)

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.)

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.)

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

High-level waste vitrification: the state of the art in France

International Nuclear Information System (INIS)

Sombret, C.; Maillet, J.

1988-02-01

This paper describes the main features of the French high-level waste vitrification program. These features include: - extensive R and D for more than 20 years; - successful operation of the AVM facility at Marcoule for about 10 years; - startup of six vitrification lines at La Hague, in the near future. The CEA is pursuing R and D for mid-term vitrification enhancement. New R and D facilities are being built at Marcoule to increase the capacity of vitrification equipment, study glass preparation at even higher temperatures to increase SiO 2 and Al 2 O 3 concentration, and perform extensive testing of samples with very high activity (more than 5,000Ci/l). 8 refs

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.

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

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

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

Plutonium and americium in the Rhone sediment

International Nuclear Information System (INIS)

Foulquier, L.; Jourd'Heuil, L.; Lambrechts, A.; Morello, M.; Miara, P.; Pally, M.

1996-01-01

238,239,240 Pu and 241 Am are measured in sediments from river ecosystems. These artificial radioisotopes are related to military and civilian activities. Small concentrations require an original radiochemical process followed by alpha spectrometry. 104 analysis on sediment from the Rhone have been taken since 1989. The transuranic elements present in sediment from the Rhone originate principally from the atmospheric nuclear tests carried out between 1945 and 1975, fallout from which spread some 1.2 x 10 16 Bq of 239 , 240 Pu and 2.9 x 10 13 Bq of 238 Pu into the atmosphere, 80 % of which was in the Northern Hemisphere (1). Various accidents have also released transuranic elements into the environment. Such was the case with the SNAP-9A satellite, which burned up in April 1964 and released 5.1 x 10 14 Bq of 238 Pu, 40 % of that in the Northern Hemisphere. Fallout from the Chernobyl accident containing α emitters was negligible in France. Irradiated-fuel reprocessing plants (La Hague and Marcoule) are authorized to release a emitters in their liquid effluent. The Marcoule plant is authorized to release 150 GBq per year into the Rhone. In 1991 the Marcoule facility renovated its liquid effluent treatment station. The activities released diminished considerably. (author)

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

The effluent problem in a plutonium production centre

International Nuclear Information System (INIS)

Galley, R.; Cantel, J.

1960-01-01

The first part of the report is devoted to generalities: the geographical situation of the Marcoule Centre, the sources of radio-active effluent, methods of treating this effluent. In the second part the authors gives a detailed description of the various installations in the Radio-active Effluent Treatment Station at the Marcoule Centre, and outline the conditions governing the rejection of treated effluent into the Rhone. A few lines are given to comparisons between the results obtained from the use of these installations up till may 1959 and the expected results published by the same authors at the Brussels Conference (1956). In conclusion the authors lay down some of the essential principles, applicable to the study of new installations. (author) [fr

Measurement of secondary emissions during laser cutting of steel equipments

Energy Technology Data Exchange (ETDEWEB)

Pilot, Guy [Institut de Radioprotection et de Surete Nucleaire, BP 68, 91192 Gif-sur-Yvette Cedex (France)], E-mail: guy.pilot@irsn.fr; Fauvel, Sylvain [Institut de Radioprotection et de Surete Nucleaire, BP 68, 91192 Gif-sur-Yvette Cedex (France); Gosse, Xavier [AREVA NC, Centre de Marcoule, 30200 Bagnols-sur-Ceze Cedex (France); Dinechin, Guillaume de [Commissariat a l' Energie Atomique, DEN/DM2S/SEMT, Saclay, Bat. 611, 91191 Gif-sur-Yvette Cedex (France); Vernhet, Didier [Commissariat a l' Energie Atomique, DEN/VRH/UMODD, Centre de Valrho, BP 17171, 20207 Bagnols-sur-Ceze Cedex (France)

2008-08-15

In order to dismantle some equipments of an obsolete reprocessing plant in Marcoule, studies were carried out by IRSN (Institut de Radioprotection et de Surete Nucleaire)/DSU/SERAC in cooperation with CEA (power laser group) on the laser cutting of steel structures, on the request of AREVA NC/Marcoule (UP1 dismantling project manager) and CEA/UMODD (UP1 dismantling owner). These studies were aimed at: {center_dot}quantifying and characterizing the secondary emissions produced by Nd-YAG laser cutting of Uranus 65 steel pieces and examining the influence of different parameters, {center_dot}qualifying a prefiltration technique and particularly an electrostatic precipitator, {center_dot}comparing the Nd-YAG laser used with other cutting tools previously studied especially on aerosol production and aerosol size distribution.

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

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

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

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

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

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

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

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)

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.)

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.

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)

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

Operational experience of the Marcoule reactors

International Nuclear Information System (INIS)

Conte, F.

1963-01-01

The results obtaining from three years operation of the reactors G-2, G-3 have made it possible to accumulate a considerable amount of operational experience of these reactors. The main original points: - the pre-stressed concrete casing - the possibility of loading while under power - automatic temperature control have been perfectly justified by the results of operation. The author confirms the importance of these original solutions and draws conclusions concerning the study of future nuclear power stations. (author) [fr

Usefulness of the decay rate in the management of radioactive waste stocks; De l'interet de la decroissance pour la gestion des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

Rodier, J; Cohendy, G [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

1969-07-01

It became apparent, during first few years operation of the Marcoule Centre, that it was very useful to exploit the natural decay rate of the radioactive element contaminating the waste. The storage of this waste under the best possible conditions in each case, was first of all favorable for the radiological safety point of view; it led, furthermore, to a marked reduction in the cost price since it made it possible to avoid employing protection means which would have proved to be excessively outsize after a few years. Finally, even when the half-life of the radioelements involved seemed to annul any possible advantages of this method, the temporary storage made it possible to develop treatment processes which were unknown at the time. The overall result of this policy is that at the present time over 98 per cent of the solid waste produced by the Marcoule Centre has been processed in such a way that it can, at any moment, be discharged from the site without difficulty. (authors) [French] Des les premieres annees de fonctionnement du Centre de Marcoule, il est apparu qu'il etait extremement benefique de mettre a profit la decroissance naturelle des elements radioactifs contaminant les dechets. Le stockage de ces dechets dans des conditions appropriees a chaque cas d'espece a tout d'abord ete favorable a la surete radiologique; en outre, il a abouti a une reduction sensible des prix de revient, du fait qu'il a evite de mettre en oeuvre des moyens de protection qui se seraient reveles surdimensionnes au bout de quelques annees. Enfin, meme lorsque la periode des radioelements en cause semblait enlever tout interet a cette methode, le stockage d'attente a permis de mettre au point des procedes de traitement inconnus a l'epoque. Le resultat global de cette politique est que, actuellement, plus de 98 pour cent des dechets solides produits depuis l'origine du Centre de Marcoule ont ete conditionnes de telle sorte qu'ils peuvent, a tout moment, etre evacues hors du Site

Sharing Experiences within AREVA D and D Project Portfolio: Four Illustrations - 13049

International Nuclear Information System (INIS)

Chabeuf, Jean-Michel; Varet, Thierry; AREVA Site Value Development Business Unit, La Hague Site

2013-01-01

Over the past ten years, AREVA has performed D and D operations on a wide range of nuclear sites, such as Marcoule and La Hague recycling plants, to Cadarache MOX fuel fabrication plant or Veurey and Annecy metallic Uranium machining plants. Each site is different from the other but some lessons can be shared through this D and D portfolio. In that respect, knowledge management is one of AREVA D and D Technical Department main missions. Four illustrations demonstrate the interest of knowledge share. Waste management is one of the key activities in D and D; It requires a specific characterization methodology, adapted logistics, and optimized waste channels, all of which have been developed over the years by AREVA teams on the site of Marcoule while they are rather new to La Hague, whose main activity remains fuel reprocessing despite the launch of UP2 400 D and D program. The transfer of know how has thus been organized over the past two years. Plasma cutting has been used extensively in Marcoule for years, while prohibited on the site of La Hague following questions raised about the risks associated wit Ruthenium sublimation. La Hague Technical Department has thus developed an experimental protocol to quantify and contain the Ruthenium risk, the result of which will then be applied to Marcoule where the Ruthenium issue has appeared in recent operations. Commissioning and operating fission products evaporators is a rather standard activity on UP2 800 and UP3, while the associated experience has been decreasing in Marcoule following final shutdown in 1998. When the French atomic Energy commission decided to build and operate a new evaporator to concentrate rinsing effluents prior to vitrification in 2009, AREVA La Hague operators were mobilized to test and commission the new equipment, and train local operators. Concrete scabbling is the final stage prior to the free release of a nuclear facility. In the context of Veurey and Annecy final cleanup and declassification

Sharing Experiences within AREVA D and D Project Portfolio: Four Illustrations - 13049

Energy Technology Data Exchange (ETDEWEB)

Chabeuf, Jean-Michel; Varet, Thierry [AREVA Site Value Development Business Unit, La Hague Site (France); AREVA Site Value Development Business Unit, La Hague Site

2013-07-01

Over the past ten years, AREVA has performed D and D operations on a wide range of nuclear sites, such as Marcoule and La Hague recycling plants, to Cadarache MOX fuel fabrication plant or Veurey and Annecy metallic Uranium machining plants. Each site is different from the other but some lessons can be shared through this D and D portfolio. In that respect, knowledge management is one of AREVA D and D Technical Department main missions. Four illustrations demonstrate the interest of knowledge share. Waste management is one of the key activities in D and D; It requires a specific characterization methodology, adapted logistics, and optimized waste channels, all of which have been developed over the years by AREVA teams on the site of Marcoule while they are rather new to La Hague, whose main activity remains fuel reprocessing despite the launch of UP2 400 D and D program. The transfer of know how has thus been organized over the past two years. Plasma cutting has been used extensively in Marcoule for years, while prohibited on the site of La Hague following questions raised about the risks associated wit Ruthenium sublimation. La Hague Technical Department has thus developed an experimental protocol to quantify and contain the Ruthenium risk, the result of which will then be applied to Marcoule where the Ruthenium issue has appeared in recent operations. Commissioning and operating fission products evaporators is a rather standard activity on UP2 800 and UP3, while the associated experience has been decreasing in Marcoule following final shutdown in 1998. When the French atomic Energy commission decided to build and operate a new evaporator to concentrate rinsing effluents prior to vitrification in 2009, AREVA La Hague operators were mobilized to test and commission the new equipment, and train local operators. Concrete scabbling is the final stage prior to the free release of a nuclear facility. In the context of Veurey and Annecy final cleanup and declassification

Safety apparatus for serious radioactive accidents (1962)

International Nuclear Information System (INIS)

Estournel, R.; Rodier, J.

1962-01-01

In the case of a serious radioactive accident, radioactive dust and gases may be released into the atmosphere. It is therefore necessary to be able to evaluate rapidly the importance of the risk to the surrounding population, and to be able to ensure, even in the event of an evacuation of the Centre, the continuation of the radioactivity analyses and the decontamination of the personnel. For this, the Anti-radiation Protection Service at Marcoule has organised mobile detection teams and designed a mobile laboratory and a mobile shower-unit. After describing the duty of the mobile teams, the report gives a description of the apparatus which would be used at the Marcoule Centre in the case of a serious radioactive accident. The method of using this apparatus is given. (authors) [fr

French industrial plant AVM for continuous vitrification of high level radioactive wastes

International Nuclear Information System (INIS)

Bonniaud, Roger; Sombret, Claude; Barbe, Alain

1975-01-01

The A.V.M. plant is a continuous process plant now under construction at Marcoule and intended for vitrifying the whole of fission product solutions from the C.E.A. (Commissariat a l'Energie Atomique) - Marcoule reprocessing plant. The outset of the construction took place in the second 1974 half year; the first radioactive run is scheduled in July 1977. The two steps of the process are shown: first a continuous calcination then a continuous glass making from the calcined product and suitable additives. The plant consists in two parts: vitrification and storage facilities. Some wastes will be continuously produced day after day due to gas clean up and worn out materials. Characteristics of the solutions processed, calcined products, glass composition, and expected liquid wastes are given in tables [fr

Direction of Nuclear Energy. Activity report 2010

International Nuclear Information System (INIS)

2011-11-01

This report proposes an overview of the research activities performed by the French DEN (Direction de l'Energie Nucleaire, Direction of Nuclear Energy) within the CEA. These activities address the future nuclear industrial systems (4. generation reactors, back-end of the future fuel cycle, basic scientific and technological research), the optimization of the industrial nuclear power (fuel cycle front end, second and third generation reactors, back-end of the present fuel cycle), major tools for the development of nuclear energy (simulation tools, Jules Horowitz reactor, value creation), clean up and dismantling of nuclear facilities (present status, the Passage project in Grenoble, the Aladin project in Fontenay-aux-Roses, projects at Marcoule, flow management of radioactive wastes, materials and disused fuels, transport). Three research centres are presented: Marcoule, Cadarache and Saclay

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

High level waste management in France

International Nuclear Information System (INIS)

Sombret, C.; Bonniaud, R.; Jouan, A.

1979-01-01

This paper deals with solidification of radioactive wastes. The vitrification process has been selected, the Marcoule vitrification plant and the operation are described. Prospects for vitrification of fission product solutions from La Hague reprocessing plant are given

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.)

Nuclear energy Division - 2011 Activity report

International Nuclear Information System (INIS)

2012-01-01

This document reports the activity of the Nuclear Energy Department (DEN) within the CEA. It evokes its international relationship (participation to international initiatives, cooperation with different countries), describes the scientific activity within the DEN, presents the Advanced Material Program, and the activities undertaken in different fields: future nuclear industrial systems (fourth generation reactors, downstream part of the future fuel cycle, fundamental scientific and technological research), optimization of the present nuclear industrial activity (second and third generation reactors, nuclear security, upstream and downstream part of the present fuel cycle), tools for nuclear development (numerical simulation, Jules Horowitz reactor), cleaning up and nuclear dismantling (dismantling strategy, the Passage project in Grenoble, works in Marcoule, the Aladin project in Fontenay, waste and material flow management, nuclear support installations, transports). It finally addresses the specific activities of the Marcoule, Cadarache and Saclay centres

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

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

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)

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

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

Plutonium extraction by the formation of insoluble salts (1960); Extraction du plutonium par formation de sels insolubles (1960)

Energy Technology Data Exchange (ETDEWEB)

Ganivet, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1960-06-15

The aim of this work is to convert Pu IV nitrate in solution into an insoluble salt. Three methods have been studied: 1) the conventional oxalic acid method was improved; 2) precipitation with 8-hydroxyquinoline was tried; 3) the hydrogen peroxide method was adapted to the eluates of the ionic resins from Marcoule. The yield from the oxalic process has been increased (loss of Pu in the mother-liquor brought from 200 mg/l to 20 mg/l). The study of Pu IV precipitation by 8-hydroxyquinoline has shown that the yield is excellent (Pu concentration in the mother-liquor less than 5 mg/h), but decontamination from impurities is nil. Finally, experiments on the precipitation by hydrogen peroxide of Pu IV solutions at the concentrations normally obtained from the anionic resins at Marcoule have given us good yields (Pu concentration in the mother-liquor less than 7 mg/l), and the purification is better than that obtained by oxalic acid (1000 ppm total impurities after a precipitation). (author) [French] L'objet de l'etude est la transformation en sel insoluble du nitrate de Pu IV en solution. Trois procedes ont ete etudies: 1) la methode classique a l'acide oxalique a ete amelioree, 2) la precipitation a la 8-hydroxyquinoleine a ete essayee; 3) le procede a l'eau oxygenee a ete adapte aux solutions d'elution des resines anion de Marcoule. Le rendement du procede oxalique a ete augmente (perte en Pu dans les eaux-meres ramenee de 200 mg/l a 20 mg/l). L'etude de la precipitation du Pu IV par la 8-hydroxyquinoleine a montre que le rendement etait excellent (concentration du Pu dans les eaux-meres inferieure a 5 mg/l), mais la decontamination en impuretes est nulle. Enfin, l'etude et l'application de la precipitation par l'eau oxygenee de solutions de Pu IV de concentrations habituellement obtenues a la sortie des resines anion a Marcoule nous ont permis d'obtenir un bon rendement (concentration de Pu dans les eaux-meres inferieure a 7 mg/l); la purification est meilleure que

Compared sensitivity of two nuclear sites: case of farming production contaminated by foliar way (chronicle release) S.E.N.S.I.B. project

International Nuclear Information System (INIS)

Mercat, C.; Vassas, C.

