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

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.)

Reprocessing RTR fuel in the La Hague plants

International Nuclear Information System (INIS)

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

2001-01-01

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

Reprocessing RTR fuel in the La Hague plants

Energy Technology Data Exchange (ETDEWEB)

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

2001-07-01

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

Reprocessing RTR fuel in the La Hague plants

Energy Technology Data Exchange (ETDEWEB)

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

2001-07-01

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

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

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

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

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.)

Advanced Purex process and waste minimization at La Hague

International Nuclear Information System (INIS)

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

1993-01-01

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

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)

CEA R and D contribution to the La Hague extension plant

International Nuclear Information System (INIS)

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

1986-06-01

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

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.)

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

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)

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

La Hague: keep cool

International Nuclear Information System (INIS)

Gaullier, V.

1997-01-01

The study made by OPRI (ionizing radiation protection agency) confirms the results given by Greenpeace concerning the radioactive contamination due to the undersea discharge pipe of La Hague reprocessing plant. It is highlighted that at about 50 meters from the end of the pipe no contamination is perceptible. (A.C.)

Diagnostic aid and maintenance at the La Hague reprocessing plants

International Nuclear Information System (INIS)

Bern, J.B.; Chabert, J.

1989-01-01

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

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

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

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)

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-11-01

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

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-04-15

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

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

International Nuclear Information System (INIS)

Horn, Thomas

2012-01-01

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

Sediments as indicators of artificial radionuclide distribution west of La Hague

International Nuclear Information System (INIS)

Guegueniat, P.; Auffret, J.P.; Ballada, J.

1981-01-01

Four-year investigations of the coastal surface sediments and associated radionuclides in the English Channel show complex distribution patterns around La Hague. Plutonium ratios in the particulate fraction confirm the general understanding gathered from long-term gamma studies - mainly that accumulation of La Hague generated radionuclides is in the Bay of Mont-Saint-Michel and along the Normandy-Brittany Coast. The oil from the Amoco Cadiz accident caused a significant increase in coastal sediment activity of 144 Ce. Experimental studies with plutonium and hydrocarbons indicate that plutonium is more difficult to desorb than 144 Ce. (author)

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

International Nuclear Information System (INIS)

2006-04-01

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

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

International Nuclear Information System (INIS)

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

1991-01-01

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

Epidemiological study around La Hague

International Nuclear Information System (INIS)

1999-01-01

The North Cotentin is in France, the area where have been led until now, the biggest number of epidemiology studies on the effects of ionizing radiations on man, in order to assess the leukemia incidences and other cancer pathologies around nuclear facilities. The North Cotentin concentrates four nuclear installations.The objective of this file is to take stock of the situation in this field. In 1995 and 1998 have been published two sections of an epidemiology study about the incidence of leukemia in North Cotentin (J.F. Viel study for the period 1978-1992, Spira study for 1993-1997). The study of the Professor Spira does not bring to the fore a significant excess of leukemia for the period 1978-1997. The report of the professor Spira advocates several complementary epidemiology studies to precise or complete the data and lighten the causes of leukemia in North Cotentin. The studies of J.F.Viel shows that it does not exist a significant excess of cases in the studied area (25 cases for 22.8 expected cases, so a non significant difference) but notices an aggregate at the limit to be significant in the Beaumont-Hague canton (4 cases for 1.4 expected cases). J.F.Viel puts forward a relationship between the risk increase (of leukemia incidence) and some individual characteristics linked to the way of life of the studied persons: the North Cotentin beaches frequenting by the mothers or the children at least one time by month, the consumption of fish or shellfish having a local origin at least one time by week. This study suggests that it is the radioactivity, on the beaches on in fishes and shellfish that would be at the origin of the additional noticed leukemia. The authorities asked at the beginning of 1997, a scientific commission directed by the Professor Souleau to propose a new epidemiology study on the leukemia risk around La Hague. The report concludes that the leukemia incidence in the North Cotentin is in accordance with the expected incidence (25 observed

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.)

A look inside Cogema

International Nuclear Information System (INIS)

Anon.

1993-01-01

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

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)

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

Energy Technology Data Exchange (ETDEWEB)

Anon.

1996-12-31

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

Radioecological synthesis of the various compartments of La Hague (Cotentin) marine environment

International Nuclear Information System (INIS)

Calmet, D.

1986-03-01

Permits for low level radioactive liquid waste releases by the LA HAGUE (Cotentin, France) fuel reprocessing plant are based on an accurate radioecological study of the marine environment. Since 1967, the monitoring of indicators such as seawater, sediments and marine organisms (Fucus serratus, Laminaria sp., Mytilus sp., ...) have made it possible to create an important environmental data base. A statistical treatment has been used to quantify the spatio-temporal (daily, seasonal, local and regional) variabilities of these indicators from 1975 up to now. It has demonstrated the interest of F. serratus seaweed as bioindicators of radioactivity. Moreover it appears that seawater-soluble radionuclides such as 125 Sb and 137 Cs are monitored through longer distance from the outlet than those bound to particles such as 144 Ce. A study of the sestonic load by satellite images suggested a number of geographical sites of potential accumulation through particle transport, some of which were verified by radioactivity measurements of sediments. However, such accumulation was not confirmed by the particle size distribution at the level of the Cap de LA HAGUE associated with radioactive measurements of seawater. A spectral analysis of biota radioactive levels vs radioactive waste releases showed a time delay of 2 - 4 months for F. serratus and Mytilus sp. collected in the local area of LA HAGUE after either an increase or a decrease of the releases. Modeling of marine currents fields associated with a transfer model can now be used to predict, at small time scales, the radioactivity levels inthe various Cotentin marine compartments from the liquid waste releases [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

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

The safety of the new reprocessing plants of La Hague

International Nuclear Information System (INIS)

Devillers, C.; Dubois, G.

1987-09-01

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

Cogema's transatlantic partnership

International Nuclear Information System (INIS)

McMurphy, M.; Ihde, R.

1991-01-01

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

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)

Tritium waste management on the La Hague AREVA NC site: associated impact and monitoring

International Nuclear Information System (INIS)

Devin, P.; Deguette, H.

2009-01-01

The authors propose an analysis of tritium behaviour in the nuclear fuel processed in the AREVA NC plant in La Hague, of its presence in the plant and in its wastes, and of the impact of these wastes and the tritium monitoring in the environment. First, they present the AREVA NC plant and evoke the legal context concerning the waste management. They report and discuss the analysis of the presence and behaviour of tritium in irradiated fuel, of its behaviour during spent fuel processing, the evolution of tritium releases (legal limitations, evolutions since 1992), of measurement of activity in effluents, and discuss a study of possible reductions of tritium releases by La Hague plants (mainly in sea waters). They also report the computational assessment of the dosimetric impact of tritium on neighbouring population. They describe how the presence of tritium in the environment is monitored within the annual radioactivity monitoring programme

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

Energy Technology Data Exchange (ETDEWEB)

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

2001-11-15

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

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

International Nuclear Information System (INIS)

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

2001-11-01

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

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.

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.)

Technetium-99 content in some marine organisms collected near La Hague, France

International Nuclear Information System (INIS)

Jeanmaire, L.; Patti, F.; Cappellini, L.; Masson, M.; Germain, P.

1981-01-01

Analyses for 99 Tc in some marine biological samples taken near the outlet of the low level radioactive effluent pipeline of the nuclear reprocessing plant of La Hague, France, gave positive results. From 500 to 3500 pCi kg -1 wet weight of 99 Tc were observed in brown algae; Fucus sp. appeared to be a good indicator of this long-lived radionuclide in a marine environment. (author)

Particular intervention plan of the Areva La Hague facility - 2012 edition

International Nuclear Information System (INIS)

2012-01-01

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Areva NC La Hague fuel reprocessing plant (located on the territories of Beaumont-Hague, Digulleville, Herqueville, Jobourg and Omonville-la-Petite towns, Manche, France) which comprises the totally decommissioned UP2 400 unit, and the UP2 800 production unit still in operation

Solid waste processing and compaction in the AD2 workshop of the new La Hague reprocessing plant

International Nuclear Information System (INIS)

Singer, B.M.; Vigreux, B.

1987-01-01

The AD2 workshop of the new spent nuclear fuel reprocessing plant at La Hague in France will process and package dry solid wastes. The waste packages will be segregated according to their activity levels and stored at temporary on-site facilities. Full commissioning is scheduled for end-1988. However, operation of the TO dry spent field unloading and receiving unit at La Hague required early availability of some waste processing functions and part of the AD2 workshop was commissioned towards the end of 1986. The new La Hague plant is organized into four main zones: - zone 1 is an uncontrolled area with no permanent contamination and zero risk of accidental contamination, - zone 2 is a controlled are with no permanent contamination and low risk of accidental minor contamination, - zone 3 is a controlled area with no permanent contamination but a risk of minor contamination due to various incidents, - zone 4 is a controlled area with permanent contamination. The AD2 workshop will handle all dry solid wastes from zones 2, 3 and 4. It will also: characterize the resulting waste packages (contents, mass, alpha, beta and gamma activity, dose equivalent rate) and check for absence of surface contamination; transfer the packages to temporary on-site storage facilities; store and administer mobile handling tasks and transporters

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.)

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

International Nuclear Information System (INIS)

Alexandre, D.

1986-05-01

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

Radioecological data concerning La Hague marine environment

International Nuclear Information System (INIS)

Ancellin, J.; Bovard, P.

1979-01-01

New radioecological observations have been made in the environment of the La Hague (North-West Cotentin) spent fuel processing plant to supplement earlier studies on the transfer of sea-borne radioactive wastes and on radioactivity levels found in the North-West sector of the Cotentin and some distance away on the channel coasts. Of the radionuclides discharged by the plant, ruthenium-106 and cerium-144 account for most of the artificial γ activity found in living species and sediments. Together with plutonium they tend to disperse less than a radionuclide present in essentially soluble form such as cesium-137. Certain coastal deposits moreover tend to be more pronounced South-West than East-South-East of the discharge point. Finally the radioactivity levels observed and their repercussions on public health show good agreement with the results of the previsional study carried out before the plant was started up [fr

Zirconium-made equipment for the new La Hague reprocessing plants

International Nuclear Information System (INIS)

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

1991-01-01

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

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.)

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.)

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)

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)

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.)

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.)

The R7/T7 vitrification at La Hague: 10 years of operation

International Nuclear Information System (INIS)

Masson, H.; Desvaux, J.L.; Pluche, E.; Jouan, A.

2001-01-01

Vitrification of high level wastes from reprocessing of spent nuclear fuels has been carried out at La Hague on an industrial scale for ten years. This paper presents an historical overview of the facilities, and describes the facilities and their operations, startup performance, facility upgrading that has been done, and process control functions. The paper concludes that the technology for vitrification of high level wastes is mature and has been mastered. (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.)

Nuclear energy: democracy flouted. La Hague in the center of the debate

International Nuclear Information System (INIS)

Anger, D.

2002-01-01

In this book, the author denounces the collusion between the French government and the nuclear lobby and the dark side of the implementation of the nuclear program in France without any real democratic debate with the citizens. The history of the La Hague radioactive waste facility is taken as an example. The author recommends the development of alternative and decentralized energy sources. He considers also that the main questions generated by the nuclear industry (radioactive wastes, spent fuels reprocessing, health hazards, environmental impact, terror threat..) are still unanswered since 30 years. (J.S.)

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.)

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.

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

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.)

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)

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

Science.gov (United States)

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

2014-11-01

The aim of this work was to study the near-field dispersion of (85)Kr around the nuclear fuel reprocessing plant at La Hague (AREVA NC La Hague - France) under stable meteorological conditions. Twenty-two (85)Kr night-time experimental campaigns were carried out at distances of up to 4 km from the release source. Although the operational Gaussian models predict for these meteorological conditions a distance to plume touchdown of several kilometers, we almost systematically observed a marked ground signal at distances of 0.5-4 km. The calculated atmospheric transfer coefficients (ATC) show values (1) higher than those observed under neutral conditions, (2) much higher than those proposed by the operational models, and (3) higher than those used in the impact assessments. Copyright © 2014 Elsevier Ltd. All rights reserved.

Development of a computer system at La Hague center

International Nuclear Information System (INIS)

Mimaud, Robert; Malet, Georges; Ollivier, Francis; Fabre, J.-C.; Valois, Philippe; Desgranges, Patrick; Anfossi, Gilbert; Gentizon, Michel; Serpollet, Roger.