2005-01-01

This study joins within the framework of the S.E.N.S.I.B. project. The principle is to set up a step which allows to compare the sensitivity of two sites in case of radioisotopes releases; as illustration the sites of Marcoule and La Hague are considered. We are interested here in the case of the agricultural productions contaminated by foliar way during an atmospheric chronic release. Every site is characterized by specific vegetable and animal productions. The calculations of activities give an information about the sensitivity of products (mass and surface activities) and on the sensitivity of the Communes ( total activities). The contamination is supposed to be only made about foliar transfer. The studied radioisotopes are the cesium 137 , the cobalt 60 , the strontium 90 and the iodine 131 . For the cesium 137 and the cobalt 60 , the agricultural environment of the site of Marcoule seems globally more sensitive than that of La Hague, in the mean where the total activity in becquerels exported by the agricultural productions produced on the zone of 10 km around the site is more important for Marcoule than for La Hague. For the strontium 90 and for the iodine 131 , both agricultural environments are globally equivalent. This study which privileged the consideration of the regional specificities shows that the key factors of sensitivity are respectively the topographic situation for the deposit, the factor of translocation and the farming output for the vegetable productions and the daily food ration and the factor of transfer for the animal productions. (N.C.)

Vitrification of HLLW Surrogate Solutions Containing Sulfate in a Direct-Induction Cold Crucible Melter

International Nuclear Information System (INIS)

Tronche, E.; Lacombe, J.; Ledoux, A.; Boen, R.; Ladirat, C.H.

2009-01-01

Efforts were made in the People's Republic of China to solidify legacy high level liquid waste (HLLW) by the Liquid-Fed Ceramic Melter process (LFCM) in the 1990's. This process was to be a continuous process with high throughput as in the French Marcoule Vitrification Plant (AVM) or the LFCM. In this context, the CEA (Commissariat a l'Energie Atomique is a French government-funded technological research organization) suggests the Cold Crucible Induction Melter (CCIM) technology that has been developed by the CEA since the 1980's to improve the performance of the vitrification process. In this context a series of vitrification tests has been carried out in a CCIM. CEA and AREVA have designed an integrated platform based on the CCIM technology on a sufficient scale to be used for demonstration programs of the one-step process. In 2003 a test was carried out at Marcoule in southern France on simulated HLLW with high sulfur content. In order to ensure the tests performed at Marcoule were consistent with the Chinese waste-forms, the glass frit was supplied by a Chinese Industry. The CCIM facility is described in detail, including process instrumentation. The test run is also described, including how the solution was directly fed on the surface of the molten glass. A maximum capacity was determined according to the applied process parameters including the high operating temperature. The electrical power supply characteristics are detailed and a glass mass balance is also presented covering more than seven hundred kilograms of glass produced in a sixty-hour test run. (authors)

Radioactivity in the mediterranean sea. Sources and measures in the marine environment (sediments, mussels) - application to the Rhone delta (France)

International Nuclear Information System (INIS)

Pruchon-Zhen, S.

1995-01-01

Cesium 137, cesium 134, ruthenium 106 and ruthenium 103 have been studied in marine sediments and mussels collected from the Mediterranean coasts, in particular close to the Grand-Rhone river mouth. The influence of both the atmospheric fallout from the Chernobyl accident arisen on 26/4/86 and liquid discharges from nuclear facilities (nuclear power plants and Marcoule fuel reprocessing plant) upon radioactivity levels in the samples have guided this discussion. The Chernobyl accident represents a punctual input in time of radioactivity. In the North-Western Mediterranean basin, the South-East coasts have been more affected than the Rhone estuary rather influenced by liquid discharges into the Rhone river carried out mainly by the Marcoule reprocessing plant (mostly cesium 137 and ruthenium 106). In sediments located in front of the river mouth, cesium activity levels are linked to the Rhone river flow rather than to the fluctuations of the liquid discharges of low radioactive level from the Marcoule reprocessing plant. In fact, the highest levels of cesium in sediments correspond to low water levels of relatively strong intensity. Sediment rates have been calculated. Ruthenium is confirmed as a bad tracer for sedimentary processes. In mussels, cesium 137 ant ruthenium 106 activity levels show an annual rhythmic evolution apart from the respective concentrations in the Rhone river water. Only cesium exhibits activity levels linked to the biological cycle of mussels. The highest cesium 137 activity levels appear during winter spawning and show that it exists a preferential incorporation of cesium into the somatic tissue. (author)

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)

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)

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)

Improvement of the IRIS Process for Incineration of Various Radioactive Waste Compositions

International Nuclear Information System (INIS)

Lemort, F.; Charvillat, J. P.

2003-01-01

Incineration represents a promising weight and volume reduction technique for alpha-contaminated organic waste. Following several years of laboratory research initiated in 1983 on a nonradioactive prototype unit at the CEA's Rhone Valley (Marcoule) Research Center, an innovative process, IRIS, has been developed to meet the need for processing nuclear glove box waste containing large amounts of chlorine. In March 1999, the first highly chlorinated alpha-contaminated waste was incinerated in the industrial facility based on the IRIS process at the CEA's Valduc Center. The nonradioactive prototype at Marcoule and the radioactive facility at Valduc demonstrated that the process is highly effective with a continuously fed rotating tubular kiln and with a very effective control of corrosion by pyrolytic decomposition of the waste initially at 550 C. The ash quality meets specification requirements (< 1% carbon, < 1% chlorine) and the volume and weight reduction factors are sufficient (around 30). The offgas treatment system exhibits very high operating efficiency complying with gaseous emission standards

The Valduc waste incineration facility starts operations (iris process)

International Nuclear Information System (INIS)

Chateauvieux, H.; Guiberteuau, P.; Longuet, T.; Lannaud, J.; Lorich, M.

1998-01-01

In the operation of its facilities the Valduc Research Center produces alpha-contaminated solid waste and thus decided to build an incineration facility to treat the most contaminated combustible waste. The process selected for waste incineration is the IRIS process developed by the CEA at the Marcoule Nuclear Research Center. The Valduc Center asked SGN to build the incineration facility. The facility was commissioned in late 1996, and inactive waste incineration campaigns were run in 1997. The operator conducted tests with calibrated radioactive sources to qualify the systems for measuring holdup of active material from outside the equipment. Chlorinated waste incineration test runs were performed using the phosphatizing process developed by the Marcoule Research Center. Inspections performed after these incineration runs revealed the complete absence of corrosion in the equipment. Active commissioning of the facility is scheduled for mid-1998. The Valduc incinerator is the first industrial application of the IRIS process. (author)

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.)

Compared sensitivity of two nuclear sites: case of farming production contaminated by foliar way (chronicle release) S.E.N.S.I.B. project; Sensibilite comparee de deux sites nucleaires: cas des productions agricoles contaminees par voie foliaire (rejet chronique) Projet SENSIB

Energy Technology Data Exchange (ETDEWEB)

Mercat, C.; Vassas, C

2005-07-01

This study joins within the framework of the S.E.N.S.I.B. project. The principle is to set up a step which allows to compare the sensitivity of two sites in case of radioisotopes releases; as illustration the sites of Marcoule and La Hague are considered. We are interested here in the case of the agricultural productions contaminated by foliar way during an atmospheric chronic release. Every site is characterized by specific vegetable and animal productions. The calculations of activities give an information about the sensitivity of products (mass and surface activities) and on the sensitivity of the Communes ( total activities). The contamination is supposed to be only made about foliar transfer. The studied radioisotopes are the cesium{sup 137}, the cobalt{sup 60}, the strontium{sup 90} and the iodine{sup 131}. For the cesium{sup 137} and the cobalt{sup 60}, the agricultural environment of the site of Marcoule seems globally more sensitive than that of La Hague, in the mean where the total activity in becquerels exported by the agricultural productions produced on the zone of 10 km around the site is more important for Marcoule than for La Hague. For the strontium{sup 90} and for the iodine{sup 131}, both agricultural environments are globally equivalent. This study which privileged the consideration of the regional specificities shows that the key factors of sensitivity are respectively the topographic situation for the deposit, the factor of translocation and the farming output for the vegetable productions and the daily food ration and the factor of transfer for the animal productions. (N.C.)

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)

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)

Institute for separation chemistry of Marcoule I.C.S.M; Institut de chimie separative de Marcoule I.C.S.M

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

Institute for Separation Chemistry was created in March 2007, and the building including laboratory and offices will be opened to scientists and technicians the middle of 2008. Since resources in Uranium are scarce and wastes related to nuclear energy production are potentially dangerous, the chemistry associated to nuclear energy production always followed the principles of green chemistry: close the life-cycle of material and fuel, minimize wastes and ascertain the acceptability by a society via knowledge of chemistry and physical chemistry involved in processes. The Institute is devoted to chemistry at the service of the nuclear energy of the future, seen as an actor for sustainable development compatible with limited resources and chemical preservation of the atmosphere. Progresses in fundamental research, based on publication and education of students, engineers and young scientists, will be focused along seven identified directions, devoted to scattering and diffraction, microscopies and mainly mesoscopic modelling. The goals of the teams are described in this booklet, describing activities of the 28 scientists since two years. Separation chemistry, a branch of physical chemistry, is a key actor in 'green chemistry'. Nano-science and physical chemistry, at the roots of modern chemistry considering also non-covalent and long-range interactions, need to be included along the 'tools' involved in new processes. Three axis of research will be privileged: initial steps of separation, via dissolution by sono-chemical means, ion separation via colloids and complex fluids, and maintaining the separation between species involving self-repairing nano-materials, once the evolution of the interface fed from the evolving interface has been modelled. Eleven permanent staff scientists are already active since a few months on average at ICSM at the date of this report (5 CEA, 2 Universities and 4 CNRS). Teaching, scientific animation, summer schools and the common laboratory book of the UMR 5257 ICSM are managed by a team from CEA/INSTN. The activity report regroups goals of teams starting to work, together with previous recent activities of scientists now belonging to ICSM. This report describes the work done before (2003-2007) creation of ICSM by scientists now belonging to ICSM as well as the scientific work done in the first months of existence of ICSM, in the form of scientists integrated in host laboratories. Work done before is described on pages with a frame concern research performed before by scientists now staff permanent scientists at ICSM and related to the goals of ICSM. ICSM will be build by conjunction of the knowledge of scientists joining the group: at the date of writing - ten months before opening of the laboratory - 1/4 of the total number of permanent scientists have already joined the UMR 5257 and convene once every month. The report could have been presented either in administrative order, i.e. by the 'number' of the team, or starting from analysis of needs in nuclear and green chemistry. We have chosen the chronological order, i.e. the order of effective starts of experiments made by permanent ICSM staff.

Institute for separation chemistry of Marcoule I.C.S.M; Institut de chimie separative de Marcoule I.C.S.M

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

Institute for Separation Chemistry was created in March 2007, and the building including laboratory and offices will be opened to scientists and technicians the middle of 2008. Since resources in Uranium are scarce and wastes related to nuclear energy production are potentially dangerous, the chemistry associated to nuclear energy production always followed the principles of green chemistry: close the life-cycle of material and fuel, minimize wastes and ascertain the acceptability by a society via knowledge of chemistry and physical chemistry involved in processes. The Institute is devoted to chemistry at the service of the nuclear energy of the future, seen as an actor for sustainable development compatible with limited resources and chemical preservation of the atmosphere. Progresses in fundamental research, based on publication and education of students, engineers and young scientists, will be focused along seven identified directions, devoted to scattering and diffraction, microscopies and mainly mesoscopic modelling. The goals of the teams are described in this booklet, describing activities of the 28 scientists since two years. Separation chemistry, a branch of physical chemistry, is a key actor in 'green chemistry'. Nano-science and physical chemistry, at the roots of modern chemistry considering also non-covalent and long-range interactions, need to be included along the 'tools' involved in new processes. Three axis of research will be privileged: initial steps of separation, via dissolution by sono-chemical means, ion separation via colloids and complex fluids, and maintaining the separation between species involving self-repairing nano-materials, once the evolution of the interface fed from the evolving interface has been modelled. Eleven permanent staff scientists are already active since a few months on average at ICSM at the date of this report (5 CEA, 2 Universities and 4 CNRS). Teaching, scientific animation, summer schools and the common laboratory book of the UMR 5257 ICSM are managed by a team from CEA/INSTN. The activity report regroups goals of teams starting to work, together with previous recent activities of scientists now belonging to ICSM. This report describes the work done before (2003-2007) creation of ICSM by scientists now belonging to ICSM as well as the scientific work done in the first months of existence of ICSM, in the form of scientists integrated in host laboratories. Work done before is described on pages with a frame concern research performed before by scientists now staff permanent scientists at ICSM and related to the goals of ICSM. ICSM will be build by conjunction of the knowledge of scientists joining the group: at the date of writing - ten months before opening of the laboratory - 1/4 of the total number of permanent scientists have already joined the UMR 5257 and convene once every month. The report could have been presented either in administrative order, i.e. by the 'number' of the team, or starting from analysis of needs in nuclear and green chemistry. We have chosen the chronological order, i.e. the order of effective starts of experiments made by permanent ICSM staff.

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)

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)

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)

Fluvial export of radionuclides: impact on sediment storages of the Rhone River and fluxes towards the Mediterranean Sea; Transfert des radionucleides artificiels par voie fluviale: consequences sur les stocks sedimentaires rhodaniens et les exports vers la Mediterranee

Energy Technology Data Exchange (ETDEWEB)

Rolland, B

2006-02-15

This study deals with the behaviour of trace contaminants originating from chronic liquid releases within fluvial aquatic systems. It focuses on some particle reactive artificial radionuclides that were released by the Marcoule nuclear fuel reprocessing plant during several years mainly prior the end of the nineties and that are still detected in the lower Rhone river. It underlines the decrease of {sup 137}Cs, {sup 238}Pu and {sup 239+240}Pu fluxes to the Mediterranean Sea in relation with the variations in the chronic liquid releases from Marcoule. The role of flood events on radionuclides exports processes is particularly considered. Over the years 2002 to 2004, floods contributed for 67%, 55%, 68%, 49% and 56% of the mean annual fluxes of {sup 137}Cs, {sup 238}Pu and {sup 239+240}Pu and natural {sup 7}Be et {sup 210}Pbxs, although these events only represented 5% of time. The removal, during floods, of sediments contaminated by the Marcoule releases contributes on the average for 19%, 44% and 22% of the annual exports of {sup 137}Cs, {sup 238}Pu and {sup 239+240}Pu towards the Sea. Thus, such sedimentary stocks act as a delayed source term of artificial radioactivity that is currently significant. Determination of the sediments residence times before removal allows to evaluate the Rhone capacity to clear its contaminated stocks. Residence times of 200 years, 100 years and 900 years are estimated to be necessary to totally remove the accumulated {sup 137}Cs, {sup 238}Pu and {sup 239+240}Pu, respectively. The location typologies of sediment storages within fluvial systems are also specified. These location are represented on one hand by dams, and on the other hand by river banks and oxbow lakes. Stocks accumulated in dams seem to be removed more easily than those trapped in banks. (author)

Fluvial export of radionuclides: impact on sediment storages of the Rhone River and fluxes towards the Mediterranean Sea

International Nuclear Information System (INIS)

Rolland, B.

2006-02-01

This study deals with the behaviour of trace contaminants originating from chronic liquid releases within fluvial aquatic systems. It focuses on some particle reactive artificial radionuclides that were released by the Marcoule nuclear fuel reprocessing plant during several years mainly prior the end of the nineties and that are still detected in the lower Rhone river. It underlines the decrease of 137 Cs, 238 Pu and 239+240 Pu fluxes to the Mediterranean Sea in relation with the variations in the chronic liquid releases from Marcoule. The role of flood events on radionuclides exports processes is particularly considered. Over the years 2002 to 2004, floods contributed for 67%, 55%, 68%, 49% and 56% of the mean annual fluxes of 137 Cs, 238 Pu and 239+240 Pu and natural 7 Be et 210 Pbxs, although these events only represented 5% of time. The removal, during floods, of sediments contaminated by the Marcoule releases contributes on the average for 19%, 44% and 22% of the annual exports of 137 Cs, 238 Pu and 239+240 Pu towards the Sea. Thus, such sedimentary stocks act as a delayed source term of artificial radioactivity that is currently significant. Determination of the sediments residence times before removal allows to evaluate the Rhone capacity to clear its contaminated stocks. Residence times of 200 years, 100 years and 900 years are estimated to be necessary to totally remove the accumulated 137 Cs, 238 Pu and 239+240 Pu, respectively. The location typologies of sediment storages within fluvial systems are also specified. These location are represented on one hand by dams, and on the other hand by river banks and oxbow lakes. Stocks accumulated in dams seem to be removed more easily than those trapped in banks. (author)

Study of the retention of fission products by a few common minerals. Application to the treatment of medium activity effluents (1962); Etude de la retention des produits de fission par quelques mineraux usuels. Application aux traitements d'effluents de moyenne activite specifique (1962)

Energy Technology Data Exchange (ETDEWEB)

Auchapt, J M [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1962-07-01

The conditions in which strontium is fixed on calcite (the object of the Geneva report P/395 - USA - 1958) are more closely studied and the work is extended to five fission products present in the effluents, and to 17 common rocks and minerals. Although as it turns out this fixation is not suitable as a method of treating the S.T.E. effluents (i.e. those from the Effluent Treatment plant at Marcoule), the study shows that all the crystals considered are strongly contaminated by simple contact with the effluents. (author) [French] Les conditions de fixation du strontium sur la calcite (objet du rapport de Geneve P/395 - USA - 1958) sont approfondies et l'etude est etendue aux cinq produits de fission presents dans les effluents et a 17 roches et minerais courants. Bien qu'en definitive cette fixation se revele inutilisable comme procede de traitement d'effluents S.T.E. (Station de Traitement des Effluents, Marcoule), l'etude montre que tous les cristaux consideres se contaminent fortement par simple contact avec les effluents. (auteur)

Adaptation of mechano-graphy to the measurement of integrated doses (1962); Adaptation de la mecanographie pour la comptabilisation des doses integrees (1962)

Energy Technology Data Exchange (ETDEWEB)

Tabardel-Brian, R; Dulau, J [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1962-07-01

Because of the increasing number of workers exposed to nuclear radiation, and with a view to avoiding doses above the maximum permissible dose for these workers, it was necessary to find a system whereby the total irradiation assimilated during periods of 3 and 12 consecutive months could be known and circulated rapidly, within 48 hours. The method chosen for this requires the services of the Mechano-graphic service of the Marcoule Centre. The present article describes the mechanical data processing solution to this problem. (authors) [French] Devant le nombre croissant de travailleurs appeles a etre exposes a une irradiation d'origine nucleaire et avec le souci constant d'eviter les depassements de Dose Maximum Admissible a ces agents, il convenait de trouver un systeme de diffusion de doses integrees capable de nous renseigner, dans un delai de 48 h, sur le capital irradiation integre au cours des periodes 3 mois et 12 mois consecutifs. Le mode de diffusion retenu fait appel aux services de l'Atelier Mecanographie du Centre de Marcoule. Le present rapport expose la solution mecanographique apportee a ce probleme. (auteurs)

Advanced fuel fabrication

International Nuclear Information System (INIS)

Bernard, H.

1989-01-01

This paper deals with the fabrication of advanced fuels, such as mixed oxides for Pressurized Water Reactors or mixed nitrides for Fast Breeder Reactors. Although an extensive production experience exists for the mixed oxides used in the FBR, important work is still needed to improve the theoretical and technical knowledge of the production route which will be introduced in the future European facility, named Melox, at Marcoule. Recently, the feasibility of nitride fuel fabrication in existing commercial oxide facilities was demonstrated in France. The process, based on carbothermic reduction of oxides with subsequent comminution of the reaction product, cold pressing and sintering provides (U, Pu)N pellets with characteristics suitable for irradiation testing. Two experiments named NIMPHE 1 and 2 fabricated in collaboration with ITU, Karlsruhe, involve 16 nitride and 2 carbide pins, operating at a linear power of 45 and 73 kW/m with a smear density of 75-80% TD and a high burn-up target of 15 at%. These experiments are currently being irradiated in Phenix, at Marcoule. (orig.)

Experience gained in two years operation of G1; Experience acquise au cours de deux ans de fonctionnement du reacteur G1

Energy Technology Data Exchange (ETDEWEB)

de, Rouville; Pascal, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Scalliet, [Electricite de France (EDF), 75 - Paris (France)

1958-07-01

Technical specifications in respect of the first plutonium generating graphite reactor, the G1 at Marcoule, were stated in a paper read at the first Geneva Conference in 1955. We shall not therefore deal further with the technical characteristics of G1 in the present note, but rather propose to define - in the characteristic fields we think will be of major interest to foreign specialists - the results obtained in two and a half years operation since G1 first became critical on january 7, 1956. (author)Fren. [French] Les caracteristiques techniques du premier reacteur plutonigene, au graphite, de Marcoule, G1, ont ete donnees dans une communication presentee a la premiere conference de Geneve, en 1955. Nous n'y reviendrons donc pas dans la presente note qui a pour objet de faire le point, dans quelques domaines caracteristiques, qui nous ont paru les plus susceptibles d'interesser les specialistes etrangers, des resultats obtenus et des experiences faites au cours des deux annees et demi de fonctionnement du reacteur qui ont suivi sa divergence, le 7 janvier 1956. (auteur)

Experimental study of glass sampling devices

International Nuclear Information System (INIS)

Jouan, A.; Moncouyoux, J.P.; Meyere, A.

1992-01-01

Two high-level liquid waste containment glass sampling systems have been designed and built. The first device fits entirely inside a standard glass storage canister, and may thus be used in facilities not initially designed for this function. It has been tested successfully in the nonradioactive prototype unit at Marcoule. The work primarily covered the design and construction of an articulated arm supporting the sampling vessel, and the mechanisms necessary for filling the vessel and recovering the sample. System actuation and operation are fully automatic, and the resulting sample is representative of the glass melt. Implementation of the device is delicate however, and its reliability is estimated at about 75%. A second device was designed specifically for new vitrification facilities. It is installed directly on the glass melting furnace, and meets process operating and quality control requirements. Tests conducted at the Marcoule prototype vitrification facility demonstrated the feasibility of the system. Special attention was given to the sampling vessel transfer mechanisms, with two filling and controlled sample cooling options

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)

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.)

Minimum cost research when defining a very high efficiency air filtering installation

International Nuclear Information System (INIS)

Billard, F.; Seau, C.

1974-01-01

Economic criteria importance when establishing filtering projects is shown. In a first part, an optimization method of costs is studied. In the existing installations, it is necessary to study the operating costs, and eventually introduce changes in order to improve profitability. In the second part it is indicated how the Marcoule Center has solved this problem [fr

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

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.)

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)

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.)

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

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)

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)

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)

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.)

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

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

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

French high level wastes management

International Nuclear Information System (INIS)

Gauvenet, A.J.; Sombret, C.G.

1980-06-01

The first French spent fuel reprocessing plant went on stream in 1956 at Marcoule. Since then, all French irradiated fuels and some foreign spent fuels have been reprocessed either in this plant or in a subsequent plant built at La Hague. Marcoule is primarily devoted to metallic fuels, and La Hague to oxide fuels. The fission products solutions generated by reprocessing are acid liquids. They are stored on site in double walled stainless steel tanks fitted with a cooling device to deal with thermal release due to radioactive decay. Although these liquids are retrievable and can be transfered from one tank to another, and in spite of the fact that no disturbance such as overheating or leakage has ever occurred, a decision was made to solidify these solutions in order to make interim storage and, later on, ultimate disposal, safer and easier to control. Glass was chosen, because it is a flexible medium to deal with and it answers the quality requirements of ultimate disposal as well as the manufacturing constraints, such as equipment corrosion, volatilization during fabrication, and suitability to casting into canisters

Testing and evaluation of the properties of various potential materials for immobilizing high activity waste

International Nuclear Information System (INIS)

Malow, G.; Beran, V.; Lutze, W.

1980-01-01

Second joint annual report of the work performed on the testing and evaluation of materials for immobilizing high activity waste under Community contracts. At Marcoule, active block samples containing HAW from the Marcoule reprocessing plant were cast to the specification of five of the six original reference samples and leach tested at ambient temperature. Phosphate glass -bead samples produced by the Gelsenberg/DWK PAMELA process- were included in the test programme at HMI-Berlin and UKAEA Harwell. Leaching tests of inactive samples with leachants of various pH-values, with ionized water and with natural water compositions representative of certain repository conditions (salt, clay and granite) were added to the Harwell programme. The studies of radiation and thermal effects and the investigation of devitrification phenomena, started in 1977, continued, as samples reached annealing times of 2400 h and doses 4 x 10 17 dpg. The results achieved have so far confirmed most of the favourable preliminary assessments of glass based solidification products. At this stage the programme aims primarily at the understanding of physical and chemical phenomena rather that at verification under realistic waste storage and disposal conditions

Experience in the decontamination and dismantling of alpha facilities

International Nuclear Information System (INIS)

Charamathieu, A.

1988-01-01

Experience in dismantling alpha-containing radiochemical installations in France is described. The dismantling programme undertaken by the Societe des Techniques en Milieu Ionisant since 1977 is tabulated. This includes the dismantling of CALCIO and FLUO (plutonium metal), the dismantling of a slag processing plant, the dismantling of part of a medium activity plutonium mine and the dismantling of rooms 82-100 at Marcoule, France. (author)

Reprocessing of ''fast'' fuel in France

International Nuclear Information System (INIS)

Sauteron, J.; Bourgeois, M.; Le Bouhellec, J.; Miquel, P.

1976-05-01

The results of laboratory studies as well as pilot testing (AT-I La Hague, Marcoule, Fontenay-aux-Roses) in reprocessing of fast breeder reactor fuels are described. The paper covers all steps: head end, aqueous and fluoride volatility processes, and waste treatment. In conclusion, it is demonstrated why it is still too early to define a strategy of industrial reprocessing for this reactor type

Advanced high throughput MOX fuel fabrication technology and sustainable development

International Nuclear Information System (INIS)

Krellmann, Juergen

2005-01-01

Marcoule, the AREVA-COGEMA MELOX facility produces MOX fuel to recycle plutonium. I would like to insist on the advantages of the treatment/recycling process. The treatment/recycling strategy chosen by France is part of a global policy of sustainable development and safe management of the nuclear fuel cycle'. Considering the recent developments in the global nuclear industry, recycling will certainly have a significant part to play. Plutonium can be considered a valuable resource that will power current and future reactors, like the EPR. (author)

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.)

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

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.

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.

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)

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

Marcoule Institute for Separation Chemistry - 2009-2012 Scientific report

International Nuclear Information System (INIS)

Pellet-Rostaing, Stephane; Zemb, Thomas

2013-01-01

The mixed research unit 'Institute for Separation Chemistry' was created jointly by CEA, CNRS, University of Montpellier and Ecole Nationale Superieure de Chimie de Montpellier in March 2007. The building has been inaugurated in June 2009, with laboratories opened in the fall 2009 and has obtained authorisation to start experiments including a few grams of depleted uranium and natural thorium in January 2010. Last take-off was the theory group, who started in October 2009. Resources in Uranium are scarce, if only the 235 isotope is used and wastes related to nuclear energy production are potentially dangerous. The use of fast neutrons allows to multiply existing resources in national independence, but will be based on new separation processes, that can be modelled using predictive theory. Understanding and optimizing separation in the nuclear fuel cycle is the central aim of the 'Institute for Separation Chemistry' (ICSM). Enlarging this central goal to the needs for chemistry of recycling, for instance, strategic metals crucial for alternative energy, is the natural extension surfaces of needs and development of science, with a strong link for technology and implementation. This report gives an overview of the work published and submitted by ICSM since January 2009. The nine active research teams still work in the direction of the scientific open questions as defined and published by the French academy in 2007. The report is organized by scientific topics: each of the nine active research groups gathers a community of researchers and engineers from different expertises, who publish in various domains in the corresponding journals, and who participate at different international meetings. The research teams are organized as follows: 1 - Chemistry and Physical-chemistry of the Actinides; 2 - Ions at Active Interfaces; 3 - Ionic Separation from self-assembled Molecular systems; 4 - Sono-chemistry in Complex Fluids; 5 - Nano-materials for Energy and Recycling processes; 6 - Evolving Interfaces in Materials; 7 - Scattering and diffraction; 8 - Microscopies; 9 - Mesoscopic Modelization and Theoretical Chemistry. However, a large fraction of crucial results are obtained and published in common between teams within ICSM, via collaborations. Five focussed objectives of the research actions undertaken guide the choice of financially supported priorities within the large autonomy of creative chemists working at ICSM: - Understand chemical mechanisms underlying processes of chemical separation; - Optimize known methods for separation, in order to imagine, propose and test new separation methods, including supramolecular systems; - Anticipate the life-cycle of materials used in the context of nuclear and alternative energy productions; - Develop theory, with special attention to mesoscopic modelling, a well as develop methods of characterisation of fluid and solid samples: small angle scattering as well as environmental electronic microscopy; - Develop 'Green Chemistry' in all its facets, including sono-chemistry

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

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)

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.)

Nuclear energy

International Nuclear Information System (INIS)

1996-01-01

Several issues concerning nuclear energy in France during 1996 are presented: permission of a demand for installing underground laboratories in three sites (Marcoule, Bure and Chapelle-Baton); a report assessing the capacity of Superphenix plant to operate as a research tool; the project of merging between Framatome and Gec-Alsthom companies; the revision of a general report on nuclear energy in France; the issue of military plutonium management

Radiation hardening and irradiation testing of in-cell electronics for MA23/APM

International Nuclear Information System (INIS)

Friant, A.

1988-09-01

We relate briefly the radiation hardening method used to guarantee a gamma resistance of 10 Mrad for the whole electronic equipment associated with the slave arm of MA23 M servomanipulator which will be set up in cell 404 in Marcoule (APM). We describe the radiation testing of electronic devices and of the various subsystems designed by the D. LETI groups involved in the MA23/APM project

A solution to level 3 dismantling of gas-cooled reactors: Graphite incineration

International Nuclear Information System (INIS)

Dubourg, M.

1993-01-01

This paper presents an approach developed to solve the specific decommissioning problems of the G2 and G3 gas cooled reactors at Marcoule and the strategy applied with emphasis in incinerating the graphite core components, using a fluidized-bed incinerator developed jointly between the CEA and FRAMATOME. The incineration option was selected over subsurface storage for technical and economic reasons. Studies have shown that gaseous incineration releases are environmentally acceptable

High-level waste processing and conditioning: vitrification

International Nuclear Information System (INIS)

Bonniaud, R.

1981-02-01

The vitrification process used to treat fission product solutions at the Marcoule Vitrification Plant is described. The type of waste processed is characterized by its very high activity and the long lifetimes of some of the emitters that it contains. The performance obtained with this process is given together with the future developments envisaged. The storage of glasses is described as well as their behavior with time [fr

The MOX fuel in France

International Nuclear Information System (INIS)

2011-01-01

This document briefly describes the MOX production cycle which is performed in the MELOX plant in Marcoule by AREVA. It briefly indicates the main risks occurring during the whole MOX production and use cycle. They are associated with MOX production (high neutron and gamma dose rates, contamination, criticality, heat release), transportation, its use in reactors, its storage in pools after irradiation. All these stages need radiation protection measures

Statement of research in the field of solidification of high level radioactive wastes in France

International Nuclear Information System (INIS)

Bonniaud, R.; Sombret, C.

1975-01-01

Researches undertaken in France on the solidification of fission products are presented. Examples of glass compositions suitable for several types of fuels are given. The irradiation effects, crystallization, leaching and effects of α emitters have been studied. Two processes, one discontinuous, the other continuous have been studied and developed. In Marcoule, a continuous vitrification plant is under building and an experimental air-cooling storage is carried out [fr

EDF's dismantling experience

International Nuclear Information System (INIS)

Mira, J.J.

1993-01-01

The dismantling policy at EDF, taking into account technical, economical and socio-political factors, is presented. The various current realizations are reviewed and their dismantling solution discussed: Chinon A2, Chinon A1, Marcoule G1, G2, G3, Brennilis (EL4). Several dismantling projects are also described (Chinon A3, St-Laurent A1-A2, Chooz A). The various dismantling operations are presented and scheduled

Disposal of Low-Activity Liquid Effluents by Dilution

Energy Technology Data Exchange (ETDEWEB)

Bovard, P.; Candillon, C. [Atomic Energy Commission, Saclay (France)

1960-07-01

Nuclear centres are frequently faced with problems of disposal of sizeable quantities of low-activity liquid effluents. Under present conditions the most practicable solution seems to be to discharge them into a natural or artificial water system, so as to dilute them as much as possible and thus reduce their radioactive isotope content below the public health levels. This technique is employed by all nuclear centres in France, which use the following convenient outlets: Saclay: the artificial ponds made by Louis XIV to feed the great Versailles fountains; Fontenay-aux-Roses: the Paris sewer system; Grenoble: the river Isere; Marcoule: the river Rhone. Until 1957 the amount of waste was negligible. It is still very slight at the first three centres, only a few dozen millicuries a month. At Marcoule the activity of the effluents is somewhat greater, but the Rhone's rate of flow ensures a very low final content of radioactive elements. The increasing discharge of wastes into river systems calls for a close watch on changes in radioactivity in the environment (i.e. in air, water and soil), and especially on areas in which radioactive isotopes may accumulate. We have therefore made laboratory studies of the mechanics of radioactivity concentration, in order to improve our sampling methods and ascertain the movement of wastes.