1977-01-01

The U.P.2 plant, built at La Hague Center is intended mainly for the reprocessing of spent fuels coming from (as metal) graphite-gas reactors and (as oxide) light-water, heavy-water and breeder reactors. In each of the five large nuclear units the digital processing of measurements was dealt with until 1974 by CAE 3030 data processors. During the period 1974-1975 a modern industrial computer system was set up. This system, equipped with T 2000/20 material from the Telemecanique company, consists of five measurement acquisition devices (for a total of 1500 lines processed) and two central processing units (CPU). The connection of these two PCU (Hardware and Software) enables an automatic connection of the system either on the first CPU or on the second one. The system covers, at present, data processing, threshold monitoring, alarm systems, display devices, periodical listing, and specific calculations concerning the process (balances etc), and at a later stage, an automatic control of certain units of the Process [fr

A world first. Industrial operation of computer-aided master-slave manipulator at the La Hague recycling plant

International Nuclear Information System (INIS)

Brueziere, Jerome; Thro, Jean Francois; Brudieu, Marie-Anne; Piolain, Gerard; Geffard, Franck; Garrec, Philippe; Measson, Yvan; Coudray, Alain; Lelann, Eric

2011-01-01

Since the beginning of industrial nuclear plants like recycling, mechanical master-slave manipulators have been widely used for operation and maintenance in hot cells, in conjunction with shielding windows. In the La Hague plant for instance, all hot cells where maintenance is or could be required are fitted with shielding windows and through-wall telescopic master-slave manipulators. This well mastered solution, if used by highly skilled workers, has demonstrated its capability to perform all the maintenance tasks required, as long as equipment and tools inside the cell were designed accordingly. However, this technology has also shown significant limitations in terms of capacity, flexibility, efficiency and reliability. In order to improve those characteristics, AREVA and CEA have developed together a new technology: computer-aided master-slave manipulators. By replacing the traditional mechanical link, between the 'slave arm' in the cell and the 'master arm', with motors, sensors and electronics, this new tool improves load capacity and provides added flexibility and efficiency, while protecting the slave arm from overload and therefore improving reliability. In addition, this new device was developed to be fully compatible with current La Hague configuration. After developing and testing this solution in realistic but inactive environment, by performing all kinds of operation and maintenance activities with trained workers, the first generation tool was improved by incorporating feed-back and suggestions from operators. Second generation system was then developed, and first introduced in 2010 in an active cell of the La Hague plant, namely a vitrification cell. After a few months in operation, feedback from manufacturing staff was so positive that implementation of several new arms was decided for 2011. This paper will describe how this development benefited from the existing know-how and component library jointly developed by AREVA and CEA, as well as the main

Elaboration and implementation of automatized management system of operating mode at La Hague reprocessing plant

International Nuclear Information System (INIS)

Charon, S.; Lepine, C.; Dumetz, A.; Nicolet, J.L.

1986-01-01

This paper presents the documentation system for operators conducting the new units for fuel reprocessing at La Hague plant. The aim of this system, called COGEMO, is to improve man-machine system reliability, by presenting in real time to operators the information required for efficiently operating the installation in any situation (start up), transients, incidents). Qualification is developed in two shops (a mechanical and a chemical unit) and will be extended to other units when they will be put into service [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.)

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)

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)

TAO2000 V2 computer-assisted force feedback tele-manipulators used as maintenance and production tools at the AREVA NC-La Hague fuel recycling plant

International Nuclear Information System (INIS)

Geffard, Franck; Garrec, Philippe; Piolain, Gerard; Brudieu, Marie-Anne; Thro, Jean-Francois; Coudray, Alain; Lelann, Eric

2012-01-01

During a 15-year joint research program, French Atomic Energy Agency Interactive Robotics Laboratory (CEA LIST) and AREVA have developed several remote operation devices, also called tele-robots. Some of them are now commonly used for maintenance operations at the AREVA NC (Nuclear Cycle) La Hague reprocessing plant. Since the first maintenance operation in 2005, several other successful interventions have been realized using the industrial MA23/RX170 tele-manipulation system. Moreover, since 2010, the through-the-wall tele-robot named MT200 TAO based on the slave arm of the MSM MT200 (La Calhene TM ), has been evaluated in an active production cell at the AREVA NC La Hague fuel recycling plant. Although these evaluations are ongoing, the positive results obtained have led to an update and industrialization program. All these developments are based on the same generic control platform, called TAO2000 V2. TAO2000 V2 is the second release of the CEA LIST core software platform dedicated to computer aided force-feedback tele-operation (TAO is the French acronym for computer aided tele-operation). This paper presents all these developments resulting from the joint research program CEA LIST/AREVA. The TAO2000 V2 controller is first detailed, and then two maintenance operations using the industrial robot RX170 are presented: the removal of the nuclear fuel dissolver wheel rollers and the cleanup of the dissolver wheel inter-bucket spaces. Finally, the new MT200 TAO system and its evaluations at the AREVA NC La Hague facilities are discussed. (authors)

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.)

Preliminary measures of tritium content in the Hague (Cotentin) area

International Nuclear Information System (INIS)

Umezu, T.

1971-01-01

Tritium content of about thirty samples (seawater, algae and rainwater) taken during April-July 1973 in La Hague (Cotentin) area was determined with a liquid scintillation detector after electrolytic enrichment. Tritium content was 15 to 130 tritium units not much higher than concentration generally observed in environment nowadays [fr

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.)

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.

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)

Bewijslastverdeling onder de Hague (Visby) Rules

NARCIS (Netherlands)

Margetson, N.J.

2009-01-01

Er bestaat geen heersende leer ten aanzien van de bewijslastverdeling onder de Hague Rules en de Hague Visby Rules. In dit artikel worden verschillende visies die naast elkaar bestaan besproken. De auteur concludeert dat een algemene regel van bewijslastverdeling niet bestaat. De bewijslast zal

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)

Safety of spent fuel elements storage under water at La Hague facility

International Nuclear Information System (INIS)

Guezenec, J.Y.

1990-12-01

Awaiting for a decision about radioactive waste repository, the spent fuel elements are stored in the storage pools at the La Hague facility. The water in the pools is permanently cooled and purified to maintain the temperature, radioactivity and chemical pollution under preset limits. The first safety problem is concerned with the spent fuel transport casks. Opening of the casks is done under water in a number of facilities. The most recent approach is done by the company To, which established dry manipulation which enables to minimise the risk of possible cask failures as well as external contamination of cooling fins of the casks. Another general safety related problem is related to criticality risk caused by possible cooling failures or by external events like earthquakes. Special probability limit is set up for seismic events to be less than 10 -7 /year. Equally, risk of fuel assembly failures due to possible chocs and possibility of defects in pool isolation are taken into account [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

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.)

Four years of experience with the use of calculated isotopic correlations in establishing input balances at the La Hague plant

International Nuclear Information System (INIS)

Aries, M.; Patigny, P.; Bouchard, J.; Giacometti, A.; Girieud, R.

1983-01-01

For more than four years the La Hague reprocessing plant has been using calculated isotopic correlations to establish and check its input balances. The masses of uranium and plutonium entering the plant are determined by the gravimetric balance method, which utilizes the burnup obtained by calculated isotopic correlation as well as the Pu/U ratio measured at the dissolver after cross-checking with the values obtained by correlation. Further, a verification of all the parameters needed to establish these balances - whether physical or chemical in origin - is carried out systematically by means of internal coherence constants which make it possible to detect any anomalies in the dissolution data. The calculated isotopic correlations were evaluated when the analyses of numerous representative samples of irradiated fuel and experimental results of separated isotopic irradiation in water reactor spectra had been interpreted. The accuracy achieved was improved by allowing in the neutron calculations for effects inherent in the first reactor core and by selecting a set of calculation functions which attenuates (by compensation effects) the various perturbations in the irradiation history. The results obtained at La Hague with calculated isotopic correlations on nearly 600 t of reprocessed UO 2 , because of their large number and above all their high quality, suggest that it be proposed extending the method to other reprocessing plants. This could be done by the operator himself or by national or international control bodies within the framework of a safeguards arrangement. (author)

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1998-07-01

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

Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2014

International Nuclear Information System (INIS)

2013-01-01

Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2014, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2013

International Nuclear Information System (INIS)

2014-01-01

Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2013, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

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.)

Complementary safety assessment assessment of nuclear facilities - La Hague plant - AREVA

International Nuclear Information System (INIS)

2011-01-01

This complementary safety assessment analyses the robustness of La Hague plant to extreme situations such as those that led to the Fukushima accident. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site; 3) featuring the activities and installations; 4) accidental sequences 5) protection from the earthquake; 6) protection from the flood; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This study shows a globally good robustness of the plant for the considered risks and, in the case of a severe accident, specified remedial actions can be brought into play by the staff to secure the installations. (A.C.)

The reproduction of sea birds of La Hague and of the Nez-de-Jobourg: The search for reasons of decline (Manche)

International Nuclear Information System (INIS)

James, Jean-Baptiste

2001-11-01

Since 1965, the site of the Nez-de-Jobourg, in the Manche district and at the vicinity of the La Hague plant, has been a site of ornithological follow-up, notably because it harbours different population of nesting sea birds. Since 1990, it has been noticed that the population of European shags has been keeping on decreasing, with abnormally low birth rate, while the European herring gull has totally disappeared. If the relationship between this decline and the releases of the La Hague nuclear waste processing plant is easily and quickly suspected, other reasons are also plausible. The authors report a study of this decline and an investigation of its possible origins. After a presentation of the site, of its status regarding hunting and specie protection, and a presentation of other close sites (small islands, bay), the report addresses the case of the European shag. It gives information on its biology, characteristics, location and population, reproduction sites and nesting cycle. It presents the method adopted to test the various hypotheses of origin of the noticed decline: contamination by radioactive materials or by chemical substances, problems of disturbance by fishers, tourists or others, problems of predation, parasitism or lack of food resources. Samplings have been performed within the studied site and also within reference sites located some miles away. Based on data and observations, hypotheses are then discussed. An analytical report of measurement of artificial radio-elements performed by gamma spectrometry is provided

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.)

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

Product quality follow-up for the start of an industrial plant, e.g.: The waste station No 3 at La Hague

International Nuclear Information System (INIS)

Saas, A.; Vidal, H.; Alvy, J.C.; Boudry, J.C.; Bouin, R.

1990-01-01

During the start-up of the plant for waste treatment and mud coating in bitumen (waste station No 3 La Hague), the Characterization and Estimate of Containments and Analyses Service performed several different controls and tests to verify: whether the industrial plant was operating according to the defined procedure, whether the coated products obtained were in line with provisional specifications, whether the operational sector of the plant ensured the final quality of the coated product. The main results of these measurements and tests are presented in this paper. (orig./DG)

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

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

International Nuclear Information System (INIS)

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

1986-09-01

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

Information report on nuclear safety and radiation protection of the La Hague AREVA site- Issue 2012

International Nuclear Information System (INIS)

2013-06-01

Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basis nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2012, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

Information report of AREVA La Hague site, written in compliance with article L. 125-15 of the French environment code - 2015 Edition

International Nuclear Information System (INIS)

2016-01-01

Published in compliance with the French code of the environment, this report presents, first, the Areva La Hague site with its facilities and activities in relation with spent fuel reprocessing and radioactive waste management. Then, it takes stock of the dispositions implemented for the limitation and prevention of risks and summarizes the events declared in 2015. Next, it presents the management of the site effluents and wastes and the environmental monitoring. Finally, the actions of public information are presented. The recommendations of the Health and safety Committee are included in appendix

Seance of the 11. december 2002 of the special and permanent commission of information nearby the establishment of La Hague. Audition de Mycle Schneider, Director of Ise-Paris; Seance du 11 decembre 2002 de la Commission speciale et permanente d'information aupres de l'etablissement de La Hague. Audition de Mycle Schneider, Directeur de WISE-Paris

Energy Technology Data Exchange (ETDEWEB)

Schneider, M

2002-07-01

The intervention of Mycle Schneider leaned on numerous updated transparencies (graphs, illustrations) gathered according to the principal tackled themes. The tables and graphs devoted to the doses issued from releases of reprocessing plants show a revised version of collective doses estimations. The different subjects are: the world electronuclear park, the situation of nuclear matters, the exploitation of La Hague facility, the release in environment of reprocessing plants, the individual land collective radiation doses induced by releases, the risk of a plane fall and other safety problems. (N.C.)

The Hague Judgments Convention

DEFF Research Database (Denmark)

Nielsen, Peter Arnt

2011-01-01

The Hague Judgments Convention of 2005 is the first global convention on international jurisdiction and recognition and enforcement of judgments in civil and commercial matters. The author explains the political and legal background of the Convention, its content and certain crucial issues during...

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

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

Hot air in Kyoto, cold air in The Hague

DEFF Research Database (Denmark)

Steiner, Urs; Svendsen, Gert Tinggaard

2001-01-01

Summary: Why did the climate negotiations in The Hague fail? Our contribution is to argue that the conflict between the European Union (EU) and the United States (US) stems mainly from disagreement on the cost issue. We argue that three main concerns promoted by the EU in The Hague. First, a 50...

Hot air in Kyoto, cold air in The Hague

DEFF Research Database (Denmark)

Brandt, Urs Steiner; Svendsen, Gert Tinggaard

2002-01-01

Why did the climate negotiations in The Hague fail? Our contribution is to argue that the conflict between the European Union (EU) and the United States (US) stems mainly from disagreement on the cost issue. We argue that three main concerns promoted by the EU in The Hague. First, a 50% national...

Cement waste form development for ion-exchange resins and fine particles ILW of AREVA La Hague Reprocessing Plant

International Nuclear Information System (INIS)

Chartier, D.; Sanchez-Canet, J.; Avril, D.; Roussel, C.; Pineau, J.N.

2015-01-01

Wastes have been temporarily stored in dedicated silos in La Hague reprocessing plant. These wastes are to be retrieved in the near future and to be conditioned for final disposal. Some of these wastes are supposed to be encapsulated in cement matrix and, depending on the chemical composition of the waste streams, several projects are presently ongoing. The present article aims to focus on one amongst these cement encapsulation relevant projects, namely the conditioning of a mix of spent ion-exchange resins (from filtration of pool) and fine particles (insoluble fission products from spent fuel dissolution and Zircaloy and stainless steel fines from cladding shearing). The project, aims to retrieve these wastes from a silo, separate the resins and fine particles from the other waste (hulls and end pieces), in order to encapsulate the intermediate-level fines and resins in a cement matrix. The waste forms will be produced in AREVA's La Hague reprocessing plant, prior to being sent as intermediate-level waste to a long-term repository. The cement formulation developments were initially carried out at a small scale at C.E.A. Marcoule on surrogate wastes. One of the main issues that were considered was the chemical compatibility between waste and cement matrix. Indeed, swelling phenomena are sometimes reported when ion exchange resins are embedded in cement matrixes such as Portland cement. This kind of destructive phenomenon has been prevented by the use of cement containing a high amount of ground granulated blast furnace slag. The impact of the variability of ionic charge of the resins on the waste form's properties has also been addressed in order to comfort the results obtained on the reference ionic charge of resins NaNO 3 . Once the results obtained were satisfactory, intermediate scale and full scale tests were performed by AREVA. These tests have focused on adjusting the mixing process and controlling the thermal properties of the mix during setting

78 FR 77621 - Forum To Discuss Proposed Changes To Implement the Hague Agreement Concerning International...

Science.gov (United States)

2013-12-24

... implement the PLTIA. Additional information concerning the proposed rules and the Hague Agreement, and any... [Docket No. PTO-C-2013-0059] Forum To Discuss Proposed Changes To Implement the Hague Agreement Concerning... Geneva Act of the Hague Agreement Concerning International Registration of Industrial Designs (``Hague...