Natural uranium-graphite system. Critial experiments on the G1 reactor; Systeme uranium naturel-graphite. Experiences critiques sur le reacteur G1

Energy Technology Data Exchange (ETDEWEB)

Schmitt, A P; Tanguy, P; Teste du Bailler, A; Zaleski, C P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

A number of experiments have been performed during the start up period of the G1 (1956) and G2 (1958) reactors in Marcoule, both on their lattices and on different lattices (hollow rods, clusters, under moderated lattices). The first chapter gives a thorough description of the two reactors. The second chapter deals with buckling measurements, both absolute (flux plots) and relative by the method of progressive substitution. The experimental results are summarised in Table VI. The third chapter contains a number of other measurements performed on G1. (author)Fren. [French] Le demarrage des reacteurs G1 (1956) et G2 (1958) de Marcoule nous a permis d'effectuer une serie d'experiences tant sur les reseaux de ces piles que sur des reseaux differents (elements tubulaires ou divises, reseaux sous-moderes, etc...). Dans une premiere partie, nous donnons une description detaillee des deux reacteurs. Dans la deuxieme partie, relative aux mesures de laplaciens, nous decrivons d'abord les mesures absolues de laplaciens (cartes de flux), puis les mesures relatives effectuees par la methode originale de remplacement progressif. Les resultats experimentaux sont rassembles dans le tableau VI. Dans la troisieme partie, nous rappelons un certain nombre d'autres mesures effectuees sur G1. (auteur)

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

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)

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

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)

Compaction of irradiated fuel can wastes by high temperature melting in cold crucibles

International Nuclear Information System (INIS)

Piccinato, R.; Ruty, J.P.; Caraballo, R.; Jacquet-Francillon, N.

1993-01-01

The fusion of hull wastes obtained from the reprocessing of various irradiated fuels is an alternative method to the cementation process used for the conditioning of such wastes. This new process, based on the direct fusion of hulls, has been carried out at CEA Marcoule with an inactive industrial prototype and qualified with an active laboratory prototype. The report shows the results obtained with the lab prototype on stainless steel and zircaloy hulls

Status of the French AVM vitrification facility

International Nuclear Information System (INIS)

Bonniaud, R.A.; Jouan, A.F.; Sombret, C.G.

1979-01-01

The Commission of the Marcoule Vitrification Plant (or AVM) has opened the industrial development era for the continuous vitrification process. Radioactive liquid wastes are calcinated in a rotary kiln to give a solid form, mixed with suitable raw materials in an electric furnace to make the glass. The glass is poured in containers and transferred to a disposal facility. The off gas released are processed. Design of La Hague next vitrification plant is given

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.)

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.)

4. European forum of radiation protection sciences. Proceedings

International Nuclear Information System (INIS)

2010-09-01

This 4. European forum of radiation protection sciences was the occasion for nuclear professionals to share their experience and to present the tools and techniques implemented in dismantling operations in the respect of radiation protection rules. This document brings together the abstracts and the available presentations given at this forum: 1 - Dismantling organisation and management - regulations: dismantling environment (A. Gay, Areva NC); Dismantling at the CEA (Ph. Guiberteau, DEN-Saclay); Optimisation of future dismantlement at the design and operation stage of facilities (P. Poncet, Areva); Action of the labour Ministry for workers radiation protection (T. Lahaye, DGT); 2 - Dismantling experience feedbacks 1: Radiation protection and dismantlement at Marcoule (J. Chardin, Areva NC); INB 106 dismantling (N. Pauwels, UDIL); Dismantling wastes management and valorisation of ALS and Saturne accelerators at Saclay (C. Salmon, CEA-Saclay); Chooz power plant deconstruction (L. Bardou, EDF); 3-4 - Dismantling projects: Phenix power plant dismantling (C. Beretti, CEA-Marcoule); Radiological characterization impact on the DGB project (H.C. Turbatte, F. Lemperiere, DGB Eurodif); Contribution of scientific calculations to reactor dismantling studies (A. Van Lauwe, CEA-Saclay); Acceptance committee of radiological cleansing companies (S. Faure, DPSN); Externalizing of the radiation protection skilled person (J.P. Piferrer, ATSR); International network of radiation protection professionals (G. Abela, EDF); 5 - Dismantling experience feedback 2: gloveboxes dismounting at La Hague plant (R. Choquet, P. Mougnard, Areva NC); Nuclear submarines dismantling in Russia (C. Deregel, Topp-Decide); Radioactive waste management of CERN accelerators (Y. Algoet, CERN); Nuclear facilities decommissioning (M. Berton, CEA, B. Marc, DRIM Sogeris); Asbestos removal in radiological environment (R. Blanc, Areva NC); 6-7-8 - Tools and methods: Aspilaser, decontamination by laser ablation (F

Researches on the radioactive wastes management: advances in the domain of the conditioning and the storage

International Nuclear Information System (INIS)

2003-12-01

This paper presents in the first part the researches in the domain of the radioactive wastes management at the Cea: separation processes and transmutation, the underground geologic disposal, the conditioning and the storage. The recent progresses in the domain of the conditioning and the storage are then detailed and the legal context presented. A special attention is given to the CECER of Marcoule, the expertise center on the conditioning and the storage of radioactive wastes. (A.L.B.)

Painting radioprotection at the nuclear eve

International Nuclear Information System (INIS)

Portelli, Aurelien; Travadel, Sebastien; Guarnieri, Franck; Parizel, Claire

2017-01-01

The CEA Marcoule centre is one of the first pillar of the French nuclear industry. The radiation protection department (SPR) of the centre benefited from the artistic skill of Jacques Castan who illustrated the safety campaigns of the SPR since 1959 and fed an imagination about radiation protection. His most ambitious creation was a wall painting in a staircase, made in 1962. This article describes the symbolic meaning of this work of art, which is today missing

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)

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

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)

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

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

Preliminary studies on the Marcoule site, using a wind-tunnel

International Nuclear Information System (INIS)

Chassany, J.Ph.; Salaun-Penquer, G.

1961-01-01

The tests were carried out in the 3.30 x 2.20 subsonic elliptical wind-tunnel of the Marseille Institute of fluid mechanics, on a 1/1000 scale model measuring 3 m x 3 m. The aerodynamic field developing above the site, made visible by ammonium, hydro-chlorate fumes, and the residues were observed and filmed by means of a synchronised cine-camera with stroboscopic lighting for 4 wind directions. The fall-out from the various waste products was obtained from a spraying of lead acetate solution on the model and hydrogen sulphide emissions. The zones of maximum pollution can be determined from a study of the film taken during the blackening of the spots. (author) [fr

Institute for separation chemistry of Marcoule I.C.S.M

International Nuclear Information System (INIS)

2007-01-01

Institute for Separation Chemistry was created in March 2007, and the building including laboratory and offices will be opened to scientists and technicians the middle of 2008. Since resources in Uranium are scarce and wastes related to nuclear energy production are potentially dangerous, the chemistry associated to nuclear energy production always followed the principles of green chemistry: close the life-cycle of material and fuel, minimize wastes and ascertain the acceptability by a society via knowledge of chemistry and physical chemistry involved in processes. The Institute is devoted to chemistry at the service of the nuclear energy of the future, seen as an actor for sustainable development compatible with limited resources and chemical preservation of the atmosphere. Progresses in fundamental research, based on publication and education of students, engineers and young scientists, will be focused along seven identified directions, devoted to scattering and diffraction, microscopies and mainly mesoscopic modelling. The goals of the teams are described in this booklet, describing activities of the 28 scientists since two years. Separation chemistry, a branch of physical chemistry, is a key actor in 'green chemistry'. Nano-science and physical chemistry, at the roots of modern chemistry considering also non-covalent and long-range interactions, need to be included along the 'tools' involved in new processes. Three axis of research will be privileged: initial steps of separation, via dissolution by sono-chemical means, ion separation via colloids and complex fluids, and maintaining the separation between species involving self-repairing nano-materials, once the evolution of the interface fed from the evolving interface has been modelled. Eleven permanent staff scientists are already active since a few months on average at ICSM at the date of this report (5 CEA, 2 Universities and 4 CNRS). Teaching, scientific animation, summer schools and the common laboratory book of the UMR 5257 ICSM are managed by a team from CEA/INSTN. The activity report regroups goals of teams starting to work, together with previous recent activities of scientists now belonging to ICSM. This report describes the work done before (2003-2007) creation of ICSM by scientists now belonging to ICSM as well as the scientific work done in the first months of existence of ICSM, in the form of scientists integrated in host laboratories. Work done before is described on pages with a frame concern research performed before by scientists now staff permanent scientists at ICSM and related to the goals of ICSM. ICSM will be build by conjunction of the knowledge of scientists joining the group: at the date of writing - ten months before opening of the laboratory - 1/4 of the total number of permanent scientists have already joined the UMR 5257 and convene once every month. The report could have been presented either in administrative order, i.e. by the 'number' of the team, or starting from analysis of needs in nuclear and green chemistry. We have chosen the chronological order, i.e. the order of effective starts of experiments made by permanent ICSM staff

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.)

Integral measurements of lattice properties in the natural uranium-graphite critical facility Marius; Mesures globales de reseaux a graphite dans l'empilement critique marius

Energy Technology Data Exchange (ETDEWEB)

Cogne, F [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-07-01

A systematic study of natural uranium-graphite lattices has been undertaken in the critical facility MARIUS, which was built in 1959 in Marcoule. Integral measurement of lattice properties are carried out by the progressive replacement method. This report describes the experimental methods, the analysis of the experiments and the results obtained for lattices with pitches ranging from 192 to 317 mm and fuel elements with cross sections ranging from 6 to 20 cm{sup 2}. The principles of correlation of the results are also outlined. Additional experimental results are also given, pertaining to the determination of the anisotropy, of both the axial and the radial migration areas, and of the age in graphite. (author) [French] L'empilement critique MARIUS, construit en 1959 a Marcoule, a ete utilise pour l'etude systematique des reseaux a graphite-uranium naturel. Les mesures globales de reseaux sont faites par la methode de remplacement progressif. On decrit ici les methodes experimentales utilisees pour ces mesures globales, les principes du depouillement et les resultats obtenus pour des pas de 192 a 317 mm et des combustibles de 6 a 20 cm{sup 2} d'uranium naturel. On donne d'autre part le principe de correlation des mesures. Un certain nombre de resultats experimentaux complementaires sont donnes, en permettant de determiner l'anisotropie, les aires de migration axiale et radiale, l'age dans le graphite. (auteur)

137 Cs as a tracer of the Catalan current

International Nuclear Information System (INIS)

Sanchez-Cabeza, J.A.; Molero, J.; Merino, J.; Pujol, L.; Mitchell, P.I.

1995-01-01

A number of nuclear power installations located in the north-western Mediterranean (NWM) area are known to enhance 137 Cs levels in various marine compartments. The nuclear fuel reprocessing plant at Marcoule (France) has been reported to originate a significant increase of 137 Cs in Rhone river waters and sediments because of the discharge of low-level liquid radioactive waste. This radionuclide may be used as a tracer of oceanographic processes in the NWM; in fact, 137 Cs of Rhone river origin has been detected in the Gulf of Lions by several authors. The results reported in this work correspond to various transect experiments in waters of the Catalan Sea and show that: (i) surface salinity measurements confirmed the presence of the Catalan current in the Cap de Creus area; (ii) the 1991 Cap de Creus transect showed clearly the presence of 137 Cs above a baseline level of 4.3 ± 0.2 Bq.m -3 ; (iii) the Cap de Salou transect showed elevated levels towards the coast; (iv) the 1992 Cap de Creus transect showed no structure at all. Therefore, it was concluded that traces of 137 Cs from the Marcoule nuclear fuel reprocessing plant were transported by the Catalan current and were detectable in the Catalan Sea with a complex spatio-temporal structure. (authors). 25 refs., 4 figs

Breeder reactors

International Nuclear Information System (INIS)

Gollion, H.

1977-01-01

The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components [fr

Bituminization of low- and medium-level radioactive wastes

International Nuclear Information System (INIS)

Lefillatre, G.

1976-01-01

French operations are presented concerning mainly: the bituminization of radioactive wastes produced in light water reactors; the direct bituminization of liquid effluents without concentration; the experiments carried out for 18 months on the land burial of concentrates solidified by bitumen into blocks of 100 liters. The knowledge acquired in France is exposed: in Valduc and in Saclay with facilities equipped with thin film evaporators and in Marcoule with the conditioning of trilaurylamine and tributyl-phosphate. At last the Cadarache bituminization [fr

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.)

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.)

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

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.)

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.)

Radio cobalt in French rivers

International Nuclear Information System (INIS)

Lambrechts, A.; Baudin-Jaulent, Y.

1996-01-01

The isotopes 58 and 60 of cobalt present in liquid wastes from nuclear plants or from fuel reprocessing plant of Marcoule are fixed in the different compartments of French rivers. The activity levels of radio-cobalt vary according to the sampled compartments nature (bryophyta > immersed plants > sediment > fish). Elsewhere, laboratory experimentations show that the contamination of fish occurs essentially from the water way rather than from food. Cobalt is mainly fixed by kidneys; muscles is no more than 30 % of the total fish activity. (author)

1996 Activity report; Rapport d`activite 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The 1996 activity report of the Direction for Waste Management of the CEA, is presented. Its activities have been developed in the framework of the general CEA cleaning plan, and include the management of wastes generated before 1992 in R and D CEA facilities, the disposal of spent fuels generated by research reactors (Orphee and Siloe) or prototype reactors (EL4 at Brennilis), and the dismantling and cleaning of obsolete facilities such as the plutonium radiochemistry building at Fontenay-aux-Roses and the pilot workshop at Marcoule

1996 Activity report

International Nuclear Information System (INIS)

1996-01-01

The 1996 activity report of the Direction for Waste Management of the CEA, is presented. Its activities have been developed in the framework of the general CEA cleaning plan, and include the management of wastes generated before 1992 in R and D CEA facilities, the disposal of spent fuels generated by research reactors (Orphee and Siloe) or prototype reactors (EL4 at Brennilis), and the dismantling and cleaning of obsolete facilities such as the plutonium radiochemistry building at Fontenay-aux-Roses and the pilot workshop at Marcoule

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.)

Decontamination of irradiated fuel processing waste using lead paraperiodate; Decontamination des effluents de traitement des combustibles irradies par le paraperiodate de plomb

Energy Technology Data Exchange (ETDEWEB)

Auchapt, J M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

1967-07-01

The process is designed to eliminate ruthenium. It consists in an oxidation using para-periodic acid whose excess, acting then as a carrying-over agent, is precipitated in the form of a lead salt at a pH of 5 or 6. This process makes it possible to precipitate 80 to 98 per cent of the ruthenium which is not removed by the conventional precipitation techniques which follow it. If the waste is a reducing agent, it is pre-oxidized using ozone or potassium permanganate. The process was developed at Marcoule in 1963 and has since 1965 been applied industrially; its cost price is of the same order of magnitude as conventional processes and its results are satisfactory. (author) [French] Le procede est destine a l'elimination du ruthenium. Il consiste en une oxydation par l'acide par paraperiodique dont l'exces, jouant alors le role d'entraineur, est precipite sous forme de sel de plomb a pH 5 ou 6. Ce traitement permet de precipiter 80 a 98 pour cent du ruthenium rebelle aux traitements de precipitation classique, qui doivent le suivre. Si l'effluent est reducteur il est preoxyde a l'ozone ou au permanganate de potassium. Mis au point a Marcoule en 1963, il est depuis 1965 exploite industriellement, son prix de revient est du meme ordre de grandeur que celui des traitements habituels et les resultats ont donne satisfaction. (auteur)

Pilot unit for cesium-137 separation; Unite pilote de separation du cesium-137

Energy Technology Data Exchange (ETDEWEB)

Raggenbass, A; Quesney, M; Fradin, J; Dufrene, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

Users of radiation are becoming increasingly interested in cesium-137. At the same time the starting up of the industrial plant at Marcoule will make available in the near future large stocks of fission products which should be made use of as quickly as possible. The installation described is a pilot plant for cesium-137 production which should make it possible: - to verify the chemical method on actual solutions of fission products, by treating about 100 curies of {sup 137}Cs by operation, - to obtain technical information on the chemical equipment (tele-commands, corrosion, maintenance, etc...), - to obtain {sup 137}Cs in sufficient quantity to perfect the technique of the manufacture of sealed sources. (author)Fren. [French] L'interet des utilisateurs de rayonnement se porte de plus en plus vers le caesium-137. Parallelement, la mise en oeuvre de l'ensemble industriel de Marcoule nous permettra de disposer dans un avenir proche de stocks importants de produits de fission qu'il sera interessant de valoriser au plus vite. L'installation que nous decrivons est un pilote de production de caesium-137 qui doit nous permettre: - de verifier la methode chimique sur des solutions de produits de fission reelles en traitant environ 100 curies de {sup 137}Cs par operation; - d'obtenir des renseignements techniques sur l'appareillage chimique (telecommandes, corrosion, entretien, etc...); - d'obtenir du {sup 137}Cs en quantite suffisante pour mettre au point la technique de fabrication des sources scellees. (auteur)

A contribution to the study of radioactive waste dilution in the Rhone involving tests with a rhodamine B tracer; Contribution a l'etude de la dilution des effluents radioactifs dans le Rhone par le rejet experimental de rhodamine B

Energy Technology Data Exchange (ETDEWEB)

Rodier, J.; Marichal, M. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre de production de plutonium de Marcoule, Service de protection contre les radiations (France)

1961-07-01

The process whereby waste from the Marcoule plant mixes with the water in the Rhone was followed in tests with rhodamine as a chemical tracer. Satisfactory dispersion was noted less than 4 km downstream from the waste discharge duct outlet, and the degree of homogeneity was considered to be satisfactory at the bridge of Roquemaure, und perfect at Avignon. This investigation not only revealed a complete absence of any preferential flow paths containing high radioactive waste concentrations, but it also enabled the most representative points to be selected at which to take Rhone water samples during future radioactive waste discharges. Reprint of a paper published in 'La Houille Blanche' N. 5 - Aug 196, p. 636-641 [French] L'emploi de la rhodamine comme traceur chimique a permis de suivre l'evolution du melange des effluents du Centre de Marcoule aux eaux du Rhone. La dispersion est deja satisfaisante a moins de 4 km en aval de la conduite des rejets, et l'homogeneite peut etre consideree comme atteinte au pont de Roquemaure et parfaite a Avignon. Cette etude a montre que les veines preferentielles ou se concentrait l'ecoulement des effluents radioactifs n'existent pas. Elle a permis de preciser en outre les emplacements les plus representatifs des points d'echantillonnage des eaux du Rhone au cours des rejets. Reproduction d'un article publie dans 'La houille blanche' N. 5 - Aug 196, p. 636-641.

Recuperation of the energy released in the G-1, an air-cooled graphite reactor core; Recuperation de l'energie degagee dans G 1 pile a graphite refroidie a l'air

Energy Technology Data Exchange (ETDEWEB)

Chambadal, P [Electricite de France (EDF), 75 - Paris (France); Pascal, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

The CEA (in his five-year setting plan) has objective among others, the realization of the two first french reactors moderated with graphite. The construction of the G-1 reactor in Marcoule, first french plutonic core, is achieved so that it will diverge in the beginning of 1956 and reach its full power in the beginning of the second semester of the same year. In this report we will detail the specificities of the reactor and in particular its cooling and energy recuperation system. The G-1 reactor being essentially intended to allow the french technicians to study the behavior of an energy installation supply taking its heat in a nuclear source as early as possible. (M.B.) [French] Le Commissariat a l'Energie Atomique (dans le cadre du plan quinquennal) a entre autres objectifs, la realisation des deux premiers reacteurs francais moderes au graphite. La construction du reacteur G-1 a Marcoule, premiere pile plutonigene francaise, est realise afin qu'il puisse diverger au debut de 1956 et atteindre sa pleine puissance au debut du second semestre de la meme annee. Dans ce rapport nous detaillerons les specificites du reacteur et en particulier son systeme de refroidissement et de recuperation d'energie. Le reacteur G-1 etant essentielement destine a permettre aux techniciens francais d'etudier le plus tot possible le comportement d'une installation productrice d'energie empruntant sa chaleur a une source nucleaire. (M.B.)

Nuclear materials transport in France

International Nuclear Information System (INIS)

Korycanek, J.

1990-01-01

About 1.5 million tons of uranium ore, 8000 tons of uranium concentrate, 1000 tons of UF 6 , 340 spent fuel containers, and 30 000 m 3 of nuclear wastes are transported annually by trucks, trains and ships in France. Annual costs of this transportation amount to 500-600 million FRF, and about 200 employees are engaged in this activity. Transportation of spent fuel to the La Hague and Marcoule fuel reprocessing plants, and the transport of plutonium are dealt with in detail. (Z.M.). 5 figs., 1 ref

U P1, an example for advanced techniques applied to high level activity dismantling

International Nuclear Information System (INIS)

Michel-Noel, M.; Calixte, O.; Blanchard, S.; Bani, J.; Girones, P.; Moitrier, C.; Terry, G.; Bourdy, R.

2014-01-01

The U P1 plant on the CEA Marcoule site was dedicated to the processing of spend fuels from the G1, G2 and G3 plutonium-producing reactors. This plant represents 20.000 m 2 of workshops housing about 1000 hot cells. In 1998, a huge program for the dismantling and cleaning-up of the UP1 plant was launched. CEA has developed new techniques to face the complexity of the dismantling operations. These techniques include immersive virtual reality, laser cutting, a specific manipulator arm called MAESTRO and remote handling. (A.C.)

Jacques Castan (1929-2014), radiation protection illustrator in the nuclear industry

International Nuclear Information System (INIS)

Guarnieri, Franck; Portelli, Aurelien; Travadel, Sebastien

2017-01-01

Improving risk control allows to reduce them. Showing that they can be controlled and how to do so is essential, and using images is an excellent mean. The work of Jacques Castan (1929-2014), draughtsman at the Radiation Protection Service (SPR) of CEA Marcoule Centre is the perfect illustration of this safety culture. Castan put his artistic talent to inform the general public and visitors about the activities of his Service through wall paintings, posters, comics and board games, giving a reassuring image of the radiation protection role

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

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.)

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.)

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.)

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.)

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

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)

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)

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

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)

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

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

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.)

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.)

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.)

Numerical modelling of coupled phenomena within molten glass heated by induction and mechanically stirred

International Nuclear Information System (INIS)

Jacoutot, L.

2006-11-01

This study reports on a new vitrification process developed by the French Atomic Energy Commission (CEA, Marcoule). This process is used for the treatment of high activity nuclear waste. It is characterized by the cooling of all the metal walls and by currents directly induced inside the molten glass. In addition, a mechanical stirring device is used to homogenize the molten glass. The goal of this study is to develop numerical tools to understand phenomena which take place within the bath and which involve thermal, hydrodynamic and electromagnetic aspects. The numerical studies are validated using experimental results obtained from pilot vitrification facilities. (author)

Decision no. 2011-DC-0223 of the French nuclear safety authority from May 5, 2011, ordering the MELOX SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

International Nuclear Information System (INIS)

2011-01-01

As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to MELOX SA company, operator of the Melox MOX fuel fabrication plant of Marcoule (France). (J.S.)

Multifunction system

International Nuclear Information System (INIS)

Wauthier, J.; Fiori, R.

1990-01-01

The development, the characteristics and the applications of a multifunction system are presented. The system is used on the RBES laboratory pipes, at Marcoule. The system was developed in order to allow, without time loss, the modification of the circuit function by replacing only one component. The following elements form the multifunction system: a fixed base, which is part of the tube, a removable piece, which is inserted into the base, a cover plate and its locking system. The material, chosen among commercial trade marks, required small modifications in order to be used in the circuit [fr

Numerical modelling of coupled phenomena within molten glass heated by induction and mechanically stirred; Modelisation numerique de phenomenes couples dans des bains de verre brasses mecaniquement et elabores en creuset froid inductif

Energy Technology Data Exchange (ETDEWEB)

Jacoutot, L

2006-11-15

This study reports on a new vitrification process developed by the French Atomic Energy Commission (CEA, Marcoule). This process is used for the treatment of high activity nuclear waste. It is characterized by the cooling of all the metal walls and by currents directly induced inside the molten glass. In addition, a mechanical stirring device is used to homogenize the molten glass. The goal of this study is to develop numerical tools to understand phenomena which take place within the bath and which involve thermal, hydrodynamic and electromagnetic aspects. The numerical studies are validated using experimental results obtained from pilot vitrification facilities. (author)

Context of surveillance of underground and surface waters; Contexte de la surveillance des eaux souterraines et superficielles

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

This document briefly describes the evolutions of regulations on site liquid effluents and of guideline values concerning radioactive wastes, briefly presents the surveillance of underground and surface waters of CEA sites, comments the guideline values of the radiological quality of waters aimed at human consumption, and gives an overview of information which are brought to public's attention. Then, for different CEA sites (Cadarache, Marcoule, Saclay, Grenoble, Fontenay-aux-Roses, Valduc, DIF), this document proposes a presentation of the hydrological context, regulatory context, the surface and underground water surveillance process and values, the storing zones of old wastes.

The solidification of high-level liquid wastes in glass and ceramics

International Nuclear Information System (INIS)

Krause, H.

1989-01-01

In spent nuclear fuel reprocessing a highly radioactive waste solution is produced. It must be converted into a solid product, which binds the radionuclides, be hydrolytic as well as radiation and temperature resistant. Borosilicate glasses fulfil these requirements and, jointly with the barriers of a repository, they prevent inadmissible amounts of radionuclides from escaping into the biocycle. Two techniques were developed for industrial-scale vitrification: a rotary kiln calciner combined with an induction heated metallic melter and the electrode heated ceramic melters. Both techniques were already demonstrated on an industrial scale and under radioactive conditions. (AVM, Marcoule and PAMELA, Mol). (orig./MM) [de

Separation of tritium from other hydrogen isotopes

International Nuclear Information System (INIS)

Roth, E.

1988-01-01

The paper describes a plant that has been operated at Marcoule for tritium production and used thermal diffusion enrichment, a facility that was built in Saclay to enrich hydrogen in tritium for low level measurements, and the Laue Langevin Institute tritium extraction plant. Details are given on the project under construction for the tritium separation facility at JET using Gas Chromatography, and on proposals for circuits for NET. Studies on catalysers for liquid phase catalytic exchange, on electrolysers, or different gas chromatography arrangements, are described. Systems designed for reprocessing plants, for detritiation of heavy water by distillation are briefly accounted for

Context of surveillance of underground and surface waters

International Nuclear Information System (INIS)

2010-01-01

This document briefly describes the evolutions of regulations on site liquid effluents and of guideline values concerning radioactive wastes, briefly presents the surveillance of underground and surface waters of CEA sites, comments the guideline values of the radiological quality of waters aimed at human consumption, and gives an overview of information which are brought to public's attention. Then, for different CEA sites (Cadarache, Marcoule, Saclay, Grenoble, Fontenay-aux-Roses, Valduc, DIF), this document proposes a presentation of the hydrological context, regulatory context, the surface and underground water surveillance process and values, the storing zones of old wastes

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.)

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

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)

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

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)

The Atalante facility at CEA/Marcoule: towards Gen IV systems fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Bordier, Gilles; Warin, Dominique; Masson, Michel [CEA/Marcoule Direction, BP 17171 - 30207 - Bagnols-sur-Ceze Cedex (France)

2008-07-01

The Atalante facility is a complete set of 18 hot labs and 9 shielded cells devoted to the research and development on fuel cycle. The activities correspond to 4 major sectors of nuclear research: -) to support the operation of actual reprocessing plants with the aim of adapting the head of the process to the increase of the spend fuel burn-up and to different types of new burnt fuels to be reprocessed (including MOX, USi or UMo fuels); -) to develop the COEX{sup TM} process that jointly manages uranium and plutonium from the dissolution of spent fuel to the production of UPuO{sub 2} powder and the fabrication of MOX fuel pellets; -) to prepare the recycling of minor actinides (MA) by partitioning or by grouped actinide extraction, and by MA bearing fuel fabrication; -) to study the long term behavior of high level waste conditioning matrices and especially self irradiation and leaching of vitrified waste. The first hot lab of Atalante was operated in 1992, the process shielded cell (CBP) in 2003 and the last LN1 lab in 2005, while at the same time a large scale demonstration test on the DIAMEX-SANEX MA partitioning process was performed. Now some new challenges involve further necessary evolutions of the facility. Some are related to safety assessment and operating flexibility; the major evolutions will come from new scientific goals and research programs. Furthermore, minor actinides materials irradiation tests in fast reactors will be prepared in the framework of a large international cooperation (GACID program) and need the production of significant amounts of MA bearing mixed U-Pu oxide compounds in new hot labs and shielded cells equipment. The major new research tools are presented and we highlight how Atalante is a unique facility which brings a real opportunity to reinforce the European and international scientific cooperation in order to prepare the next Gen IV fuel cycle. (authors)

The Atalante facility at CEA/Marcoule: towards Gen IV systems fuel cycle

International Nuclear Information System (INIS)

Bordier, Gilles; Warin, Dominique; Masson, Michel

2008-01-01

The Atalante facility is a complete set of 18 hot labs and 9 shielded cells devoted to the research and development on fuel cycle. The activities correspond to 4 major sectors of nuclear research: -) to support the operation of actual reprocessing plants with the aim of adapting the head of the process to the increase of the spend fuel burn-up and to different types of new burnt fuels to be reprocessed (including MOX, USi or UMo fuels); -) to develop the COEX TM process that jointly manages uranium and plutonium from the dissolution of spent fuel to the production of UPuO 2 powder and the fabrication of MOX fuel pellets; -) to prepare the recycling of minor actinides (MA) by partitioning or by grouped actinide extraction, and by MA bearing fuel fabrication; -) to study the long term behavior of high level waste conditioning matrices and especially self irradiation and leaching of vitrified waste. The first hot lab of Atalante was operated in 1992, the process shielded cell (CBP) in 2003 and the last LN1 lab in 2005, while at the same time a large scale demonstration test on the DIAMEX-SANEX MA partitioning process was performed. Now some new challenges involve further necessary evolutions of the facility. Some are related to safety assessment and operating flexibility; the major evolutions will come from new scientific goals and research programs. Furthermore, minor actinides materials irradiation tests in fast reactors will be prepared in the framework of a large international cooperation (GACID program) and need the production of significant amounts of MA bearing mixed U-Pu oxide compounds in new hot labs and shielded cells equipment. The major new research tools are presented and we highlight how Atalante is a unique facility which brings a real opportunity to reinforce the European and international scientific cooperation in order to prepare the next Gen IV fuel cycle. (authors)

Modernization and enlarging of the Marcoule pilot plant for R and D

International Nuclear Information System (INIS)

Calame-Longjean, A.; Revol, G.; Roux, J.P.; Ranger, G.

1987-01-01

The aim of the pilot plant is the testing of process and equipment in actual conditions with spent fuels on a half-industrial scale and for a significant time. From 1963 to 1983 more than 11t of spent fuels (mainly from fast reactors) were reprocessed. Since 1983 is modernized and enlarged and the new plant of the TOR project (treatment of oxides from fast reactors) are described [fr

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)

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)

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)

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)

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

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

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

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)

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)

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.)

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.)

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.)

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.)

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

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...