Engaging Local Stakeholders on Technical Issues: Test Case at the La Hague Reprocessing Plant - 59211

International Nuclear Information System (INIS)

Gilli, Ludivine

2012-01-01

In 2009 and 2010, the Institute for Nuclear Safety and Radiation Protection (IRSN) lead a pilot action dealing with the decommissioning of a workshop located on the site of Areva's La Hague fuel-reprocessing plant site in Northwestern France. The purpose of the pilot program was to test ways for IRSN and a few local stakeholders (Non-Governmental Organizations (NGOs) members, local elected officials, etc.) to engage in technical discussions. The discussions were intended to enable the local stakeholders to review the operator's decommissioning application and provide input. The pilot program confirmed there is a definite challenge in successfully opening a meaningful dialogue to discuss technical issues. Three factors influence the extent of the challenge: the knowledge gap between experts and local stakeholders, the conflict between transparency and confidentiality which is inherent with technical topics, and the difficulty for an official expertise institute to hold a dialogue with 'outsiders' during an ongoing reviewing process in which it is participating. The pilot program, given its mixed results, also provided valuable lessons for further improvement of stakeholders' involvement. (authors)

Polyvalent fuel treatment facility (TCP): shearing and dissolution of used fuel at La Hague facility

Energy Technology Data Exchange (ETDEWEB)

Brueziere, J.; Tribout-Maurizi, A.; Durand, L.; Bertrand, N. [Recycling Business Unit, AREVA, 1 place de la coupole, 92084 Paris La defense Cedex (France)

2013-07-01

Although many used nuclear fuel types have already been recycled, recycling plants are generally optimized for Light Water Reactor (LWR) UO{sub x} fuel. Benefits of used fuel recycling are consequently restricted to those fuels, with only limited capacity for the others like LWR MOX, Fast Reactor (FR) MOX or Research and Test Reactor (RTR) fuel. In order to recycle diverse fuel types, an innovative and polyvalent shearing and dissolving cell is planned to be put in operation in about 10 years at AREVA's La Hague recycling plant. This installation, called TCP (French acronym for polyvalent fuel treatment) will benefit from AREVA's industrial feedback, while taking part in the next steps towards a fast reactor fuel cycle development using innovative treatment solutions. Feasibility studies and R/Development trials on dissolution and shearing are currently ongoing. This new installation will allow AREVA to propose new services to its customers, in particular in term of MOX fuel, Research Test Reactors fuel and Fast Reactor fuel treatment. (authors)

Year 2006. GRNC's appreciation of the dose estimates presented in the annual environmental monitoring report of Areva-NC La Hague facility. Forth GRNC viewpoint. Detailed report

International Nuclear Information System (INIS)

2007-01-01

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 Areva NC, 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 2006 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 - a critical analysis of the 2006 source term; a note about the uranium content in liquid effluents; the data transmitted by Areva NC (status of atmospheric effluents, status of liquid effluents at sea, fuel data); the data transmitted by the IRSN - the French institute of radiation protection and nuclear safety (status of the radioactive effluents of Areva La Hague facility); the history of liquid and gaseous effluents between 1966 and 2006; 2 - detailed comparison between model and 2006 measurements; critical analysis of 14 C and tritium data available for the Nord Cotentin and the English Channel area; 3 - detail of the 2006 efficient dose calculations; presentation of the environmental dispersion of tritium and of its effects on living organisms. (J.S.)

Discharges and impacts from la Hague plant: history and recent achievements

International Nuclear Information System (INIS)

Kalimbadjian, J.; Rincel, X.

1998-01-01

Industrial reprocessing at La Hague was started in 1966. During 30 years. the annual rate of production gradually increased, up to more than 1,600 tons. Simultaneously, considerable innovative design and technology was introduced at all steps of the process, including effluent treatment and waste management. The characteristics of reprocessed fuel elements also changed. from low burn-up metallic fuel to high burn-up oxides. Reflecting all those evolutions, the plant discharges to the atmosphere and to the sea have shown significant variations in quantity and in composition. The complete history of liquid and gaseous releases displays a broad spectrum of situations, as to the relative weight of each radionuclide. However, the level of discharge has always remained significantly lower than the authorized limits. whatever radionuclide. Moreover, discharges to the sea have continuously decreased for 10 years, in spite of fast rising rate of production. As to the total radiological impact of discharges. it was permanently maintained well within the acceptable level of 0.15 mSv/year for the reference groups of neighbouring population, as decided for the level of authorizations. Since 1988, several actions have been decided in order to minimize the present and future impacts: improved liquid effluent treatment, extended recycling of liquid effluents towards vitrification, supplementary filtration of gaseous effluents for iodine scavenging. As a result, the plant will be able to maintain the overall impact from all discharges at less than the present acceptable level, in spite of projected wider domain of operations: - modified grades of reprocessed fuel, - decommissioning operations; - treatment of older waste stocks. (author)

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

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)

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)

Year 2006. GRNC's appreciation of the dose estimates presented in the annual environmental monitoring report of Areva-NC La Hague facility. Forth GRNC viewpoint. Detailed report; Annee 2006. Appreciation par le GRNC de l'estimation des doses presentee dans le rapport annuel de surveillance de l'environnement d'Areva-NC La Hague. Quatrieme avis du GRNC. Rapport detaille

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

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 Areva NC, 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 2006 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 - a critical analysis of the 2006 source term; a note about the uranium content in liquid effluents; the data transmitted by Areva NC (status of atmospheric effluents, status of liquid effluents at sea, fuel data); the data transmitted by the IRSN - the French institute of radiation protection and nuclear safety (status of the radioactive effluents of Areva La Hague facility); the history of liquid and gaseous effluents between 1966 and 2006; 2 - detailed comparison between model and 2006 measurements; critical analysis of {sup 14}C and tritium data available for the Nord Cotentin and the English Channel area; 3 - detail of the 2006 efficient dose calculations; presentation of the environmental dispersion of tritium and of its effects on living organisms. (J.S.)

Atmospheric tritium concentrations under influence of AREVA NC La Hague reprocessing plant (France) and background levels.

Science.gov (United States)

Connan, O; Hébert, D; Solier, L; Maro, D; Pellerin, G; Voiseux, C; Lamotte, M; Laguionie, P

2017-10-01

In-air tritium measurements were conducted around the AREVA NC La Hague reprocessing plant, as well as on other sites that are not impacted by the nuclear industry in northwest of France. The results indicate that the dominant tritium form around the AREVA site is HT (86%). HT and HTO levels are lower than 5 and 1 Bq. m -3 for hourly samples taken in the plume. No tritiated organic molecules (TOM) were detected. 26 measurement campaigns were performed and links were established between near-field 85 Kr, HT and HTO activities. Environmental measurements are in line with those taken at the discharge stack, and tend to demonstrate that there are no rapid changes in the tritium forms released. Out of the influence of any nuclear activities, the levels measured were below 13 mBq.m -3 for HT and 5 mBq.m -3 for HTO (<0.5 Bq. L -1 ). HTO level in air seems to be influenced by HTO activities in surrounding seawater. Copyright © 2017 Elsevier Ltd. All rights reserved.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-01-15

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

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

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

What Really Happened in The Hague? Report on the COP 6. Part I. 13 - 25 November 2000, The Hague, The Netherlands

International Nuclear Information System (INIS)

Buchner, B.K.

2001-06-01

This paper investigates the occurrences at the Sixth Conference of the Parties (CoP) to the 1992 United Nations Framework Convention on Climate Change (UNFCCC) which took place in The Hague, Netherlands, from 13-25 November of 2000. Since the conference did not reach an agreement there exists a broad interest in knowing what really happened during the negotiations. The aim of the analysis is to give greater insight to reasons of the climate talks' failure and to progress made during the negotiations. Following the discussions of the issues surrounding the talks in The Hague, the paper will also look forward as to possible solutions and ideas for an eventual agreement

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.)

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.)

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)

Seance of the 11. december 2002 of the special and permanent commission of information nearby the establishment of La Hague. Audition de Mycle Schneider, Director of Ise-Paris

International Nuclear Information System (INIS)

Schneider, M.

2002-01-01

The intervention of Mycle Schneider leaned on numerous updated transparencies (graphs, illustrations) gathered according to the principal tackled themes. The tables and graphs devoted to the doses issued from releases of reprocessing plants show a revised version of collective doses estimations. The different subjects are: the world electronuclear park, the situation of nuclear matters, the exploitation of La Hague facility, the release in environment of reprocessing plants, the individual land collective radiation doses induced by releases, the risk of a plane fall and other safety problems. (N.C.)

Improvement of operation capacity and decreasing of delay of The Hague Holland Spoor

NARCIS (Netherlands)

Xiaojun, P.

2001-01-01

The Hague Holland Spoor is a representative main station in the Netherlands railvi/ay network, its current form of operation and passenger organisation is being limited by its infrastructure. Also its infrastructure restricts the main network capacity of the Netherlands between Leiden, The Hague and

Preliminary study of the {sup 129}I distribution in environment of La Hague reprocessing plant with the help of a terrestrial moss: Homalotecium sericeum. Study report; Etude preliminaire de la repartition de {sup 129}I dans l'environnement de l'usine de retraitement de La Hague a l'aide d'une mousse terrestre: Homalotecium sericeum. Rapport d'etude

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The preliminary study of the {sup 129}I distribution has allowed to underline the limits of use of a Homalotecium sericeum type terrestrial moss as biological indicator. However, this preliminary study allowed all the same to give a spatial distribution of this radioelement around La Hague reprocessing plant (source term) that underlines the existence of four geographic areas in function of collected activities. The levels are generally under 99 Bq/kg dry. It is recommended to improve the knowledge that we can have of transfers and quantity of iodine 129 from the marine environment to the terrestrial environment, but also, the one that we can have of factors able to modify the spatial distribution of this radionuclide. (N.C.)

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)

Preliminary study of the 129I distribution in environment of La Hague reprocessing plant with the help of a terrestrial moss: Homalotecium sericeum. Study report

International Nuclear Information System (INIS)

1999-01-01

The preliminary study of the 129 I distribution has allowed to underline the limits of use of a Homalotecium sericeum type terrestrial moss as biological indicator. However, this preliminary study allowed all the same to give a spatial distribution of this radioelement around La Hague reprocessing plant (source term) that underlines the existence of four geographic areas in function of collected activities. The levels are generally under 99 Bq/kg dry. It is recommended to improve the knowledge that we can have of transfers and quantity of iodine 129 from the marine environment to the terrestrial environment, but also, the one that we can have of factors able to modify the spatial distribution of this radionuclide. (N.C.)

Modelling the transfer of 14C from the atmosphere to grass: A case study in a grass field near AREVA-NC La Hague

International Nuclear Information System (INIS)

Aulagnier, C.; Le Dizès, S.; Maro, D.; Hébert, D.; Lardy, R.; Martin, R.; Gonze, M.-A.

2012-01-01

Radioactive 14 C is formed as a by-product of nuclear power generation and from operation of nuclear fuel reprocessing plants like AREVA-NC La Hague (North France), which releases about 15 TBq per year of 14 C into the atmosphere. Since the autumn of 2006, 14 C activity concentrations in samples from the terrestrial environment (air, grass and soil) have been monitored monthly on grassland 2 km downwind of the reprocessing plant. The monitoring data provides an opportunity to validate radioecology models used to assess 14 C transfer to grassland ecosystems. This article compares and discusses the ability of two different models to reproduce the observed temporal variability in grass 14 C activity in the vicinity of AREVA-NC La Hague. These two models are the TOCATTA model which is specifically designed for modelling transfer of 14 C and tritium in the terrestrial environment, and PaSim, a pasture model for simulating grassland carbon and nitrogen cycling. Both TOCATTA and PaSim tend to under-estimate the magnitude of observed peaks in grass 14 C activity, although they reproduce the general trends. PaSim simulates 14 C activities in substrate and structural pools of the plant. We define a mean turn-over time for 14 C within the plant, which is based on both experimental data and the frequency of cuts. An adapted PaSim result is presented using the 15 and 20 day moving average results for the 14 C activity in the substrate pool, which shows a good match to the observations. This model reduces the Root Mean Square Error (RMSE) by nearly 40% in comparison to TOCATTA. - Highlights: ► We model 14 C transfer from the atmosphere to grass near AREVA-NC reprocessing plant. ► Both models considered under-estimate the observed variability and highest peaks. ► A model based solely on the sap 14 C activity and mean turn-over time is considered. ► It performs well and could be applied to case studies around nuclear facilities.

Health effects due to the release of iodine 129 from the marine outlet for the reprocessing plant located at La Hague

International Nuclear Information System (INIS)

Robeau, D.; Calmet, D.