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

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

Nuclear reactor (1960); Reacteurs nucleaires (1960)

Energy Technology Data Exchange (ETDEWEB)

Maillard, M L [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires; Leo, M B [Electricite de France (EDF), 75 - Paris (France)

1960-07-01

The first French plutonium-making reactors G1, G2 and G3 built at Marcoule research center are linked to a power plant. The G1 electrical output does not offset the energy needed for operating this reactor. On the contrary, reactors G2 and G3 will each generate a net power of 25 to 30 MW, which will go into the EDF grid. This power is relatively small, but the information obtained from operation is great and will be helpful for starting up the power reactor EDF1, EDF2 and EDF3. The paper describes how, previous to any starting-up operation, the tests performed, especially those concerned with the power plant and the pressure vessel, have helped to bring the commissioning date closer. (author) [French] Les premiers reacteurs industriels plutonigenes francais G1 - G2 - G3 du Centre de Marcoule comportent une installation de recuperation d'energie. La production d'electricite de G1 ne compense pas l'energie depensee par ailleurs pour le fonctionnement de l'ensemble, par contre, G2 et G3 doivent fournir chacun une puissance de 25 a 30 MW au reseau national d'Electricite de France. Cette puissance est modeste, mais l'experience acquise grace a ces reacteurs est tres grande et c'est grace a elle qu'il nous sera possible de mettre en exploitation les reacteurs energetiques EDF1 - EDF2 - EDF3. Le memoire decrit comment, avant tout demarrage du reacteur, les essais effectues, en particulier ceux concernant l'installation de recuperation d'energie et le caisson, ont permis d'abreger la phase de montee en puissance. (auteur)

Review of the incineration of 500 tonnes of radio-active residues; Bilan de l'incineration de 500 tonnes de residus radioactifs

Energy Technology Data Exchange (ETDEWEB)

Rodier, J; Seyfried, P; Charbonneaux, M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

1969-07-01

During its first five years operation, the incinerator at the Marcoule Centre has burnt almost 500 tonnes of radio-active residues. Improvements in some of the details of the process have been made during this period; they concern the nature of the materials involved. The technical and radiological results for the installation are very favorable, and have made it possible to maintain a high charge factor.Although the overall economic results are not advantageous in the case of ungraded solid residues this method represents nevertheless the best available for eliminating oils, solvents, wood and dead animals. It can also be of use furthermore each time that a dilution in the atmosphere can advantageously be used as a method of disposing of certain radio elements such as tritium or carbon 14 in the form of gases or vapours. (author) [French] L'incinerateur du Centre de Marcoule a brule, durant les 5 premieres annees de fonctionnement, pres de 500 tonnes de residus radioactifs. Les ameliorations de detail realisees au cours de cette periode ont porte sur la nature des materiaux employes. Les bilans techniques et radiologiques de l'installation sont tres favorables et ont permis de maintenir un facteur de charge eleve. Si le bilan economique n'est pas favorable a l'incineration des residus solides 'tout venant' cette methode constitue cependant la solution ideale pour l'elimination des huiles, des solvants, du bois et des cadavres d'animaux. En outre, elle peut etre interessante chaque fois que la dilution dans l'atmosphere peut etre avantageusement mise a profit pour rejeter certains radioelements tels que le tritium ou le carbone 14 sous forme de gaz ou de vapeurs. (auteur)

Chemical analysis as production guide

International Nuclear Information System (INIS)

Bouzigues, H.; Fontaine, A.; Patigny, P.

1975-01-01

All piloting data of chemical processing plants are based on the results of analysis. The first part of this article describes a system of analysers adapted to the needs of the Pierrelatte plant, with management of signals collected by the factory computer. Part two shows the influence of analytical development in the establishment of material balance sheets for the Marcoule spent fuel processing plant. Part three stresses the contribution of the automation of analytical test processes at the La Hague spent fuel processing plant. In all three cases the progress in analytical methods greatly improves the safety, reliability and response time of the various operations [fr

French reprocessing and waste management R and D

International Nuclear Information System (INIS)

Lefevre, J.; Baudin, G.; Viala, M.

1991-01-01

The R and D facilities, briefly described here, are very large in France, covering α, β and γ research on the laboratory, prototype and pilot plant scales. Thanks to these resources, many innovations have been designed for UP3, concerning the overall process: shearing, dissolution, clarification, offgas treatment, extraction cycles, acid recovery, aqueous and organic effluent treatment, in-line conditioning of process wastes and fission products, process control and analysis. The effort has not stopped with the startup of UP3. A new R and D unit, Atalante, at Marcoule, will start operating in late 1991. Innovative R and D programs have been set up to prepare for the future

Jean-Marc Delaye's application file for the HDR (accreditation to supervise research) diploma

International Nuclear Information System (INIS)

Delaye, J.M.

1999-01-01

This document contains a curriculum vitae of the candidate who is a researcher in the Marcoule CEA, and then a presentation of his personal and professional approach to scientific research. The author presents the main topics he has studied: molecular dynamics simulation techniques, the diffusion theory, metal and oxide glass structures, the effect of irradiation on glasses. He also describes his supervision activities. The document also contains some of its scientific publications: molecular dynamics study of vacancy-like defects in a model glass, use of molecular dynamics to represent the structure of simplified nuclear glasses, atomistic modelling approach of the effects of alpha disintegrations in nuclear glasses

Study of the {sup 241}Am in fresh water. Application to Rh e ecosystem; Etude des transferts de L'{sup 241}Am en eau douce. Application a l'ecosysteme rhodanien

Energy Technology Data Exchange (ETDEWEB)

Veran, M.P.; Garnier-Laplace, J.; Baudin, J.P. [CEA Cadarache, Inst. de Protection et de Surete Nucleaire (IPSN), 13 - Saint-Paul-lez-Durance (France)

1999-07-01

The {sup 241}Am transfers are quantified in the heart of a model ecosystem, representative of the aquatic medium downstream the site of Marcoule. The dominating phenomenon of adsorption governs the distribution of Am in the ecosystem. The capacities of bioaccumulation are more important for the primary producers, the zooplankton and the filter molluscs. The results show the key role of the benthic fauna able to mobilize {sup 241}Am fixed on the sediment and the importance of the feeding to explain the contamination of the omnivorous fishes. The dreissensia can be used as bio indicator of radio contamination by transuranium elements. (N.C.)

Advice presented on behalf of the national defense and forces commission, about the project of financial law for 2003 (no 230). Tome 2. Defense, nuclear dissuasion; Avis presente au nom de la commission de la defense nationale et des forces armees, sur le projet de loi de finances pour 2003 (no 230). Tome 2. Defense, disssuasion nucleaire

Energy Technology Data Exchange (ETDEWEB)

Carre, A

2002-10-01

The first part of this document analyzes, first, the increased flexibility of the US nuclear dissuasion, then it makes a status of the ballistic and nuclear proliferation in Asia and in the Middle-East and shows the organization of the French nuclear dissuasion with respect to the evolution of the threat. The second part concerns the budget for 2003 devoted to the modernization of the dissuasion tool with the continuation of the main programs: modernization of the oceanic and air forces, front-end studies on nuclear safety and propulsion reactors, simulation program, and dismantling of the fissile materials production sites (Pierrelatte and Marcoule centers). (J.S.)

Advice presented on behalf of the national defense and forces commission, about the project of financial law for 2003 (no 230). Tome 2. Defense, nuclear dissuasion

International Nuclear Information System (INIS)

Carre, A.

2002-10-01

The first part of this document analyzes, first, the increased flexibility of the US nuclear dissuasion, then it makes a status of the ballistic and nuclear proliferation in Asia and in the Middle-East and shows the organization of the French nuclear dissuasion with respect to the evolution of the threat. The second part concerns the budget for 2003 devoted to the modernization of the dissuasion tool with the continuation of the main programs: modernization of the oceanic and air forces, front-end studies on nuclear safety and propulsion reactors, simulation program, and dismantling of the fissile materials production sites (Pierrelatte and Marcoule centers). (J.S.)

Graphite reactor physics; Physique des piles a graphite

Energy Technology Data Exchange (ETDEWEB)

Bacher, P; Cogne, F [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Noc, B [Electricite de France (EDF), 75 - Paris (France)

1964-07-01

The study of graphite-natural uranium power reactor physics, undertaken ten years ago when the Marcoule piles were built, has continued to keep in step with the development of this type of pile. From 1960 onwards the critical facility Marius has been available for a systematic study of the properties of lattices as a function of their pitch, of fuel geometry and of the diameter of cooling channels. This study has covered a very wide field: lattice pitch varying from 19 to 38 cm. uranium rods and tubes of cross-sections from 6 to 35 cm{sup 2}, channels with diameters between 70 and 140 mm. The lattice calculation methods could thus be checked and where necessary adapted. The running of the Marcoule piles and the experiments carried out on them during the last few years have supplied valuable information on the overall evolution of the neutronic properties of the fuel as a function of irradiation. More detailed experiments have also been performed in Marius with plutonium-containing fuels (irradiated or synthetic fuels), and will be undertaken at the beginning of 1965 at high temperature in the critical facility Cesar, which is just being completed at Cadarache. Spent fuel analyses complement these results and help in their interpretation. The thermalization and spectra theories developed in France can thus be verified over the whole valid temperature range. The efficiency of control rods as a function of their dimensions, the materials of which they are made and the lattices surrounding them has been measured in Marius, and the results compared with calculation on the one hand and with the measurements carried out in EDF 1 on the other. Studies on the control proper of graphite piles were concerned essentially with the risks of spatial instability and the means of detecting and controlling them, and with flux distortions caused by the control rods. (authors) [French] Entreprise il y a dix ans a l'occasion de la construction des piles de Marcoule, l'etude de la

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

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)

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)

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)

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

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

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.

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.)

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

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)

Application of crown-ethers to caesium and strontium removal from Marcoule reprocessing concentrate

International Nuclear Information System (INIS)

Dozol, J.F.; Garcia, J.C.i; Sastre, A.M.

1991-01-01

The liquid wastes arising from reprocessing plants are treated by evaporation, the distillate is discharged into environment and the concentrate containing all the active and inactive salts must be stored in geological formation, after embedding, due to the activity of long life radionuclides (actinides, Cs, Sr). The object of the work is to remove actinides and cesium/strontium from high sodium content acidic concentrated in order to sharply decrease the volume of wastes to be stored in geological formation. (author)

Application of crown-ethers to cesium and strontium removal from Marcoule reprocessing concentrate

International Nuclear Information System (INIS)

Dozol, J.F.; Casas I Garcia, J.

1990-01-01

The liquid wastes arising from reprocessing plants are treated by evaporation, the distillate is discharged into environment and the concentrate containing all the active and inactive salts must be stored in geological formation, after embedding, due to the activity of long life radionuclides (actinides, Cs, Sr). The objective of this work, is after removal actinides, to remove cesium/strontium from high sodium content acidic concentrates in order to sharply decrease the volume of wastes to be stored in geological formation

The use tri-n-butyl phosphate in plutonium extraction. Radiolysis and recycling of the solvent (1963); Le phosphate de tri-n-butyle dans l'extraction du plutonium. Radiolyse et recyclage du solvant (1963)

Energy Technology Data Exchange (ETDEWEB)

Isaac, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1963-07-01

The work concerns the radiolysis and recycling of tri-n-butyl phosphate used as extraction solvent for plutonium. The radiolysis is studied on an industrial solvent using a cobalt 60 source. Figures are given for the yield of the mono- and di-butyl-phosphoric acids formed from the dry and water-saturated solvents and the influence of nitric acid on the formation of dibutyl-phosphoric acid is indicated. The recycling treatment of the solvent is reconsidered with a view to lowering the residual contamination due to fission products. The tests carried out on a solvent from the plutonium extraction plant at Marcoule show the efficiency of the sodium carbonate treatment. Of all the products studied, only caustic soda led to a better decontamination than sodium carbonate; in all cases however, the elimination of ruthenium is always incomplete. (author) [French] L'etude porte sur la radiolyse et le recyclage du phosphate de tri-n-butyle utilise comme solvant d'extraction du plutonium. La radiolyse est etudiee sur un solvant industriel a l'aide d'une source de cobalt 60. On donne les rendements de formation des acides mono- et dlbutylphosphoriques a partir de solvants secs et satures d'eau, et on montre l'influence de l'acide nitrique sur la formation de l'acide dibutylphosphorique. Le traitement de recyclage du solvant est repris en vue d'abaisser la contamination residuelle en produits de fission. Les essais, effectues sur un solvant provenant de l'usine d'extraction du plutonium de Marcoule, montrent l'efficacite du traitement au carbonate de sodium. De tous les reactifs etudies, seule la soude a donne une decontamination superieure au carbonate de sodium; mais dans tous les cas, l'elimination du ruthenium est toujours incomplete. (auteur)

Development of a machine for sorting laundry according to its radioactive contamination (1962); Conception et mise en oeuvre d'une machine a trier le linge en fonction de sa contamination par des produits radioactifs (1962)

Energy Technology Data Exchange (ETDEWEB)

Cohendy, G; Alles, M; Pellerin, A [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1962-07-01

A the Marcoule Plutonium Production Centre special clothing is worn, in the active zones. A large fraction of these clothes is contaminated and must therefore be subjected to specialised treatments during washing in order to be reintroduced subsequently without danger. Because of the large amount of clothes to be treated it has become necessary to install a special semi-automatic machine; the role of the operator is limited to placing the clothing in the machine and to removing the baskets of sorted clothes. The machine itself has been designed and built by the Mechanics Section. The Radiation Protection Service chose the sorting method which is based on {beta} radiation and uses Geiger counters actuating an appropriate electronic system; the Service also developed this system, depending on the various degrees of contamination of the treated clothing. (authors) [French] Le Centre de Production de Plutonium de Marcoule utilise des vetements speciaux pour travailler dans les zones actives. Une proportion importante de ces vetements se contamine et doit, de ce fait, subir des traitements appropries au cours du lavage, de facon a pouvoir etre reintroduits sans danger dans le circuit d'utilisation. Devant l'importance des quantites a traiter, il est apparu necessaire de mettre en place une machine speciale, semi-automatique; le role de l'operateur, consiste en effet uniquement a introduire le linge dans la machine et a extraire de celle-ci les paniers de linge trie. La Section de Mecanique a concu et realise la machine proprement dite. Le Service de Protection contre les Radiations a choisi le mode de tri qui s'effectue en {beta} a l'aide de compteurs Geiger actionnant une electronique appropriee et a assure la mise au point de cette electronique, en fonction des divers degres de contamination du linge a trier. (auteurs)

The first metallurgical tests on plutonium; Premiers essais metallurgiques sur le plutonium

Energy Technology Data Exchange (ETDEWEB)

Grison, E; Abramson, R; Anselin, F; Monti, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

Metallic plutonium was first prepared in France in January 1956, as soon as we had access to quantities of the order of several grams of plutonium, which had been extracted from the rods of the pile EL2 at Saclay. Since up to the present this reactor, of thermal power 2 000 kW, has been our only source of plutonium, we have so far only worked on experimental quantities sufficient for the basic tests but not for tests on a scale of possible applications. It is this work, carried out during this phase of preliminary research, which is described below. With the starting up of the plutonium extraction plant at Marcoule, where the reactor G1 has been operating at power for more than a year, we shall go on next to a another order of magnitude which will allow the manufacture and experimentation of prototype fuel elements. (author) [French] La premiere elaboration de plutonium metallique en France fut faite en janvier 1956, des que nous pumes disposer de quantites de plutonium de l'ordre de quelques grammes, qui avaient ete retires des barreaux de la pile EL2 de Saclay. Ce reacteur, d'une puissance thermique de 2 000 kW, ayant ete jusqu'a present notre seule source de plutonium, nous n'avons encore travaille que sur des quantites experimentales suffisantes pour les essais de base, mais non pour des essais a l'echelle d'applications possibles. Ce sont les travaux effectues pendant cette phase de recherches preliminaires qui seront evoques ci-dessous. Avec la mise eu route de l'usine d'extraction de plutonium de Marcoule, ou le reacteur G1 fonctionne en puissance depuis plus d'un an, nous allons passer prochainement a un autre ordre de grandeur, qui nous permettra la fabrication et l'experimentation d'elements combustibles prototypes. (auteur)

The IRIS process and its industrial application at the CEA's Valduc Center

International Nuclear Information System (INIS)

Lemort, F.; Longuet, T.; Charvillat, J.P.; Chateauvieux, H.; Guiberteau, P.; Lorich, M.