1985-02-01

The study contained in this report estimates the health effects in terms of doses to the populations due to the release of Iodine 129 from the marine outlet for the reprocessing plant located at La Hague. The release taken into account is due to the normal functioning of the plant, which introduces a consistent contamination of the English channel during the life of the plant which is thirty years. The annual release of Iodine 129, as assumed by the operating staff, is equal to either 1,662.10 12 Bq or 45 Ci. The dose equivalent to the thyroid of the concerned population due to normal consummation of marine products (fish, shell-fish, mollusc) are very low as compared to the 6.10 -4 limit of dose authorized for the public in the actual regulation. The effective dose equivalent has been estimated at 4.27.10 -7 Sv [fr

Carbon 14

International Nuclear Information System (INIS)

2002-03-01

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

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

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)

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

MOX fuel reprocessing and recycling

International Nuclear Information System (INIS)

Guillet, J.L.

1990-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

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)

[Prevalence of caries and dental erosion among school children in The Hague from 1996-2005

NARCIS (Netherlands)

Truin, G.J.; Frencken, J.E.F.M.; Mulder, J.; Kootwijk, A.J.; Jong, E. de

2007-01-01

In 2005 a dental survey of the prevalence of caries among 6- and 12-year-old schoolchildren in The Hague was carried out. In the case of the 12-year-olds, the prevalence of dental erosion was also studied. The sample consisted of 814 students in twelve primary schools in The Hague. The results

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

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.)

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

France. The Centre de la Manche disposal facility: Entering into the institutional control period

International Nuclear Information System (INIS)

2001-01-01

The Centre de la Manche disposal facility, created by decree in 1969, is the first French near-surface radioactive waste disposal facility. It lies at the northwest end of the Cotentin peninsula, next to the COGEMA-La Hague fuel reprocessing plant. The Centre de la Manche facility occupies an area of about 150,000 m 2 . Its operation was terminated in late June 1994 with about 500,000 m 3 of packages disposed of. Operating feedback from the Centre de la Manche was used to design the second French disposal facility, located in the Aube, which has been receiving LILW since 1992. Since the end of the operating period, ANDRA has been preparing the statutory files to prepare the Centre de la Manche for its entry into the institutional control period. A new government decree will set the framework in which the Centre will evolve in this period. The regulatory process includes the filing of an application with the ministries concerned, containing a file with the requisite statutory documents, including an impact study of the facility on its environment as well as a hazard study. The file will then be submitted to a public inquiry, an essential informative period of the project designed to make a compilation of criticisms and suggestions from the public. In support of the application, a safety report has been sent to the Nuclear Installation Safety Directorate (DSIN) for a decision on the admissibility of the application. Recently, the Group of experts appointed by the DSIN which examined it has come out in favor of the creation of a new basic nuclear installation (i.e., a new government agency) for the institutional control period. A draft decree will then be submitted to the approval of the Interministerial Commission for Basic Nuclear Installations. This process, initiated in 1994, is nearing completion

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)

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

International Nuclear Information System (INIS)

Bourgogne, J.L.

1998-01-01

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

II. The Notion and Beginning of Belligerent Occupation under the 1899/1907 Hague Conventions

OpenAIRE

Siegrist, Michael

2011-01-01

1. Historical Background The First Hague Peace Conference convened in 1899 sought,among other things, the revision of the Brussels Project of 1874. As stated by Graber, both the Convention (II) with Respect to the Laws and Customs of War on Land and its annexed Regulations Respecting the Laws and Customs of War on Land (hereafter: 1899 Hague Regulations) adopted at this conference generally followed the rules laid down in the Brussels Project of 1874. As a consequence of this interlinkage “th...

Growth in The Hague versus decline in Leiden. A comparison of spatial development in two Dutch cities between 1700 and 1870

Directory of Open Access Journals (Sweden)

Jelmer van der Zweep

2017-04-01

1830–1870 The Hague underwent considerable densification inside the canal ring as well as extensions north and south of the city. The number of new tenements built on inner yards in The Hague can give a distorted impression, as can the number of demolished buildings in Leiden, because the 1870 maps were much more detailed. In Leiden the advent of new factories prompted new construction on the former city walls. The Hague, too, became a major industrial player, while continuing to profit from its function as the centre of government. In 1870, The Hague had almost twoand-a-half times as many inhabitants as Leiden (92,000 versus 39,000, but within the canal girdle Leiden was still more densely built up. Between 1700 and 1870, The Hague developed into one of the Netherlands’ biggest cities, which it still is. Leiden plummeted from second place to the middle bracket, where it continues to sit today.

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)

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

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

International Nuclear Information System (INIS)

2003-01-01

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

A note on Ramsey and Corlett-Hague rules

OpenAIRE

Ley, Eduardo

1992-01-01

Ramsey-type results dictate that an optimal pattern of taxes must tax more heavily those goods which have a more inelastic(compensated)demand. Corlett and Hague (1953) investigated the optimal revenue-neutral movements from an initial uniform tax. They obtained that the goods (relatively) more complementary to the untaxed good (leisure)should see their taxes increased-which in a revenue-neutral seeting implies that the other goods see their taxes disminished. In a three-good economy (with on...

The Hague Region: Negotiating the Common Ground in Peri-Urban Landscapes

NARCIS (Netherlands)

Westerink - Petersen, J.; Aalbers, C.B.E.M.

2013-01-01

This chapter deals with the case study region with the highest average urban density, the biggest area below sea level and the largest area of greenhouse horticulture of all PLUREL case studies, The Hague Region, in the Netherlands. The chapter introduces the area and then the planning system in The

Aansprakelijkheid van de afzender van gevaarlijke goederen onder de Hague-Visby-Rules

OpenAIRE

Smeele, Frank

1999-01-01

textabstractEngland, House of Lords 22 januari 1998, (1998) 1 Lloyd's Rep. 337 [Giannis NK] Zeevervoer onder cognossement: uitleg begrip 'goederen van . . . gevaarlijke aard'; aard aansprakelijkheid afzender van gevaarlijke goederen Art. iv-6, art. iv-3 Hague (-Visby) Rules (art. 8: 423 BW)

Study of the {sup 60}Co speciation in the aqueous radioactive waste of the la Hague nuclear reprocessing plant; environmental behaviour after discharges in the waters of the channel; Etude de la speciation du {sup 60}Co dans les effluents de l'usine de retraitement de combustibles irradies de la Hague; devenir apres rejet dans les eaux de la Manche

Energy Technology Data Exchange (ETDEWEB)

Gaudaire, J.M

1999-07-01

{sup 60}Co is produced as an activation product and is present in the low-level aqueous radioactive waste released from the La Hague plant. At present, the concentration in the sea (non filtered at 0.45 {mu}m) at the Goury site are close to or even below, the detection limit: 0.2 mBq.l{sup -1}. The {sup 60}Co speciation depends on the type of effluent considered: in the effluent A ('active'), the cobalt is in the form of a stable trivalent complex; in the effluent V (to be checked), the cobalt is in majority (50% of the activity release) in the form of particles (>0.45 {mu}m), and then in the form of two soluble species: ionic divalent (Co{sup 2+}) and some stable complexes. The evolution of the reprocessing techniques used does not affect the speciation. So, since the nuclear reprocessing plant started at the La Hague plant in 1966, the chemical species discharged in the sea shows time variation related to the evolution of the type of effluent discharged. Thus, since 1994, the particles of cobalt are the main species discharged in the Channel (the V effluents represent more than 85% of the total {sup 60}Co activity released). The effect of instantaneous dilution into the marine conditions involving a variation of pH, oxido-reduction, ionic strength, a gradient of salinity, does not interfere with the evolution of the chemical species discharged. Nevertheless, during the discharge of the V effluent, the main constituents of the sea water (Mg{sup 2+} and Ca{sup 2+}) go through a precipitation. This comes with the coprecipitation of the ion Co{sup 2+} and with the particles of cobalt (complexes are not affected), and it can be responsible for an increase in the concentration in the particles. The chemical behaviour of the cobalt in the Channel is different from those of conservative element such as antimony. The ionic cobalt and the particles have a small dispersion in the water (cobalt has a very high particle/dissolved distribution factor, it is a non

Study of the {sup 60}Co speciation in the aqueous radioactive waste of the la Hague nuclear reprocessing plant; environmental behaviour after discharges in the waters of the channel; Etude de la speciation du {sup 60}Co dans les effluents de l'usine de retraitement de combustibles irradies de la Hague; devenir apres rejet dans les eaux de la Manche

Energy Technology Data Exchange (ETDEWEB)

Gaudaire, J M

1999-07-01

{sup 60}Co is produced as an activation product and is present in the low-level aqueous radioactive waste released from the La Hague plant. At present, the concentration in the sea (non filtered at 0.45 {mu}m) at the Goury site are close to or even below, the detection limit: 0.2 mBq.l{sup -1}. The {sup 60}Co speciation depends on the type of effluent considered: in the effluent A ('active'), the cobalt is in the form of a stable trivalent complex; in the effluent V (to be checked), the cobalt is in majority (50% of the activity release) in the form of particles (>0.45 {mu}m), and then in the form of two soluble species: ionic divalent (Co{sup 2+}) and some stable complexes. The evolution of the reprocessing techniques used does not affect the speciation. So, since the nuclear reprocessing plant started at the La Hague plant in 1966, the chemical species discharged in the sea shows time variation related to the evolution of the type of effluent discharged. Thus, since 1994, the particles of cobalt are the main species discharged in the Channel (the V effluents represent more than 85% of the total {sup 60}Co activity released). The effect of instantaneous dilution into the marine conditions involving a variation of pH, oxido-reduction, ionic strength, a gradient of salinity, does not interfere with the evolution of the chemical species discharged. Nevertheless, during the discharge of the V effluent, the main constituents of the sea water (Mg{sup 2+} and Ca{sup 2+}) go through a precipitation. This comes with the coprecipitation of the ion Co{sup 2+} and with the particles of cobalt (complexes are not affected), and it can be responsible for an increase in the concentration in the particles. The chemical behaviour of the cobalt in the Channel is different from those of conservative element such as antimony. The ionic cobalt and the particles have a small dispersion in the water (cobalt has a very high particle/dissolved distribution factor, it is a non

Immediate supervision of the coastal site at the La Hague centre; Surveillance immediate du site marin du Centre de La Hague

Energy Technology Data Exchange (ETDEWEB)

Scheidhauer, J [Commissariat a l' Energie Atomique, La Hague (France)

1968-07-01

The disposal into the sea of the residual waters from a plant processing irradiated fuels means that a very close watch has to be kept on the corresponding coastal zone. The material organisation of such a supervision, and the sampling techniques, are described. These latter concern: flora, fauna, sediments and sea-water. Results obtained using various analytical and routine measurement methods are presented. (author) [French] L'elimination des eaux residuaires, d'un Centre de traitement de combustibles irradies, en mer, a pour consequence une surveillance particuliere de la zone cotiere correspondant a ces rejets. L'organisation materielle de cette surveillance et les techniques de prelevements sont decrites. Elles interessent la flore, la faune, les sediments et les eaux marines. Diverses methodes d'analyses et de mesures de routine ont fourni des resultats qui sont egalement exposes. (auteur)

Immediate supervision of the coastal site at the La Hague centre; Surveillance immediate du site marin du Centre de La Hague

Energy Technology Data Exchange (ETDEWEB)

Scheidhauer, J. [Commissariat a l' Energie Atomique, La Hague (France)

1968-07-01

The disposal into the sea of the residual waters from a plant processing irradiated fuels means that a very close watch has to be kept on the corresponding coastal zone. The material organisation of such a supervision, and the sampling techniques, are described. These latter concern: flora, fauna, sediments and sea-water. Results obtained using various analytical and routine measurement methods are presented. (author) [French] L'elimination des eaux residuaires, d'un Centre de traitement de combustibles irradies, en mer, a pour consequence une surveillance particuliere de la zone cotiere correspondant a ces rejets. L'organisation materielle de cette surveillance et les techniques de prelevements sont decrites. Elles interessent la flore, la faune, les sediments et les eaux marines. Diverses methodes d'analyses et de mesures de routine ont fourni des resultats qui sont egalement exposes. (auteur)

Hamburg rules V Hague Visby rules an English perspective

OpenAIRE

Tozaj Dorian; Xhelilaj Ermal

2010-01-01

It has often been argued for the effect of defences provided to carriers under Art IV (2) of Hague Visby Rules to almost nullify the protection guaranteed to shippers in other provisions of this convention. Therefore an all embracing universal shipper friendly convention, merely the Hamburg Rules, need be incorporated in all countries in order to address this issue and fully satisfy the intentions of the parties for the establishment of international rules in international trade

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)

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

Energy Technology Data Exchange (ETDEWEB)

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

1998-07-01

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

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

International Nuclear Information System (INIS)

Cabe, J.M.; Seurat, Ph.

1998-01-01

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

New challenges for urban consolidation centres: A case study in The Hague

NARCIS (Netherlands)

Duin, J.H.R. van; Quak, H.; Muñuzuri, J.

2010-01-01

The objective of this research is to advice the Municipality of The Hague whether, if and under which conditions, the implementation of an Urban Consolidation Centre (UCC) is possible and desirable. To determine factors that caused the success or failure of UCCs in practice, a survey of 6 cases in

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

International Nuclear Information System (INIS)

Sugierr, A.

1999-01-01

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

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)

Year 2005. GRNC's appreciation of the dose estimates presented in the annual environmental monitoring report of Areva-NC La Hague facility. Third GRNC viewpoint. Detailed report; Annee 2005. Appreciation par le GRNC de l'estimation des doses presentee dans le rapport annuel de surveillance de l'environnement d'Areva-NC La Hague. Troisieme avis du GRNC. Rapport detaille

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

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 Areva NC, 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 2005 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 2005 source term, the data transmitted by Areva NC (status of atmospheric effluents, status of liquid effluents at sea, fuel data, presentation of the work progress of the Areva NC working group), the history of liquid and gaseous effluents between 1966 and 2005; 2 - detailed comparison between model and 2005 measurements; 3 - detail of the 2005 efficient dose calculations. (J.S.)

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

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.

Nuclear safety: transparency in radioactive clouds

International Nuclear Information System (INIS)

Bondy, J.Ph.

2002-01-01

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

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.)

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

International Nuclear Information System (INIS)

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

2003-01-01

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

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.)

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)

Status of the nuclear measurement stations for the process control of spent fuel reprocessing at AREVA NC/La Hague

Energy Technology Data Exchange (ETDEWEB)

Eleon, Cyrille; Passard, Christian; Hupont, Nicolas; Estre, Nicolas [CEA, DEN, Cadarache, Nuclear Measurement Laboratory, F-13108 St Paul-lez-Durance (France); Battel, Benjamin; Doumerc, Philippe; Dupuy, Thierry; Batifol, Marc [AREVA NC, La Hague plant - Nuclear Measurement Team, F-50444 Beaumont-Hague (France); Grassi, Gabriele [AREVA NC, 1 place Jean-Millier, 92084 Paris-La-Defense cedex (France)

2015-07-01

Nuclear measurements are used at AREVA NC/La Hague for the monitoring of spent fuel reprocessing. The process control is based on gamma-ray spectroscopy, passive neutron counting and active neutron interrogation, and gamma transmission measurements. The main objectives are criticality and safety, online process monitoring, and the determination of the residual fissile mass and activities in the metallic waste remained after fuel shearing and dissolution (empty hulls, grids, end pieces), which are put in radioactive waste drums before compaction. The whole monitoring system is composed of eight measurement stations which will be described in this paper. The main measurement stations no. 1, 3 and 7 are needed for criticality control. Before fuel element shearing for dissolution, station no. 1 allows determining the burn-up of the irradiated fuel by gamma-ray spectroscopy with HP Ge (high purity germanium) detectors. The burn-up is correlated to the {sup 137}Cs and {sup 134}Cs gamma emission rates. The fuel maximal mass which can be loaded in one bucket of the dissolver is estimated from the lowest burn-up fraction of the fuel element. Station no. 3 is dedicated to the control of the correct fuel dissolution, which is performed with a {sup 137}Cs gamma ray measurement with a HP Ge detector. Station no. 7 allows estimating the residual fissile mass in the drums filled with the metallic residues, especially in the hulls, from passive neutron counting (spontaneous fission and alpha-n reactions) and active interrogation (fission prompt neutrons induced by a pulsed neutron generator) with proportional {sup 3}He detectors. The measurement stations have been validated for the reprocessing of Uranium Oxide (UOX) fuels with a burn-up rate up to 60 GWd/t. This paper presents a brief overview of the current status of the nuclear measurement stations. (authors)

Status of the nuclear measurement stations for the process control of spent fuel reprocessing at AREVA NC/La Hague

International Nuclear Information System (INIS)

Eleon, Cyrille; Passard, Christian; Hupont, Nicolas; Estre, Nicolas; Battel, Benjamin; Doumerc, Philippe; Dupuy, Thierry; Batifol, Marc; Grassi, Gabriele

2015-01-01

Nuclear measurements are used at AREVA NC/La Hague for the monitoring of spent fuel reprocessing. The process control is based on gamma-ray spectroscopy, passive neutron counting and active neutron interrogation, and gamma transmission measurements. The main objectives are criticality and safety, online process monitoring, and the determination of the residual fissile mass and activities in the metallic waste remained after fuel shearing and dissolution (empty hulls, grids, end pieces), which are put in radioactive waste drums before compaction. The whole monitoring system is composed of eight measurement stations which will be described in this paper. The main measurement stations no. 1, 3 and 7 are needed for criticality control. Before fuel element shearing for dissolution, station no. 1 allows determining the burn-up of the irradiated fuel by gamma-ray spectroscopy with HP Ge (high purity germanium) detectors. The burn-up is correlated to the 137 Cs and 134 Cs gamma emission rates. The fuel maximal mass which can be loaded in one bucket of the dissolver is estimated from the lowest burn-up fraction of the fuel element. Station no. 3 is dedicated to the control of the correct fuel dissolution, which is performed with a 137 Cs gamma ray measurement with a HP Ge detector. Station no. 7 allows estimating the residual fissile mass in the drums filled with the metallic residues, especially in the hulls, from passive neutron counting (spontaneous fission and alpha-n reactions) and active interrogation (fission prompt neutrons induced by a pulsed neutron generator) with proportional 3 He detectors. The measurement stations have been validated for the reprocessing of Uranium Oxide (UOX) fuels with a burn-up rate up to 60 GWd/t. This paper presents a brief overview of the current status of the nuclear measurement stations. (authors)

Education for Public Policy and Management: Views from the Institute of Social Studies, The Hague

NARCIS (Netherlands)

D.R. Gasper (Des); J.W. Björkman (James Warner); V. Moharir (Vasant); M.E. Wuyts (Marc)

2000-01-01

markdownabstractIntroduction When the Institute of Social Studies, ISS, was founded in 1952 in The Hague as a postgraduate centre for teaching and research on social and economic development, it established the first Masters programme in public administration and the first professorial chair in

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

The Hague Convention on the Protection of Children and Cooperation in Respect of Intercountry Adoption.

Science.gov (United States)

Duncan, William

1993-01-01

Reviews chapters of the Hague Convention on Intercountry Adoption which establish requirements for intercountry adoption, provide for a system of adoption authorities in contracting states, establish procedures to be adopted by the authorities, and provide for recognition of adoptions made under the convention. Notes that the convention guarantees…

AREVA la Hague site information report. Written in compliance with Article L. 125-15 of the French Environmental Code - 2015 edition

International Nuclear Information System (INIS)

2016-01-01

This document is the annual information report required by Article L. 125-15 of the Environmental Code, which states that any operator of a regulated nuclear facility draws up a report each year containing information on: - measures taken to prevent or limit the risks or drawbacks that the facility may present for the interests mentioned in Article L. 593-1; - incidents and accidents occurring within the facility's perimeter subject to the reporting obligation under Article L. 591-5, together with the measures taken to limit their development and the consequences for human health and the environment; - the type and results of measurements of radioactive and non-radioactive releases from the facility to the environment; - the type and quantity of waste stored within the facility's perimeter together with the measures taken to limit their volumes and health and environmental impacts, in particular on soils and water. In accordance with the provisions of Article L. 125-16 of the Environmental Code, this report is submitted to the site's Health, Safety and Working Conditions Committee (CHSCT, Comite d'hygiene, de securite et des conditions de travail), which may formulate recommendations. Those recommendations are appended to the document for purposes of publication and transmission. The report presents, first, the Areva La Hague site with its facilities and activities in relation with spent fuel reprocessing and radioactive waste management. Then, it takes stock of the dispositions implemented for the limitation and prevention of risks and summarizes the events declared in 2015. Next, it presents the management of the site effluents and wastes and the environmental monitoring. Finally, the actions of public information are presented

Study of the 60Co speciation in the aqueous radioactive waste of the la Hague nuclear reprocessing plant; environmental behaviour after discharges in the waters of the channel

International Nuclear Information System (INIS)

Gaudaire, J.M.

1999-01-01

60 Co is produced as an activation product and is present in the low-level aqueous radioactive waste released from the La Hague plant. At present, the concentration in the sea (non filtered at 0.45 μm) at the Goury site are close to or even below, the detection limit: 0.2 mBq.l -1 . The 60 Co speciation depends on the type of effluent considered: in the effluent A ('active'), the cobalt is in the form of a stable trivalent complex; in the effluent V (to be checked), the cobalt is in majority (50% of the activity release) in the form of particles (>0.45 μm), and then in the form of two soluble species: ionic divalent (Co 2+ ) and some stable complexes. The evolution of the reprocessing techniques used does not affect the speciation. So, since the nuclear reprocessing plant started at the La Hague plant in 1966, the chemical species discharged in the sea shows time variation related to the evolution of the type of effluent discharged. Thus, since 1994, the particles of cobalt are the main species discharged in the Channel (the V effluents represent more than 85% of the total 60 Co activity released). The effect of instantaneous dilution into the marine conditions involving a variation of pH, oxido-reduction, ionic strength, a gradient of salinity, does not interfere with the evolution of the chemical species discharged. Nevertheless, during the discharge of the V effluent, the main constituents of the sea water (Mg 2+ and Ca 2+ ) go through a precipitation. This comes with the coprecipitation of the ion Co 2+ and with the particles of cobalt (complexes are not affected), and it can be responsible for an increase in the concentration in the particles. The chemical behaviour of the cobalt in the Channel is different from those of conservative element such as antimony. The ionic cobalt and the particles have a small dispersion in the water (cobalt has a very high particle/dissolved distribution factor, it is a non-conservative radionuclide). This sedimentary stock can

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

Energy Technology Data Exchange (ETDEWEB)

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

2000-07-01

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

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

International Nuclear Information System (INIS)

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

2000-01-01

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

What parental characteristics can predict child maltreatment at the Emergency Department? Considering expansion of the Hague Protocol

NARCIS (Netherlands)

Diderich, H.M.; Dechesne, M.; Fekkes, M.; Verkerk, P.H.; Buitendijk, S.E.; Oudesluys-Murphy, A.M.

2015-01-01

The Hague Protocol considers three parental characteristics of Emergency Department adult patients to identify child abuse: (a) domestic violence, (b) intoxication, and (c) suicide attempt or auto mutilation. This study investigated whether additional parental characteristics could be included to

Hague Convention on the Civil Aspects of International Child Abduction. Report from the Committee on Foreign Relations (To Accompany Treaty Doc. 99-11). 99th Congress, 2d Session.

Science.gov (United States)

Congress of the U.S., Washington, DC. Senate Committee on Foreign Relations.

The Hague Convention on the Civil Aspects of International Child Abduction, an international law whose purpose is to establish uniform rules to be applied in cases of international child abduction, is described. The Hague Convention requires that children wrongfully removed or retained abroad in connection with parental custody disputes be…

FOREIGN JUDGMENTS PROJECT OF HAGUE CONFERENCE: FOR A GLOBAL REGIME OF INTERNATIONAL CIRCULATION OF JUDGMENTS ON CIVIL AND COMMERCIAL SUBJECTS

Directory of Open Access Journals (Sweden)

Nadia de Araujo

2017-02-01

Full Text Available The Hague Conference on Private International Law is promoting the adoption of rules designed to circumvent usual obstacles to the international circulation of judgments. The Judgments Project initiated in the nineties aims at mitigating uncertainties and risks associated with the international commerce by setting forth a simple and safe system according to which foreign judgments may circulate from country to country. The purpose of this article is to preserve the historical moment of the negotiations taking place at the Hague, as well as to pinpoint some technical issues raised in the course of the project that may be of general interest to those involved in the subject of international jurisdiction.

Law and Practice of the Obligations of the Carrier over the Cargo : The Hague-Visby Rules

NARCIS (Netherlands)

Djadjev, Ilian Nikolaev

2016-01-01

The present-day law on the carriage of goods by sea suffers from a lack of uniformity and from being not able to adequately address the current developments in the industry of international shipping. The leading liability regime which is in force, the Hague-Visby Rules, consists of rather outdated

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

Energy Technology Data Exchange (ETDEWEB)

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

1998-07-01

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

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)

Review of BNFL's operational experience of wet type flasks

International Nuclear Information System (INIS)

McWilliam, D.S.

2004-01-01

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

Latest technological achievements and future prospects in the RCR industry

International Nuclear Information System (INIS)

Corny, F.

1998-01-01

As the international utilities community enters an era marked by new patterns such as deregulation, industrial nuclear companies must offer a broad and attractive series of flexible services in order to match with the utilities needs. COGEMA Group has therefore developed a global industrial answer-thanks to various technological tools-covering reprocessing of spent nuclear fuel, treatment of waste, and recycling of reusable materials as well as a transportation system. According to this framework, spent fuel is first shipped from the nuclear power plant to the. La Hague reprocessing site. The La Hague site-1997 reprocessed spent fuel quantities exceed 11,100 tU-offers a technically mastered and economically proven solution for spent fuel reprocessing. Besides the acquired industrial maturity, specially in the waste treatment and conditioning area-i.e., vitrification of high level waste reached more than 5,500 canisters at beginning 1998-future improvements are being prepared steadily. For instance, the construction of a new workshop, known as the ACC, for medium activity materials (hulls, end-pieces, and technological waste) compaction will be a milestone in the waste management concept. Industrial recycling of reusable materials (uranium and plutonium) is also implemented at full-throttle. For instance, the MELOX manufacturing plant-whose production reached 102 tHM in 1997 thanks to evolutive processes such as AMIMAS-allows to feed with efficiency the European MOX loading program (28 reactors: 15 in France, 8 in Germany, 3 in Switzerland and 2 in Belgium). Last, a dedicated transport organization-through highly specialized subsidiaries such as TRANSNUCLEAIRE-gives this industrial and technical scheme its consistency as shown by the successful return of vitrified residue to Japan. The development of new transport casks for instance MOX transport casks called the MX family-and the implementation of new techniques, like satellite tracking of trucks..., will give

El teatre català del segle XIX i la realitat catalana de l'època

Directory of Open Access Journals (Sweden)

Ramon Bacardit

2014-02-01

a la realitat contemporània immediata, bé a través del reflex directe com en les obres d’actualitat de Jaume Piquet, bé amb el recurs a la distanciació històrica o de clixés costumistes com en el cas de Soler. A la llarga, el model de realitat iteraturitzable consolidat s’hagué d’enfrontar a les demandes del realisme literari de configurar una altra convenció del real.