2000-01-01

Following several years of laboratory research initiated in 1983 on a nonradioactive prototype unit at the CEA's (Atomic Energy Commission) Valrho/Marcoule Research Center, an innovative process, IRIS, has been developed to meet the need for processing nuclear glove box waste. It is to our knowledge the only high-capacity process in the world capable of dealing with highly chlorinated (25 wt% chlorine) alpha-contaminated waste. IRIS is based on a two-step incineration process combining pyrolysis and calcination with a specific off-gas treatment. The nonradioactive prototype at Marcoule has operated for over 5000 hours, demonstrating the following advantages: - Highly effective process control through regular, continuous feed of the rotating tubular kiln. - Very effective control of corrosion by pyrolytic decomposition of organo-chlorine compounds at 550 deg. C under inert atmosphere. - High ash quality (< 1% carbon, < 1% chlorine) compatible with online radionuclide recovery or vitrification processes. - High waste/ash weight and volume reduction factors (30 in both cases). - Very low gas flow rates limiting waste entrainment compared with direct incineration. - Very high efficiency off-gas treatment complying with gaseous emission standards. - Protection of system piping by substitution of stable phosphates for metal chlorides generated in the off-gas lines. - Flexible process capacity from a few kg/h for nuclear waste to 500 kg/h for conventional waste. In December 1991, the CEA's Valduc Center decided to build the first industrial facility based on the IRIS process. Construction work, equipment design and assembly, nonradioactive testing and preparation of the safety report lasted six years. The facility successfully began operating with radioactive waste on March 10, 1999, substantiating the R and D effort. Three other nuclear industrial operators around the world have adopted the IRIS process for future implementation. (authors)

The health physics of installations for decladding irradiated fuels or for handling radio-elements at Marcoule; La radioprotection des installations de degainage des combustibles irradies et des radio-elements a Marcoule

Energy Technology Data Exchange (ETDEWEB)

Chassany, J; Guillermin, P; Mallet, P [Commissariat a l' Energie Atomique, Centre de Production de Plutonium de Marcoule, 30 - Chusclan (France)

1966-07-01

Radiation protection practices for handling reactor fuel elements are described. Elements of considerable specific radioactivity are handled under water. A study was made of water filtration and of ventilation in the building. The installations are divided up into zones depending on the radioactive risks, and the radiation level atmospheric contamination are the object of a systematic control at various points. A description is given of all aspects of health physics which have been encountered during six years: storage, transfer of radioactive material; decladding, rolling, waste disposal, specialized operations, installations in operation and at rest, and transport. In spite of the gradual increase in the activity of these installations, the total doses received by the personnel have hardly altered and the number of cases of physical contamination has diminished. (authors) [French] Dans ces installations, se manipulent sous l'eau des elements a radioactivite specifique considerable. La filtration de l'eau, la ventilation ont ete particulierement etudiees. L'ensemble a ete divise en lieux classes en fonction des risques radioactifs et des appareils controlent en permanence l'irradiation et la contamination atmospherique en certains points. Tous les aspects de la radioprotection resultant de six annees d'experience relatifs: au stockage, au deconteneurage, au degainage, au laminage, a l'evacuation des residus, aux travaux particuliers, installations en marche et a l'arret, et aux transports sont successivement decrits. Malgre l'accroissement progressif de l'activite de cet ensemble, les doses integrees par le personnel n'ont pratiquement pas augmente et le nombre des cas de contamination corporelle a diminue. (auteurs)

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

A contribution to the study of radioactive waste dilution in the Rhone involving tests with a rhodamine B tracer

International Nuclear Information System (INIS)

Rodier, J.; Marichal, M.

1961-01-01

The process whereby waste from the Marcoule plant mixes with the water in the Rhone was followed in tests with rhodamine as a chemical tracer. Satisfactory dispersion was noted less than 4 km downstream from the waste discharge duct outlet, and the degree of homogeneity was considered to be satisfactory at the bridge of Roquemaure, und perfect at Avignon. This investigation not only revealed a complete absence of any preferential flow paths containing high radioactive waste concentrations, but it also enabled the most representative points to be selected at which to take Rhone water samples during future radioactive waste discharges. Reprint of a paper published in 'La Houille Blanche' N. 5 - Aug 196, p. 636-641 [fr

The French R and D programme for fast reactor fuel reprocessing

International Nuclear Information System (INIS)

Auchapt, P.; Bourgeois, M.; Calame-Longjean, A.; Miquel, P.; Sauteron, J.

1979-01-01

The process employed is the Purex process adapted to the specific case of fast breeder reactor fuels. The results achieved have demonstrated that the aqueous method can be applied to these fuels: nearly ten years of operation in the ATl workshop which reprocesses RAPSODIE fuels, and the good results obtained at the Marcoule pilot facility on large batches of fuel attest to this achievement. The CEA effort continues principally on extrapolation to industrial scale, thanks mainly to experiments conducted on industrial prototypes and to the launching of the TOR project, which will, as of 1984, allow reprocessing of FBR fuels on a significant scale, and which will provide extensive additional resources for R and D activities

Pilot unit for cesium-137 separation

International Nuclear Information System (INIS)

Raggenbass, A.; Quesney, M.; Fradin, J.; Dufrene, J.

1958-01-01

Users of radiation are becoming increasingly interested in cesium-137. At the same time the starting up of the industrial plant at Marcoule will make available in the near future large stocks of fission products which should be made use of as quickly as possible. The installation described is a pilot plant for cesium-137 production which should make it possible: - to verify the chemical method on actual solutions of fission products, by treating about 100 curies of 137 Cs by operation, - to obtain technical information on the chemical equipment (tele-commands, corrosion, maintenance, etc...), - to obtain 137 Cs in sufficient quantity to perfect the technique of the manufacture of sealed sources. (author) [fr

Systematic monitoring of atmosphere radioactivity on the main French nuclear sites in 1961; Surveillance systematique de la radioactivite de l'atmosphere sur les principaux sites nucleaires francais en 1961

Energy Technology Data Exchange (ETDEWEB)

Doury, A.

1963-07-01

After having indicated the different stations, departments and bodies involved in the monitoring of radioactivity for radiation protection purposes (notably CEA, EDF, National Navy for their establishments in Saclay, Le Bouchet, Grenoble, Marcoule, Cadarache, Cherbourg, Chinon, Antony) and briefly described how this network operates, this report presents the measurement program which comprises measurements of global instantaneous radioactivity at the vicinity of the ground, measurements of long life radioactivity, the identification and dosing of long life radio-elements, and additional measurements. It presents sampling and measurement methods for these different measurements performed on different forms of radioactive elements (airborne dusts, gas, gamma and cosmic ambient radiation, precipitations). Results are discussed and presented under tabular and graphical forms.

Technical and economic assessment of process of treatment of coated bituminous sludge by combustion/vitrification (report PNGMDR 2013-2015)

International Nuclear Information System (INIS)

2015-01-01

This note reports the assessment of a processing by combustion/vitrification of about 60.000 parcels of coated bituminous sludge belonging to intermediate-level long-lived and low-level long-lived category, and warehoused on the Marcoule CEA site. This assessment identifies the front-end cost of an exploratory R and D which would be required to undo technological locks, the cost of design, realisation and exploitation of the associated installation, and the negative features dues to the lack of technological maturity and to the management of environmental risks and impacts in comparison with the reference industrial solution (geological storage). As a conclusion, the authors state that the process is still not technically feasible

Reprocessing of fast neutron reactor fuel

International Nuclear Information System (INIS)

Bourgeois, M.

1981-05-01

A PUREX process specially adapted to fast neutron reactor fuels is employed. The results obtained indicate that the aqueous process can be applied to this type of fuel: almost 10 years operation at the AT 1 plant which processes fuel from RAPSODIE; the good results obtained at the MARCOULE pilot plant on large batches of reference fuels. The CEA is continuing its work to transfer this technology onto an industrial scale. Industrial prototypes and the launching of the TOR (traitement d'oxydes rapides) project will facilitate this transfer. In 1984, it is expected that fast fuels will be able to be processed on a significant scale and that supplementary R and D facilities will be available [fr

Radiological assessment of the Rhone valley. Final report related to the ground environment

International Nuclear Information System (INIS)

Roussel-Debet, S.; Saey, L.; Mourier, D.; Salaun, G.

2012-01-01

This report presents and comments the results obtained during a ground radiological survey performed in the Rhone valley from May 2009 to end of 2011. It recalls the general sampling and analysis strategy, in terms of objectives, locations, samples to measure tritium and carbon 14, and specific samples. It presents and discusses results obtained for tritium and carbon 14, and notably measurements obtained in boar meat. Other commented results are those obtained by gamma spectrometry on farm products (measurements of natural and artificial radionuclides), by analysis of milk products, and by specific samplings and analysis (bio-indicators in the vicinity of Marcoule, Camargue sands and beaches, rice field grounds, measurements performed after the Fukushima accident)

Experience with melting beta and gamma contaminated metals

International Nuclear Information System (INIS)

Feaugas, J.; Laplante, D.; Puechlong, Y.; Barbusse, R.

1994-01-01

Following a description of the melting facility operated for purposes of decommissioning the G2 and G3 gas-cooled reactors at Marcoule, the physical and radiological characteristics of 4070 tonnes of metal processed to date in the furnace are discussed. Considerable data have been recorded regarding operating and measurement procedures; the results show that secondary wastes account for less than 5 wt% of the processed scrap metal, and that all the 137 Cs is transferred to the dust and slag. During the last two months of 1993, the ingot mold line was replaced by rails on which dollies carrying integral work-form molds can be moved into position beneath the casting ladle. (authors). 21 figs

Recuperation of the energy released in the G-1, an air-cooled graphite reactor core

International Nuclear Information System (INIS)

Chambadal, P.; Pascal, M.

1955-01-01

The CEA (in his five-year setting plan) has objective among others, the realization of the two first french reactors moderated with graphite. The construction of the G-1 reactor in Marcoule, first french plutonic core, is achieved so that it will diverge in the beginning of 1956 and reach its full power in the beginning of the second semester of the same year. In this report we will detail the specificities of the reactor and in particular its cooling and energy recuperation system. The G-1 reactor being essentially intended to allow the french technicians to study the behavior of an energy installation supply taking its heat in a nuclear source as early as possible. (M.B.) [fr

Survey of economics of spent nuclear fuel reprocessing

International Nuclear Information System (INIS)

Valvoda, Z.

1976-01-01

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

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

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.

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

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)

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.)

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)

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

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)

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

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.)

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

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

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)

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

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)

2011 reporting of the risk handling at CEA

International Nuclear Information System (INIS)

Anon.

2012-01-01

In 2011 CEA reported 100 events to the Authority for Nuclear Safety (ASN). 93 were graded 0 on the INES scale and 7 were graded 1. None of them had a significant impact on the staff health and the environment. 25% of these events concerned delays in the controls of safety equipment. In 2011 CEA had to manage several situations that led to a response of its crisis center: 1) the explosion of an oven belonging to the Socodei-Centraco company situated near the Marcoule Center, 2) the discovery of about 500 grenades from the first world war during digging out works in the Grenoble Center, 3) flooding due to heavy rains in the Cadarache Center, and 4) an intrusion attempt at the Cadarache Center. (A.C.)

Cold-crucible melting of hulls and structural materials

International Nuclear Information System (INIS)

Jouan, A.; Jacquet-Francillon, N.; Puyou, M.; Piccinato, R.

1990-01-01

The method currently implemented at the La Hague UP3 reprocessing plant for conditioning of PWR zircaloy hulls is cement embedding. Another promising method, mainly for reducing the waste volume and the available exchange surface area, is melting. A cold-crucible melting process has therefore been developed by the CEA at Marcoule (France) over the last decade. Development work first concentrated on cladding hulls from fast breeder reactors, then from pressurized water reactors. The process can be used for both types of cladding wastes. Subassembly head and foot end-caps are sheared off and should be suitable for surface storage after α decontamination by successive rinsing. If necessary because of their α activity, they could be melted in a larger furnace

Theory, design, and operation of liquid metal fast breeder reactors, including operational health physics

International Nuclear Information System (INIS)

Adams, S.R.

1985-10-01

A comprehensive evaluation was conducted of the radiation protection practices and programs at prototype LMFBRs with long operational experience. Installations evaluated were the Fast Flux Test Facility (FFTF), Richland, Washington; Experimental Breeder Reactor II (EBR-II), Idaho Falls, Idaho; Prototype Fast Reactor (PFR) Dounreay, Scotland; Phenix, Marcoule, France; and Kompakte Natriumgekuhlte Kernreak Toranlange (KNK II), Karlsruhe, Federal Republic of Germany. The evaluation included external and internal exposure control, respiratory protection procedures, radiation surveillance practices, radioactive waste management, and engineering controls for confining radiation contamination. The theory, design, and operating experience at LMFBRs is described. Aspects of LMFBR health physics different from the LWR experience in the United States are identified. Suggestions are made for modifications to the NRC Standard Review Plan based on the differences

Theory, design, and operation of liquid metal fast breeder reactors, including operational health physics

Energy Technology Data Exchange (ETDEWEB)

Adams, S.R.

1985-10-01

A comprehensive evaluation was conducted of the radiation protection practices and programs at prototype LMFBRs with long operational experience. Installations evaluated were the Fast Flux Test Facility (FFTF), Richland, Washington; Experimental Breeder Reactor II (EBR-II), Idaho Falls, Idaho; Prototype Fast Reactor (PFR) Dounreay, Scotland; Phenix, Marcoule, France; and Kompakte Natriumgekuhlte Kernreak Toranlange (KNK II), Karlsruhe, Federal Republic of Germany. The evaluation included external and internal exposure control, respiratory protection procedures, radiation surveillance practices, radioactive waste management, and engineering controls for confining radiation contamination. The theory, design, and operating experience at LMFBRs is described. Aspects of LMFBR health physics different from the LWR experience in the United States are identified. Suggestions are made for modifications to the NRC Standard Review Plan based on the differences.

Stephane Gin's application file for the HDR (accreditation to supervise research) diploma

International Nuclear Information System (INIS)

Gin, St.

2000-01-01

This document contains a curriculum vitae of the candidate who is a researcher in the Marcoule CEA, and then a presentation of his personal and professional approach to scientific research and the main topic he has been studying, i.e. the long term behaviour of nuclear glasses. He indicates the numerous works performed in collaboration with other researchers, his supervision activities. He provides a list of his scientific publications, and three articles: Use of orthophosphate complexing agents to investigate mechanisms limiting the alteration kinetics of French SON 68 nuclear glass; Alteration kinetics of a simplified nuclear glass in an aqueous medium: effects of solution chemistry and of protective gel properties on diminishing the alteration rate; French SON 68 nuclear glass alteration mechanisms on contact with clay media

High energy resolution and high count rate gamma spectrometry measurement of primary coolant of generation 4 sodium-cooled fast reactor

International Nuclear Information System (INIS)

Coulon, R.

2010-01-01

Sodium-cooled Fast Reactors are under development for the fourth generation of nuclear reactor. Breeders reactors could gives solutions for the need of energy and the preservation of uranium resources. An other purpose is the radioactive wastes production reduction by transmutation and the control of non-proliferation using a closed-cycle. These thesis shows safety and profit advantages that could be obtained by a new generation of gamma spectrometry system for SFR. Now, the high count rate abilities, allow us to study new methods of accurate power measurement and fast clad failure detection. Simulations have been done and an experimental test has been performed at the French Phenix SFR of the CEA Marcoule showing promising results for these new measurements. (author) [fr

Nuclear Energy Division. 2009 Activity report

International Nuclear Information System (INIS)

2009-01-01

After a presentation of the future investment programme of the nuclear energy department at the French national Nuclear Research Center (CEA), this report proposes a description of tomorrow's industrial nuclear systems (back-end of future fuel cycle, fourth generation systems, basic scientific and technological research), describes how current nuclear industrial systems are optimized (front-end and back-end of fuel cycle, second and third generation reactors). It presents the main tools for nuclear development: simulation programme, the Jules Horowitz reactor project, maintenance of specific facilities, research valorisation. It reports the activities related to the clean-up and dismantling in different nuclear sites, presents the activities of CEA's nuclear research centres (Saclay, Cadarache, Marcoule), briefly presents the transverse material programme, recalls some events, and gives some key figures

Simulated HLLW compositions for cold test of waste management development

International Nuclear Information System (INIS)

Banba, Tsunetaka; Kimura, Hideo; Kamizono, Hiroshi; Tashiro, Shingo

1982-07-01

Three grades of simulated high-level liquid waste (HLLW)-JW-A, JW-B, and JW-C - were proposed to be used respectively according to stages of various cold tests for safety assessment of HLW management. The composition of HLLW was estimated taking into account the spectrum of fission products and actinides, waste volume, corrosion products, and chemical additives. One of conditions, the spectrum of fission products and actinides of LWR spent fuels, was calculated by DCHAIN-code. Fuel burn-up of 28,000 MWD/tUO 2 and 33,000 MWD/tUO 2 were adopted as normal and maximum values of Japanese LWR power plants. The other conditions were estimated using the data obtained at Marcoule plant in France. (author)

Role of surfactants and/or polymers on the properties of new gels for decontaminating a radioactive surface; Role des molecules tensioactives et/ou des polymeres sur les proprietes de nouveaux gels pour decontaminer une surface radioactive

Energy Technology Data Exchange (ETDEWEB)

Bousquet, C. [Cogema 30 - Marcoule (France)]|[Montpellier-2 Univ., 34 (France)]|[CEA Valrho, Lab. des Procedes Avances de Decontamination (LPAD), 30 - Marcoule (France)

2006-07-01

In the framework of the dismantling and drainage of nuclear facilities, the LPAD (Marcoule) develops new decontamination processes such as 'suckable' gels. The principle of the 'suckable' gels process consists in pulverizing a gel on a vertical, horizontal or elbow surface. During its contact time with the wall, the gel corrodes the surface on its first microns. The gel dries, fractures and forms dried solid residues. These residues have fixed the contamination and will be easily removed of the surface by brushing and/or sucking-up. This new process uses few matter and do not require rinsing (no liquid effluent). With this process, it is then possible to reduce the volume of wastes produced during the decontamination step. (O.M.)