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

Detecting child abuse based on parental characteristics: Does The Hague Protocol cause parents to avoid the Emergency Department?

NARCIS (Netherlands)

Diderich, H.M.; Fekkes, M.; Dechesne, M.; Buitendijk, S.E.; Oudesluys-Murphy, A.M.

2015-01-01

Objectives: The Hague Protocol is used by professionals at the adult Emergency Departments (ED) in The Netherlands to detect child abuse based on three parental characteristics: (1) domestic violence, (2) substance abuse or (3) suicide attempt or self-harm. After detection, a referral is made to the

The implications of English-medium instruction on teaching practice and learning outcomes at The Hague University of Applied Sciences

NARCIS (Netherlands)

Joyce den Heijer

2015-01-01

In response to globalisation and internationalisation of both higher education and the job market, The Hague University of Applied Sciences (THUAS) has seen a considerable increase in English-medium courses, i.e. non-language subjects taught through English. Internationally, the rise of

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

In situ responses of a biological indicator Mytilus edulis L. to the variations of radionuclide discharges from a fuel reprocessing plant

International Nuclear Information System (INIS)

Masson, Michel; Leon, Rene; Miramand, Pierre; Germain, Pierre.

1983-01-01

The introduction of 10 lots of 100kg of mussels in La Hague waters made it possible to investigate the in situ uptake kinetics of 106 Ru + 106 Rh released by the fuel reprocessing plant of La Hague during 1 year. Equilibrium was reached within 1 - 3 months, whatever the time of introduction and the amounts released. The removal of the mussels labelled at La Hague to a remote aera made it possible to calculate the biological half-life of 106 Ru + 106 Rh, viz from 16 to 18 days [fr

Missed Cases in the Detection of Child Abuse Based on Parental Characteristics in the Emergency Department (the Hague Protocol)

NARCIS (Netherlands)

Diderich, H.M.; Verkerk, P.H.; Oudesluys-Murphy, A.M.; Dechesne, M.; Buitendijk, S.E.; Fekkes, M.

2015-01-01

Introduction We aimed to assess the number of “missed cases” in the detection of child abuse based on the Hague Protocol. This protocol considers 3 parental characteristics of ED adult patients to identify child abuse: (1) domestic violence, (2) intoxication, and (3) suicide attempt or

INTERACTION BETWEEN HAGUE CONVENTION ON THE CIVIL ASPECTS OF INTERNATIONAL CHILD ABDUCTION AND DOMESTIC LITIGATIONS CONCERNING DOMICILE OF THE CHILD AND PARENTAL AUTHORITY

Directory of Open Access Journals (Sweden)

Anca Magda VOICULESCU

2018-05-01

Full Text Available In the vast majority of cases, international abduction of a child determines almost per se litigations both at international and national level, namely an international litigation based on provisions of Hague Convention on the civil aspects of international child abduction and a domestic litigation aiming at establishing the domicile of the child in the state of destination and other different measures concerning the child which fall within the area of parental authority (joint or exclusive. The purpose of the article is to analyze the interaction between the international and the national case and how they influence each other from a double perspective (procedural and substantial, taking into account that the two litigations are generally pending at the same time. Even the mere coexistence of the two litigations gives rise to the question which one should have priority in solving. Therefore, the objectives of this study are, on the one hand, to examine the implications in the domestic litigation of the decision pronounced in the Hague litigation (international competence, suspension of the national case, elements which are covered by the res judicata principle, and on the other hand to identify how a national decision on domicile and parental authority may influence the solution in the Hague case.

The behaviour of 129I released from nuclear fuel reprocessing factories in the North Atlantic Ocean and transport to the Arctic assessed from numerical modelling

International Nuclear Information System (INIS)

Villa, M.; López-Gutiérrez, J.M.; Suh, Kyung-Suk; Min, Byung-Il; Periáñez, R.

2015-01-01

Highlights: • Dispersion of 129 I released from nuclear facilities evaluated by numerical modelling in the Atlantic. • Model validated through comparisons with field measurements. • 5.1 and 16.6 TBq of 129 I have been introduced in the Arctic from Sellafield and La Hague. • The distribution of 129 I among several shelf seas and regions has been evaluated. • Mean ages of tracers obtained: about 3.5 year larger for Sellafield than for La Hague releases. - Abstract: A quantitative evaluation of the fate of 129 I, released from the European reprocessing plants of Sellafield (UK) and La Hague (France), has been made by means of a Lagrangian dispersion model. Transport of radionuclides to the Arctic Ocean has been determined. Thus, 5.1 and 16.6 TBq of 129 I have been introduced in the Arctic from Sellafield and La Hague respectively from 1966 to 2012. These figures represent, respectively, 48% and 55% of the cumulative discharge to that time. Inventories in the North Atlantic, including shelf seas, are 4.4 and 13.8 TBq coming from Sellafield and La Hague respectively. These figures are significantly different from previous estimations based on field data. The distribution of these inventories among several shelf seas and regions has been evaluated as well. Mean ages of tracers have been finally obtained, making use of the age-averaging hypothesis. It has been found that mean ages for Sellafield releases are about 3.5 year larger than for La Hague releases

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.

New developments in transportation for research reactors

Energy Technology Data Exchange (ETDEWEB)

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

1998-07-01

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

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

International Nuclear Information System (INIS)

Heintschel v Heinegg, W.

1999-01-01

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

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

International Nuclear Information System (INIS)

Roux, P.; Jouan, A.

1998-01-01

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

3. forum of radiation protection sciences - Book of abstracts

International Nuclear Information System (INIS)

2002-10-01

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

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.

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.)

The potentialities of the complexation ultrafiltration technique for the decontamination of fission product contaminated aqueous effluents; Potentialites de la complexation - ultrafiltration a la decontamination d`effluents radioactifs en produits de fission

Energy Technology Data Exchange (ETDEWEB)

Thibert, V

1995-07-01

Many nuclear researchers and industrial operators lay emphasis on improving the back end of the fuel cycle. A major problem concerns the liquid wastes generated by the reprocessing plant at La Hague, discharged into the sea after treatment in the Effluent Treatment Station (STE) (3), and which have become crucial matter. The activity of these wastes is well below the current legal limits, and is constantly decreasing these last years. To bring it close to zero, and ambitious goal, entails innovative new reprocessing techniques. We accordingly investigated the possibilities of complexation-ultrafiltration, a technique that uses water-soluble macromolecules to complex the target elements to be separated. We first achieved the strontium (II) separation with poly-acrylic and poly-sulfonic acids. The effects of pH and NaNO{sub 3} concentration influence on Sr (II) complexation were studied. The Sr (II) complexation and concentration phases, followed by cation de-complexation to recover the polymer, were also taken into account. This research, combined with a potentiometric study of the polymers, offered a close understanding of the chemical systems involved, and of the operating conditions and limits of complexation-ultrafiltration. The laboratory results were also validated on a tangential ultrafiltration pilot plant. We then used complexation-ultrafiltration to treat a real effluent generated bu La Hague`s STE 3 plant. This experiment demonstrated minimum 90 % decontamination of Sr (II) (with polyacrylate complexing agent), and also for {sup 134-137}Cs (with simple ultrafiltration). The use of two polyamides allowed partial decontamination of the effluent for {sup 60}Co and {sup 106}Ru. This work therefore offers a global approach to complexation-ultrafiltration, from laboratory to pilot scale, on real and simulated effluents. The future of this technique relies chiefly on the ability to solve the problem of polymer recovery. (Abstract Truncated)

Decree of January 11, 2016 bearing homologation of the decision nr 2015-DC-0536 by the Nuclear Safety Authority of December 22, 2015 defining threshold values of releases in the environment of liquid and gaseous effluents from base nuclear installations nr 33 (UP2-400), 38 (STE2 et AT1), 47 (ELAN II B), 80 (HAO), 116 (UP3-A), 117 (UP2-800) and 118 (STE3 effluent processing station) exploited by AREVA NC on the La Hague site (Manche district)

International Nuclear Information System (INIS)

Mortureux, M.

2016-01-01

After having mentioned the various related and reference legal texts, this legal publication specifies the various threshold values which must be applied to liquid and gaseous releases of nuclear installations located in La Hague for a better control and management of pollutions and of the impact of these installations on the environment. Threshold values are thus specified for various compounds and species, and the document also mentions AREVA's publications which indicate the actual release levels and state that these levels are within the accepted limits

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

International Nuclear Information System (INIS)

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

2004-01-01

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

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

International Nuclear Information System (INIS)

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

2000-01-01

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

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)

Improvements in techniques and processes

International Nuclear Information System (INIS)

Cairon, B.; Nolin, D.

2003-01-01

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

THE PROTECTION OF CULTURAL GOODS FROM THE ROERICH PACT TO THE HAGUE CONVENTION

Directory of Open Access Journals (Sweden)

MARIAN MIHĂILĂ

2013-05-01

Full Text Available The study premises and objectives: The idea found at the basis of the discovery of a real value of cultural goods is underlined by the knowledge of their origins and history and of an environmental frame in which these have been produced. This theory could also be applied in regulations provided with certain newly introduced elements as: the absolute interdiction of thefts; the interdiction of destruction and execution of enemy property; the warning of before a terrestrial bombing with naval forces of ports, cities, villages, buildings or houses which are not defended The purpose on this paper is based on the following question: “Which of the gaps of humanitarian international law regarding cultural goods are surfacing?” The research models used are: the interpretative method, the structuralist-systematic method necessary for the knowledge of rules of organization and functioning of law as a system of social organization; the epistemological method, with an important role in the verification of an authentic meaning, fully manifesting the exigency regarding the protection of cultural property. The result of the study is obtained by offering an answer which as argued in this paper, concluding on one side that the discrepancies appeared between provisions (or dispositions of the Hague Convention of 1907 and the events of the First World War have led to an improved idea and to a completion of these norms. Conclusions: The preoccupation for the protection of cultural goods, of the people’s cultural patrimony, thus continues, even if, despite all acts adopted, we observe that certain states destroy willingly the treasures of other peoples. We have thus reached the conclusion that more drastic measures must be adopted more severe sanctions must be applied to states that neglect the norms of humanitarian international law and the existent gaps must be eliminated. For this reason the Second Protocol of The Hague Convention of 1954 has been promoted

Playing by the rules. The Hague courts and the Acteonisation du Grand Veneur d’Hollande (1643

Directory of Open Access Journals (Sweden)

Marika Keblusek

2017-02-01

Full Text Available This article discusses an unpublished play, Acteonisation du Grand Veneur d’Hollande (1643. Created – and possibly performed – within the immediate circle of the court of Elizabeth of Bohemia in The Hague, its anonymous author satirizes the various personalities in the Orange courts of respectively Frederik Hendrik and Amalia von Solms, and Willem II and Mary Stuart. Focusing on the social ambitions of Johannes Polyander van Kerckhoven, Lord of Heenvliet, and by using the popular myth of Actaeon and Diana, the clash between court and city, between princely aristocrats and republican burghers is played out.

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)

Communication dated 8 April 2014 received from the Permanent Mission of the Netherlands to the Agency regarding The Hague Nuclear Security Summit Communiqué

International Nuclear Information System (INIS)

2014-01-01

The Director General has received a communication dated 8 April 2014 from the Permanent Mission of the Netherlands to the Agency, enclosing the Communiqué of the Nuclear Security Summit 2014, which took place on 24-25 March 2014 in The Hague. The communication and, as requested by the Permanent Mission, the Communiqué are circulated herewith for information

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

[Dental caries and dental erosion among 5- and 6-year old and 11- and 12-year old school children in the Hague, the Netherlands. Changing prevalences?

NARCIS (Netherlands)

Truin, G.J.; Rijkom, H.M. van; Mulder, J.; Hof, M.A. van 't

2004-01-01

In 2002 a dental survey amongst 6- and 12-year-old schoolchildren in The Hague had been carried out. The 2002 survey suggested that in the period 1996-2002 the caries prevalence (% of cariesfree children) and the caries experience (mean dmfs/dmft scores) among 6-year-old children did not have

Communication dated 8 April 2014 received from the Permanent Mission of the Netherlands to the Agency regarding The Hague Nuclear Security Summit Communiqué

International Nuclear Information System (INIS)

2014-01-01

The Director General has received a communication dated 8 April 2014 from the Permanent Mission of the Netherlands to the Agency, enclosing the Communiqué of the Nuclear Security Summit 2014, which took place on 24-25 March 2014 in The Hague. The communication and, as requested by the Permanent Mission, the Communiqué are circulated herewith for information [es

The use of nuclear data in the field of nuclear fuel recycling

Directory of Open Access Journals (Sweden)

Martin Julie-Fiona

2017-01-01

Full Text Available AREVA NC La Hague facility is the first step of the nuclear fuel recycling process implemented in France. The processing of the used fuel is governed by high standards of criticality-safety, and strong expectations on the quality of end-products. From the received used fuel assemblies, the plutonium and the uranium are extracted for further energy production purposes within the years following the reprocessing. Furthermore, the ultimate waste – fission products and minor actinides on the one hand, and hulls and end-pieces on the other hand – is adequately packaged for long term disposal. The used fuel is therefore separated into very different materials, and time scales which come into account may be longer than in some other nuclear fields of activity. Given the variety of the handled nuclear materials, as well as the time scales at stake, the importance given to some radionuclides, and hence to the associated nuclear data, can also be specific to the AREVA NC La Hague plant. A study has thus been led to identify a list of the most important radionuclides for the AREVA NC La Hague plant applications, relying on the running constraints of the facility, and the end-products expectations. The activities at the AREVA NC La Hague plant are presented, and the methodology to extract the most important radionuclides for the reprocessing process is detailed.

The use of nuclear data in the field of nuclear fuel recycling

Science.gov (United States)

Martin, Julie-Fiona; Launay, Agnès; Grassi, Gabriele; Binet, Christophe; Lelandais, Jacques; Lecampion, Erick

2017-09-01

AREVA NC La Hague facility is the first step of the nuclear fuel recycling process implemented in France. The processing of the used fuel is governed by high standards of criticality-safety, and strong expectations on the quality of end-products. From the received used fuel assemblies, the plutonium and the uranium are extracted for further energy production purposes within the years following the reprocessing. Furthermore, the ultimate waste - fission products and minor actinides on the one hand, and hulls and end-pieces on the other hand - is adequately packaged for long term disposal. The used fuel is therefore separated into very different materials, and time scales which come into account may be longer than in some other nuclear fields of activity. Given the variety of the handled nuclear materials, as well as the time scales at stake, the importance given to some radionuclides, and hence to the associated nuclear data, can also be specific to the AREVA NC La Hague plant. A study has thus been led to identify a list of the most important radionuclides for the AREVA NC La Hague plant applications, relying on the running constraints of the facility, and the end-products expectations. The activities at the AREVA NC La Hague plant are presented, and the methodology to extract the most important radionuclides for the reprocessing process is detailed.

Sampling of charged liquid radwaste stored in large tanks

International Nuclear Information System (INIS)

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

1995-01-01

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

Status and prospects for reprocessing

International Nuclear Information System (INIS)

Rossney, G.K.

1977-01-01

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

22. ATSR congress - Book of abstracts

International Nuclear Information System (INIS)

2004-10-01

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

Impact of industrial nuclear releases into the English Channel

International Nuclear Information System (INIS)

Germain, P.; Guegueniat, P.

1992-01-01

The nuclear fuel reprocessing plant at La Hague is the main source of releases of weakly radioactive waste into the English Channel; there are also some contributions from nuclear power stations along the coast. Indicator species, seawater samples and sediments are used to study the distribution and transfer mechanisms of radionuclides in Channel waters. The observed pattern of radiolabelled zones is in good agreement with an hydrodynamic model for the Channel. The variations of activity with time are discussed in relation to releases from La Hague

INTERACTION BETWEEN HAGUE CONVENTION ON THE CIVIL ASPECTS OF INTERNATIONAL CHILD ABDUCTION AND DOMESTIC LITIGATIONS CONCERNING DOMICILE OF THE CHILD AND PARENTAL AUTHORITY

OpenAIRE

Anca Magda VOICULESCU

2018-01-01

In the vast majority of cases, international abduction of a child determines almost per se litigations both at international and national level, namely an international litigation based on provisions of Hague Convention on the civil aspects of international child abduction and a domestic litigation aiming at establishing the domicile of the child in the state of destination and other different measures concerning the child which fall within the area of parental authority (joint or ...

Metamorphosis of Shell's office buildings in The Hague, Netherlands; Metamorfose Shell Den Haag

Energy Technology Data Exchange (ETDEWEB)

Lambert, G.F.A. [Valstar Simonis, Apeldoorn (Netherlands); Van Mierlo, W.J.M. [Shell, Den Haag (Netherlands)

2008-07-15

In a project to renovate the Shell office buildings in The Hague, Netherlands, the new buildings are served by a new power plant based on a heat pump and an underground thermal storage system. Use of a heating curve in the high-temperature heating system of the renovated building sections made it possible to create a link between the new low-temperature heating system and the existing high-temperature heating system. A similar link was created for cooling. [Dutch] Bij de herstructurering van het gebouwencomplex van Shell in Den Haag is voor de nieuwe gebouwen een energiecentrale met een warmtepomp en ondergronds energieopslagsysteem gerealiseerd. Door gebruik te maken van een stooklijn in het hooggestookte verwarmingssysteem van de gerenoveerde bouwdelen, is een koppeling aangebracht tussen het nieuwe Iaagtemperatuur verwarmingssysteem en het bestaande hooggestookte verwarmingssysteem. Ook voor de koeling is een dergelijke koppeling gemaakt.

Needs and wishes of alumni and employers : Research into the requirements of the labour market for international competencies in the Bachelor programme HBO ICT of The Hague University of Applied Sciences

NARCIS (Netherlands)

Anneke Wieman

2015-01-01

The Hague University of Applied Sciences has high ambitions in the field of internationalisation. Two out of four priorities in the institutional policy touch this theme: global citizenship and internationalisation. In order to ensure that the curriculum of the new degree programme HBO ICT meets

Spatial and temporal distribution (1987-91) of 125Sb used to trace pathways and transit times of waters entering the North Sea from the English Channel

International Nuclear Information System (INIS)

Guegueniat, P.; Du Bois, P.B.; Gandon, R.; Leon, R.

1994-01-01

The labelling of marine waters off north-western Europe by artificial radionuclides discharged by the nuclear fuel reprocessing plants at Sellafield and La Hague provides a potentially useful tool for the study of hydrodynamic processes. In this context, the present investigation introduces a tracer, 125 Sb, which is conservative within the watermass and which is characteristic of releases from la Hague. Analysis of the data collected between 1987 and 1991 shows that a large part of the channel waters entering the North Sea follow a route along the Belgian, Dutch, German and Danish coasts, while undergoing a low degree of dilution with other marine waters circulating in the central North Sea. The westward extension of the channel plume is variable with time, but the general distribution is in good agreement with the ICES box model. Estimates are given for the transit times from Cap de la Hague to various sectors of the North Sea; it takes 15-17 months for labelled waters to reach the Norwegian Channel. (Author)

The role of express submission to jurisdiction under the Brussels I Regulation, Brussels I (Recast) and the Hague Convention on Choice of Court Agreements

OpenAIRE

2015-01-01

LL.M. (International Commercial Law) This essay seeks to look at the role of express submission to jurisdictjon under the Brussels I Regulation,lthe Brussels I (recast) Regulation2 and the Hague Convention on Choice of Court Agreements.3 The express submission to jurisdiction under the three instruments mentioned in the previous sentence refers to the situation in which parties to an international commercial contract include in their contract a court of their choice to govern any disputes ...

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

Jurisdiction in international civil and commercial cases : a comparative study of the law in the IBSA countries and the Hague Convention on Choice of Court Agreements

OpenAIRE

2015-01-01

LL.M. (International Commercial Law) This dissertation concerns a comparative analysis of Brazilian, Indian and South African private international law principles on the exercise of jurisdiction in international civil and commercial cases. The intention is to uncover the fundamental grounds of jurisdiction in these legal systems and in doing so draw attention to their comparable characteristics. Emphasis is placed on matters of a commercial nature. Furthermore, a discussion of the Hague Co...

Radiation protection at La Hague plant

International Nuclear Information System (INIS)

Laffaille, C.

1980-01-01

After a rapid description of the working rules of the reprocessing facility and the fuel characteristics, we describe how the safety actions are led in the plant with respect to the occasional risks. If the limitation of the doses integrated by the workers is an objective which has been reached, we think the optimal level is not secured and that other approaches are possible, which must be used without delay [fr

La Hague environment centralized control system

International Nuclear Information System (INIS)

Kalimbadjian, J.

1991-01-01

The purpose of this paper is to show what we are doing in the area of environmental monitoring and control in accordance with the basic principles we set out for ourselves. As we have seen, our objectives are twofold; first, to monitor the installations under normal operating conditions in accordance with the rules and within the imposed limits and, secondly, in the event of an accident involving any of the material at the plant, to determine the foreseeable consequences in order to provide the relevant authorities, who have to take the necessary measures to protect the personnel and the population, with all the help they need. Normal operation is guaranteed by effective control of liquid and gaseous discharges, by knowing the precise origin and nature of the radio-elements released and also the means of transfer leading to humans. This knowledge relies upon the interpretation of the systematic measurements which have been carried out, which can only be done by centralising and computerising the data involved. The use of third-generation radio protection equipment in combination with highly-developed computer systems has made it possible to set up a centralised environmental control station. In the event of abnormal occurrences, the software used to show the transfer of radio-elements in the air, the water, or the ground, along with the use of systematic measurements, makes it possible to determine the foreseeable consequences and to design a system of predictive monitoring. It has been possible to set up the centralised control system because of the development in computerised equipment and systems, but it has only been possible to operate this system because of the capacity of the personnel to adapt to the changeover to technology. (author)

French industrial capabilities for the back-end operations

International Nuclear Information System (INIS)

Caspar, Gilles A.

1988-01-01

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

The Citizen Observatory of Radioactivity - Assessment for 2010 of radioactivity survey in the environment at the scale of Normandy (coast and waterways) - Results of measurement of gamma emitters and of Tritium in water

International Nuclear Information System (INIS)

2012-01-01

This document proposes a set of tables containing different information and data regarding measurements of gamma radioactivity and of the presence of tritium made during 2010 in different marine and water environments (algae, sands, sea water, molluscs, sediments, water mosses, vegetal) in different locations: a bay close to the AREVA plant in La Hague, different locations on the Normandy coast, around the AREVA plant in La Hague, and in waterways in Normandy. These tables contain information about the sampling (date, location, quantity, analysed fraction, and so on) and results of measurements of artificial (isotopes of cobalt, ruthenium-rhodium, silver, iodine, caesium, americium, europium) and natural (potassium, beryllium, lead, bismuth, etc.) radionuclides

Application of steric exclusion chromatography for the separation of degradation products of the solvent used for the reprocessing of the nuclear fuels; Application de la chromatographie d`exclusion sterique a la separation de produits de degradation du solvant du retraitement des combustibles nucleaires

Energy Technology Data Exchange (ETDEWEB)

Pozo, C.

1993-08-01

The solvent, used in France in Purex reprocessing plants at La Hague is tributylphosphate (TBP) diluted to 30% with a mixture of branched alkanes, for which the main component is branched dodecane (70%). In order to minimize volumes of organic wastes, we have to maintain Purex solvent qualities and to get rid of degradation products. The subject of this memoir concerns among all the degradation products the heaviest molecules. The separation and the identification of these products have been carried out by preparative steric exclusion chromatography, followed by the analysis of the samples by various analytical methods. An inactive residue containing heavy degradation products was prepared according to the process used in the UP3 La Hague plant. The Analysis of this residue using steric exclusion chromatography and GPC/MS methods, shows the presence of three families of compounds heavier than TBP: the ``dimers of TBP`` (provided from the addition of two molecules of TBP), the ``TBP-alkanes`` (the main molecule is the result of the addition of dodecane with TBP), and ``the functionalized TBP`` (hydroxyled TBP, nitrous TBP, nitrated TBP). Plutonium (IV) retention tests were made on the various fractions generated by steric chromatography. They showed that ``the dimers of TBP`` and ``the functionalized TBP`` families are responsible for that retention. These results confirm the good efficiency of the solvent distillation system operated in UP3 plant which allow the elimination of heavy degradation products of the solvent with the residue and then restore excellent extracting properties for the recycled solvent. (author). 35 figs., 69 refs., 15 tabs.

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

The Citizen Observatory of Radioactivity - Assessment of results for the second half-year 2008 - Measurement of gamma emitters and tritium in water

International Nuclear Information System (INIS)

2010-01-01

This document proposes a set of tables containing different information and data regarding measurements of gamma radioactivity, of tritium level in different marine and water environments (algae, sands, sea water, molluscs, sediments, water mosses, vegetal) in different locations for the second half-year 2008: a bay close to the AREVA plant in La Hague, different locations on the Normandy coast, around the AREVA plant in La Hague, waterways in Normandy and near the Brennilis nuclear power station in Brittany. These tables contain information about the sampling (date, location, quantity, analysed fraction, and so on) and results of measurements of artificial (isotopes of cobalt, ruthenium-rhodium, silver, iodine, caesium, americium, europium) and natural (potassium, beryllium, lead, bismuth, etc.) radionuclides

The Citizen Observatory of Radioactivity. Assessment of results of the first half-year 2008 - Gamma and Tritium

International Nuclear Information System (INIS)

2009-01-01

This document proposes a set of tables containing different information and data regarding measurements of gamma radioactivity, of Tritium level in different marine and water environments (algae, sands, sea water, molluscs, sediments, water mosses, vegetal) in different locations for the first half-year 2008: a bay close to the AREVA plant in La Hague, different locations on the Normandy coast, around the AREVA plant in La Hague, waterways in Normandy and near the Brennilis nuclear power station in Brittany. These tables contain information about the sampling (date, location, quantity, analysed fraction, and so on) and results of measurements of artificial (isotopes of cobalt, ruthenium-rhodium, silver, iodine, caesium, americium, europium) and natural (potassium, beryllium, lead, bismuth, etc.) radionuclides

Lichens as indicators of tritium and radiocarbon contamination

International Nuclear Information System (INIS)

Daillant, Olivier; Kirchner, Gerald; Pigree, Gilbert; Porstendorfer, Justin

2004-01-01

Lichens were collected in France in the surroundings of a military nuclear facility in Burgundy, near the la Hague reprocessing plant and in an area away from any direct source of contamination. Organically bound tritium (OBT) has been analysed on 18 samples and radiocarbon on 11. It appeared that on the most contaminated spots, the OBT activity in lichens was higher than the background by a factor of 1000 and was still a factor 10-100 at a distance of 20 km from the source. Radiocarbon from la Hague could be traced by lichens. The slow metabolism of lichens makes them suitable for the follow-up of 3 H and 14 C, which have been incorporated by photosynthesis

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

International Nuclear Information System (INIS)

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

1997-01-01

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

Nuclear material control and accountancy in a spent fuel storage ponds

International Nuclear Information System (INIS)

Gurle, P.; Zhabo, Dgh.