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.)

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.

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)

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.)

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

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

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

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.)

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.

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

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

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

Solutions to criticality problems in a plutonium extraction plant; Solutions apportees aux problemes de criticite d'une usine d'extraction du plutonium

Energy Technology Data Exchange (ETDEWEB)

Jouannaud, C; Rodier, J; Fruchard, Y; Peyresblanques, H; Papault, C; Tabardel-Brian, R [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule, service d' extraction du plutonium, service de protection contre les radiations et d' assainissement radioactif

1968-08-01

There are two aspects to nuclear criticality safety: prevention of criticality and protection against the consequences of a possible accident: this report considers these two aspects in the case of the Marcoule Plutonium Extraction Plant. After briefly recalling the various techniques used for avoiding criticality (mass, geometry, concentration, poisoning), the authors describe their application in the plant and show in particular that, a rational use of a favorable geometry is a factor both for security and from an economic point of view. The authors then describe the inside organisation which makes it possible to obtain the necessary intrinsic safety standard right from the advance project stage, and to control the workshop safety during the operation of the plant. The second part of the report deals with the system of protection against the consequences of a possible accident: definition of a typical accident, fixing of the boundaries of a critical zone, safety alarm device, individual and collective dosimetry, evacuation plan and safety instructions. (authors) [French] La securite vis-a-vis des risques de criticite revet deux aspects: la prevention de la criticite et la protection contre les consequences d'un accident eventuel: le present rapport developpe ces deux aspects dans le cas de l'Usine d'Extraction du Plutonium de Marcoule. Apres avoir rappele les differentes techniques de prevention de la criticite (masse, geometrie, concentration, empoisonnement), les auteurs decrivent leur application a l'Usine et montrent notamment que l'utilisation rationnelle de la geometrie favorable est un double facteur de securite et d'economie. Les auteurs decrivent ensuite l'organisation interieure qui permet de realiser la securite intrinseque des le stade d'un avant projet et de controler la securite des ateliers au cours de la vie de l'Usine. La deuxieme partie du rapport est consacree au systeme de protection contre les consequences d'un accident eventuel: definition d

Study of radioactivity diffusion for bitumen-coated blocks produced by an industrial coating plant; Etude de la diffusion de la radioactivite de blocs d'enrobes bitumineux en provenance d'un atelier d'enrobage industriel

Energy Technology Data Exchange (ETDEWEB)

Rodier, J; Lefillatre, G [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

1969-07-01

The solidification by bitumen of chemical coprecipitation sludges from the Marcoule waste treatment station has been studied in the laboratory and has led to the construction of an industrial coating plant. The quality of the coated material obtained has been controlled by the lixiviation test carried out with ordinary water and with sea-water on 45 ml laboratory samples and on industrial coated blocks of 150 litres. Tests on blocks of such a size have necessitated the installation of three special tanks. Two, each of 2000 litres capacity, contain ordinary and sea-water which was continuously recycled at a rate of 2.5 cm/hr and renewed periodically. In the third tank having a capacity of 11000 litres, the coated block was buried in earth and sprinkled with ordinary water with a view to studying the migration of radioelements in soil. The results of these tests confirm those obtained during the laboratory experiments. (authors) [French] La solidification par le bitume des boues de coprecipitation chimique de la station de traitement des effluents du Centre de Marcoule, etudiee en laboratoire, a conduit a la realisation d'une installation industrielle d'enrobage. La qualite de l'enrobe obtenu a ete controlee par le test de lixiviation qui a ete effectue en eau ordinaire et en eau de mer sur des echantillons de laboratoire de 45 ml et sur des blocs d'enrobe industriel de 150 litres. L'experimentation sur des blocs de telles dimensions a necessite l'installation de 3 cuves speciales. Deux, d'une capacite de 2000 litres, contiennent de l'eau ordinaire et de l'eau de mer recyclees en permanence a une vitesse de 2.5 cm/h et renouvelees periodiquement. Dans la 3eme cuve d'une capacite de 11000 litres, le bloc d'enrobe a ete enfoui dans de la terre et asperge d'eau ordinaire afin d'etudier la migration des radioelements dans le sol. Les resultats de ces essais confirment ceux obtenus au cours des tests de laboratoire. (auteurs)

Nuclear reactor (1960)

International Nuclear Information System (INIS)

Maillard, M.L.

1960-01-01

The first French plutonium-making reactors G1, G2 and G3 built at Marcoule research center are linked to a power plant. The G1 electrical output does not offset the energy needed for operating this reactor. On the contrary, reactors G2 and G3 will each generate a net power of 25 to 30 MW, which will go into the EDF grid. This power is relatively small, but the information obtained from operation is great and will be helpful for starting up the power reactor EDF1, EDF2 and EDF3. The paper describes how, previous to any starting-up operation, the tests performed, especially those concerned with the power plant and the pressure vessel, have helped to bring the commissioning date closer. (author) [fr

Waste management in reprocessing plants

International Nuclear Information System (INIS)

Mortreuil, M.

1982-01-01

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

Study of the mineral absorbent precipitation phenomena used in decontamination of radioactive effluents; Etude des phenomenes de precipitation d'adsorbants mineraux utilises en decontamination d'effluents radioactifs

Energy Technology Data Exchange (ETDEWEB)

Pacary, V. [Institut National Polytechnique, 54 - Nancy (France)]|[CEA Valrho, Lab. des Procedes Avances de Decontamination (LPAD), 30 - Marcoule (France)

2006-07-01

The aim of this work is to determine the optimal conditions of the reactor running (feed rate, reagents concentration..) for which the effluent decontamination is the most efficient. Thus will be in particular studied the coprecipitation mechanisms and the influence of the physico-chemical conditions on these mechanisms. On the other hand, the processes occurred in the coprecipitation phenomenon being complex, the elaboration of a model is indispensable to guide and interpret the experimental work. This model will be based on the knowledge developed in precipitation and will allow to simulate the decontamination in two reactors types: the reactor fed in continuous in reagents and in effluents as the Hague's ones and the closed reactor fed only in reagents as the Marcoule's ones. (O.M.)

Microspheres Prepared by Internal Gelation - Understanding of HMTA and urea reactions

International Nuclear Information System (INIS)

Robisson, A.C.; Dauby, J.; Grandjean, S.; Benay, G.; Modolo, G.

2008-01-01

Homogenous microspheres of minor actinide (hereafter MA) compounds are of interest to prevent the generation and dispersal of MA powder at the early stages of the fabrication of targets for homogenous or heterogeneous transmutation. Sol-gel routes are being investigated as one of the possible solutions for producing these homogeneous starting materials. This document describes internal gelation basis experiments led at Cea Marcoule and at the Institute for Energy Research Juelich dedicated to the synthesis of mixed compounds including MAs, particularly mixed actinide-actinide or mixed actinide-inert element compounds. Parameter studies were undertaken by simulating cations in order to scan a larger range of conditions and to optimise more easily gelation conditions. With these experiments, key parameters were put forward and the main successive reactions taking care during gelation were understood. (authors)

Thermal denitrification of evaporators concentrates in reactor with fluidized bed

International Nuclear Information System (INIS)

Brugnot, C.

1993-11-01

As part of the treatments of liquid wastes coming from the Marcoule reprocessing plant, the study of a thermal denitrification process for evaporator concentrates has been chosen by the CEA/CEN Cadarache: the fluidized-bed calcination. This work presents the study of a calcination pilot-plant for wastes with a very high sodium nitrate content. After a reactional analysis carried out in a thermobalance on samples which are representative of the fluidized-bed compounds, the perfecting of many of the plant parameters - such as the solution injection system - was carried out on a scale-model at first. Then, it was verified on the pilot-plant, and some experiments have been carried out. A mathematical model for the particle growth inside the fluidized-bed is proposed. (author). 179 refs., 65 figs., 23 tabs

Nuclear: a world without worker?

International Nuclear Information System (INIS)

Fournier, Pierre; Maziere, M.

2014-01-01

After having recalled some characteristics of the electro-nuclear sector in terms of employment (direct and indirect jobs, average age, number of persons controlled on the radiological level, exposure with respect to work location), the author outlines that workers of this sector are seldom evoked whereas investments, incidents and accidents are generally the main evoked and commented topics. He proposes some explanations about this image of the nuclear sector. He reports an incident which occurred in Marcoule and outlines how a set of imperfectly managed events resulted in this incident. He also outlines the importance of the role of workers and the difficulty to make the right choice in such situations. As a conclusion, the author draws some lessons, and particularly outlines that the commitment of workers should be put forward

ATALANTE, innovation for the nuclear fuel cycle

International Nuclear Information System (INIS)

Anon.

2016-01-01

At Marcoule (France) CEA has been operating a facility called ATALANTE since the beginning of the eighties and dedicated to research on the nuclear fuel cycle. 4 lines of research are pursued: a technical support for nuclear industry, advanced nuclear fuel cycles, the recycling of minor actinides, and the vitrification of high level radioactive wastes. ATALANTE facility consists of 17 laboratories working on 250 glove boxes and 11 shielded hot cells. The latter allow the handling of highly gamma emitting materials through 59 workstations equipped with remote manipulatory arms, while the former allow the handling of contaminating (but low irradiating) materials like most actinides. In 2013 ATALANTE was rewarded the 'Nuclear historic landmark' by the American Nuclear Society that awards facilities that have led to major advances in scientific knowledge

The IRIS Incinerator at Cea-Valduc assessment after more than one ton and a half of active waste incineration

International Nuclear Information System (INIS)

Chateauvieux, H.; Guiberteau, P.; Longuet, T.; Lemort, F.; Lannaud, J.; Lorich, M.; Medzadourian, M.

2000-01-01

During the operation of its facilities, the Valduc Research Center produces alpha-contaminated solid waste. An incineration facility has been built to treat the most contaminated combustible waste. The process selected for waste incineration is the IRIS process, which was developed by the CEA at the Marcoule Nuclear Research Center. The Valduc Center asked SGN to build the incineration facility. The facility was commissioned in late 1996, and inactive waste incineration campaigns were run during more than 2,500 hours in 1997-1998. Active commissioning of the facility was performed in March 1999. Since then five campaigns with active waste and a complete plutonium cleaning session have been carried out, the results of which are given in the paper. The Valduc incinerator is the first industrial active application of the IRIS process. (authors)

S.T.M.I.: Several years of experience in nuclear plant dismantling

International Nuclear Information System (INIS)

Moreau, J.C.

1986-01-01

Since 1977, when STMI performed its first dismantling operation, the Company appreciably improved in that field through important operations: the dismantling of the calciothermy and fluoration metal Pu preparation facility, in La Hague reprocessing plant, the dismantling of the slag treatment chain, associated to calciothermy and fluoration processes, in La Hague reprocessing plant, the cleaning of EL4 cell in Marcoule. To perform these operations, STMI's operating teams, on top of decontamination and dismantling technologies, strived to improve handling and transportation technologies, and to nuclearize many equipments. In order to increase its technical efficiency, STMI signed a cooperation agreement with TECHNICATOME company. Therefore, the union between the operational know-hows of STMI and the design experience of TECHNICATOME allow the needs of any customs facing a dismantling case to be satisfied [fr

STMI: several years of experience in nuclear plant dismantling

International Nuclear Information System (INIS)

Moreau, J.C.

1985-01-01

Since 1977, when STMI performed its first dismantling operation, the Company appreciably improved in that field through important operations: the dismantling of the calciothermy and fluoration metal Pu preparation facility, in La Hague reprocessing plant; the dismantling of the slag treatment chain, associated to calciothermy and fluoration processes, in La Hague reprocessing plant; and the cleaning of EL4 cell in Marcoule. To perform these operations, STMI's operating teams, on top of decontamination and dismantling technologies, strived to improve handling and transportation technologies, and to nuclearize many equipments. In order to increase its technical efficiency, STMI signed a cooperation agreement with FRAMATOME company. Therefore, the union between the operational know-hows of STMI and the design experience of TECHNICATOME allow the needs of any customs facing a dismantling case to be satisfied [fr

Fast Track Characterization of Highly Radioactive Waste Pits Combining Off-the-Shelf Robotics with Innovative Investigation Protocols

International Nuclear Information System (INIS)

Chabeuf, Jean-Michel; Boya, Didier

2008-01-01

The investigation and characterization of radioactive waste pits and effluent storage tanks represents a substantial and challenging step in the overall decommissioning programme launched by AREVA NC in 1998 on the site of Marcoule on behalf of the French Atomic Energy commission. Physical ,radiological and regulatory constraints, combined with a tight schedule, have lead our teams to use proven conventional instrumentation and robotics in innovative configurations . One such investigation, conducted on a particularly challenging radioactive effluent storage pit, is described below. The 'H' pit is a stainless steel clad concrete cavity, located in the second basement of the de-cladding building of Marcoule site. It was used for forty years as buffer storage for high activity effluents and has a length of 5 meters, a width of 3 meters , a height of 2.5 meters, and is topped by lead plates over 5 cm thick and The bottom of the cavity is covered with a layer of mud containing mainly graphite, diatoms and resins. The mud level ranges from about 20 centimeters to over 50 centimeters. The overall mud volume is around 2.4 cubic meters. Ambient dose rates above the lead plates exceed 10 mSv/h. The main purpose of our investigation was to characterize the muds for future recovery and conditioning prior to decontaminating the pit. The history of the pit together with the varying mud altimetry lead us to believe that sedimentation had probably occurred throughout the years. We thus decided to combine dose rate measurements using IF104 probes, gamma spectroscopy with CdTe probes and sample collections at different depths to ensure the representativeness and full characterization of the muds. Poor access, ambient dose rates have lead us to conceive a robotic arm, mounted on an shaft which can be modified to fit a wide range of pits and tanks. Custom built robotic tools with maximum manoeuvrability generally involve costs and delays far exceeding our purposes. SIT, a French

Search for plutonium salt deposits in the plutonium extraction batteries of the Marcoule plant (1963)

International Nuclear Information System (INIS)

Bouzigues, H.; Reneaud, J.M.

1963-01-01

This report describes a method and a special apparatus making it possible to detach the insoluble plutonium salt deposits in the extraction chain of an irradiated fuel treatment plant. The process chosen allows the detection, in the extraction batteries or in the highly active chemical engineering equipment, of plutonium quantities of a few grains. After four years operation it has been impossible to detect measurable quantities of plutonium in any part of the extraction chain. The results have been confirmed by visual examinations carried out with a specially constructed endoscope. (authors) [fr

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)

Search for plutonium salt deposits in the plutonium extraction batteries of the Marcoule plant (1963); Recherche de depots de sels de plutonium dans les batteries d'extraction du plutonium de l'usine de Marcoule (1963)

Energy Technology Data Exchange (ETDEWEB)

Bouzigues, H; Reneaud, J M [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

1963-07-01

This report describes a method and a special apparatus making it possible to detach the insoluble plutonium salt deposits in the extraction chain of an irradiated fuel treatment plant. The process chosen allows the detection, in the extraction batteries or in the highly active chemical engineering equipment, of plutonium quantities of a few grains. After four years operation it has been impossible to detect measurable quantities of plutonium in any part of the extraction chain. The results have been confirmed by visual examinations carried out with a specially constructed endoscope. (authors) [French] Ce rapport decrit une methode et un montage special permettant de detacher les accumulations de sels de plutonium insolubles dans les chaines d'extraction d'une usine de traitement de combustible irradie. Le procede retenu permet de reperer, dans des batteries d'extraction ou dans l'appareillage de genie chimique fortement actif, des masses de plutonium de quelques grammes. Apres quatre annees de fonctionnement, il n'a pas ete possible de deceler des quantites ponderables de plutonium en aucun endroit de la chaine d'extraction. Ces resultats ont ete confirmes par les examens visuels effectues a l'aide d'un endoscope concu specialement pour cet usage. (auteurs)

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

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

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)