1999-01-01

The spent fuel storage ponds of a large reprocessing plant La Hague in France are under safeguards by means of a wide range of techniques currently used. These techniques include the nuclear material accountancy an containment/surveillance (C/S). Nondestructive assay, design information verification, and authentication of equipment provided by the operator are also implemented. Specific C/S equipment including video surveillance and unattended radiation monitoring have been developed and implemented in a spent fuel pond of La Hague. These C/S systems named EMOSS and CONSULHA with high degree of reliability and conclusiveness provide the opportunity to improve the efficiency of safeguards, particularly as related to spent fuel storage areas where the accountancy is verified by item counting [ru

The Citizen Observatory of Radioactivity - Assessment of results - Measurement of gamma emitters. Year 2009

International Nuclear Information System (INIS)

2010-01-01

This document proposes a set of tables containing different information and data regarding measurements of gamma radioactivity made during the first and second half-year of 2009 in different marine and water environments (algae, sands, sea water, molluscs, sediments, water mosses, vegetal) in different locations: a bay close to the AREVA plant in La Hague, different locations on the Normandy coast, around the AREVA plant in La Hague, waterways in Normandy and in other river near the Chinon and Civaux nuclear power stations. These tables contain information about the sampling (date, location, quantity, analysed fraction, and so on) and results of measurements of artificial (isotopes of cobalt, ruthenium-rhodium, silver, iodine, caesium, americium, europium) and natural (potassium, beryllium, lead, bismuth, etc.) radionuclides

Report of the study grou: Data Processing in Reprocessing Plants

International Nuclear Information System (INIS)

1976-08-01

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

Analysis by the IRSN of the Tritium concentration measured by the ACRO in a seawater sampling from the Ecalgrain bay on the 17 October 2012

International Nuclear Information System (INIS)

2013-01-01

As the ACRO published a result of seawater analysis performed on a sample taken in the Ecalgrain bay at the vicinity of the La Hague plant (this analysis revealed a very high level of Tritium in seawater), this document reports and comments the results obtained by the nearest IRSN measurement station since 1997. The authors outline the complex influence of numerous factors (meteorological conditions, sea currents, tides, and so on). They present the results obtained by a computation code which has been developed to predict the dispersion of La Hague releases. They compare the levels thus computed and the results published by the ACRO, and state that important differences may exist between two relatively close sites due to meteorological and sea conditions

The Hague Recommendations: Improving Nonlegislative Responses to Trafficking in Human Beings for the Purpose of Organ Removal.

Science.gov (United States)

Ambagtsheer, Frederike; Weimar, Willem

2016-02-01

Over the years, the trade in human organs has become an object of international concern. Since the 1980s, antiorgan trade initiatives have mainly involved the strengthening of legislative responses. Little attention however is given to nonlegislative responses by law enforcement authorities. The HOTT project is a European Union-funded research project titled "trafficking in human beings for the purpose of organ removal." Its objectives are to increase knowledge, raise awareness, and improve the nonlegislative response to the crime. Its consortium organized a "Writers' Conference" in The Hague, The Netherlands at Europol's Headquarters where a group of 40 experts, consisting of transplant professionals, law enforcement officials, and policy makers, formulated recommendations to improve nonlegislative responses. These recommendations, presented hereafter, address the ethical and legal obligations of health care providers, the protection of persons trafficked for the purpose of organ removal, strengthening cross-border collaboration in criminal cases, and stimulating partnerships between transplant professionals and law enforcement. These recommendations offer ways in which transplant professionals can contribute to improving the nonlegislative response to trafficking in human beings for the purpose of organ removal.

The reprocessing of irradiated fuels improvement and extension of the solvent extraction process; Le traitement des combustibles irradies amelioration et extension du procede utilisant les solvants

Energy Technology Data Exchange (ETDEWEB)

Faugeras, P; Chesne, A [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1964-07-01

Improvements made in the conventional tri-butylphosphate process are described, in particular. the concentration and the purification of plutonium by one extraction cycle using tri-butyl-phosphate with reflux; and the use of an apparatus working continuously for precipitating plutonium oxalate, for calcining the oxalate, and for fluorinating the oxide. The modifications proposed for the treatment of irradiated uranium - molybdenum alloys are described, in particular, the dissolution of the fuel, and the concentration of the fission product solutions. The solvent extraction treatment is used also for the plutonium fuels utilized for the fast breeder reactor (Rapsodie) An outline of the process is presented and discussed, as well as the first experimental results and the plans for a pilot plant having a capacity of 1 kg/day. The possible use of tn-lauryl-amine in the plutonium purification cycle is now under consideration for the processing plant at La Hague. The flowsheet for this process and its performance are presented. The possibility of vitrification is considered for the final treatment of the concentrated radioactive wastes from the Marcoule (irradiated uranium) and La Hague (irradiated uranium-molybdenum) Centers. Three possible processes are described and discussed, as well as the results obtained from the operation of the corresponding experimental units using tracers. (authors) [French] On decrit les ameliorations apportees au procede classique utilisant le phosphate tributylique, et notamment la concentration et la purification du plutonium par un cycle d'extraction au tributylphosphate avec reflux, l'utilisation d'un appareillage continu de precipitation d'oxalate de plutonium, de calcination de l'oxalate, et de fluoration de l'oxyde. On presente les modifications envisagees pour le traitement des alliages uranium-molybdene irradies, principalement en ce qui concerne la dissolution du combustible et la concentration des solutions de produits de fission

Citizen surveillance of the radioactivity in Normandy. Synthesis of gamma analysis results of the first semester 2004 from the Citizen network of watching, information and radioecological evaluation (R.I.V.I.E.R.E.); Surveillance citoyenne de la radioactivite en Normandie. Synthese des resultats d'analyse gamma du premier semestre 2004 du Reseau Citoyen de Veille, d'Information et d'Evaluation RadioEcologique (RIVIERE)

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-03-15

Around nuclear installations of La Hague, it is principally cesium{sup 137} that is found. The concentration is a few becquerels by kilogram of dry matter and comes from the fallout of nuclear tests before Chernobylsk accident. An excess of cesium is visible in the Sainte-Helene river where the levels go over the usual levels of a factor 10 then, in the presence of others elements such cobalt 60 (Co{sup 60}) or ruthenium-rhodium 106 (RuRh{sup 106}), iodine 129 (I{sup 129}) is also found. These pollutants find their origin in the gaseous releases of reprocessing plants. Between Granville and Saint Valery-en-Caux, along 500 kilometers of coast, four radioelements are systematically detected: cobalt 60, iodine 129, cesium 137, americium 214. Near the reprocessing plant of La Hague, the artificial radioactivity level increases with the presence of ruthenium-rhodium 106. The radiological situation is near this one of previous semesters, we can speak of stationary state, which improved with the years. It emphasize that the impact of nuclear power plants releases near the coast is not discernible. (N.C.)

Estimation of the risk of radiation-induced leukaemia among young people in the vicinity of the La Hague reprocessing plant. Results from the nord-cotentin radioecological study

International Nuclear Information System (INIS)

Rommens, C.; Laurier, D.; Merle-Szeremeta, A.; Sugier, A.; Drombry-Ringeard, C.

2000-01-01

A radioecological study has been performed around the La-Hague nuclear reprocessing plant (Nord-Cotentin, France). The Working Group included nuclear operators, authorities, international experts and members of environmental organisations and was supported by IPSN. The study aimed to reconstruct radiation doses received by members of the public aged 0 to 24 years and living in the area, with a view to estimate the associated risk of leukaemia between 1978 and 1996. The assessment involved three steps: 1. reconstruction of a cohort of people aged 0 to 24 years, using local birth rates for the years 1954 to 1996 and taking into account the additional migrations of young people in the area. 2. estimation of doses to the red bone marrow received from all source of radiation (natural, medical, local nuclear industries and Chernobyl and weapons testing). Concentrations of radionuclides in the environment were estimated with a combination of two approaches: the modelling of the transfer of the releases in the environment and the use of environmental measurements. The dose computation takes into account the life style of the local population. ICRP dose coefficients to the red bone marrow were used. 3. derivation of leukaemia risk from a dose response model recommended by the UNSCEAR committee. The reconstructed population includes 6656 people born between 1954 and 1996, who inhabited the study area for at least one year between 1978 and 1996 before the age of 25. The number of person-years between 1978 and 1996 is 69308. The total collective dose to the red bone marrow due to local nuclear installations is 0.5 man.Sv. For the sake of comparison, the collective dose due to all sources of exposure is 241 man.Sv: The estimated number of leukaemia due to all exposure sources is 0.835. 74% are due to natural exposures, 24% to medical ones and 2% to the Chemobyl accident and nuclear arm testing. Nuclear facilities of Nord-Cotentin contribute only for 0.1% (between 0.0009 and 0

Inter-CLI work-group: safety after Fukushima; GT inter-CLI 'surete post Fukushima'

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-11-03

This document contains a whole set of questions asked about nuclear safety and security by a work-group made of members of associations belonging to local information commissions. These questions are asked either to the French State, or to EDF, or to AREVA. They bear on general issues common to La Hague and Flamanville nuclear installations, notably public information, emergency plans, post-accident management, subcontracting, loss of electricity supply, public health, governance, computer hacking, extreme meteorological events. A set of questions concerns the AREVA processing plant in La Hague (warehousing, pools for irradiated fuels, plutonium oxide storage and warehousing, and so on), and another set concerns the Flamanville nuclear power plant (different aspects of the management of a crisis situation). The last set of questions concerns the Manche nuclear waste storage centre

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

Research document no. 27 bis. After the Hague, Bonn and Marrakech: the future international market for emissions permits and the issue of hot air; Cahier de recherche no. 27. Apres La Hague, Bonn et Marrakech: le futur marche international des permis de droits d'emissions et la question de l'air chaud

Energy Technology Data Exchange (ETDEWEB)

Blanchard, O.; Criqui, P.; Kitous, A

2002-01-01

The main objective of this paper is to assess the Bonn-Marrakech agreement, in terms of abatement cost and emission trading as compared with the initial agreement reached in Kyoto (the Kyoto Protocol). Our reference case (the Initial Deal) does not include the use of sinks credits, as the Kyoto Protocol does not give explicit figures nor method to estimate them. In addition, two hypothetical situations are considered. The first describes the ''missed compromise'' that could have emerged among all Parties in November 2000 in The Hague. The second is a virtual case where the US is assumed to be part of the Bonn-Marrakech Agreement, along with all the other Parties. These two cases contribute to shed the light on the Bonn-Marrakech Agreement potential pitfalls. In the current situation, the US is out of the negotiation process and has no emission reduction commitment. Given the projections of carbon dioxide (CO{sub 2}) emissions used in this study, the Former Soviet Union countries (FSU) and the Eastern European Economies (EEE) that are part of the Annex B have potentially enough Hot Air to fulfill the overall commitment of the Annex B bubble, without any domestic abatement effort from the other Annex B countries. We show that in the theoretical case where no limit would be imposed on the selling of Hot Air, the permit price according to the POLES model would be zero as no market equilibrium could take place. This is why, next, we examine the economic impacts of restrictions to hot air trading, for FSU and EEE as well as for the other countries. We shed the light on the potential market power of the former countries that arises from the Bonn-Marrakech Agreement. (author)

The Hague Recommendations: Improving Nonlegislative Responses to Trafficking in Human Beings for the Purpose of Organ Removal

Science.gov (United States)

Ambagtsheer, Frederike; Weimar, Willem

2016-01-01

Abstract Over the years, the trade in human organs has become an object of international concern. Since the 1980s, antiorgan trade initiatives have mainly involved the strengthening of legislative responses. Little attention however is given to nonlegislative responses by law enforcement authorities. The HOTT project is a European Union-funded research project titled “trafficking in human beings for the purpose of organ removal.” Its objectives are to increase knowledge, raise awareness, and improve the nonlegislative response to the crime. Its consortium organized a “Writers' Conference” in The Hague, The Netherlands at Europol's Headquarters where a group of 40 experts, consisting of transplant professionals, law enforcement officials, and policy makers, formulated recommendations to improve nonlegislative responses. These recommendations, presented hereafter, address the ethical and legal obligations of health care providers, the protection of persons trafficked for the purpose of organ removal, strengthening cross-border collaboration in criminal cases, and stimulating partnerships between transplant professionals and law enforcement. These recommendations offer ways in which transplant professionals can contribute to improving the nonlegislative response to trafficking in human beings for the purpose of organ removal. PMID:27500254

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

After the Hague, Bonn and Marrakech: uncertainties on the future international market of emission permits

International Nuclear Information System (INIS)

Kitous, A.; Criqui, P.; Blanchard, O.

2002-01-01

The purpose of this article is to present an economic assessment, step by step, of the successive developments of the negotiation on weather changes since the Kyoto protocol in 1997 until the agreement achieved in Marrakech during the seventh Conference of the Parties (COP 7) in November 2001. The analysis covers the international market of emission rights, a key mechanism of the Protocol, the purpose of which is to facilitate the Parties' compliance with their undertakings, by introducing flexibility to improve the economic efficiency of emission reduction. However, it now appears that despite the Marrakech agreement in November 2001, the system is weakened by the withdrawal of the USA decided by President G.W. Bush in March 2001, following COP 6 in The Hague, and by a potential excess of permits due to the economic recession of transition countries since the early nineties (hot air). As things stands, the establishment of the market between the countries taking part in the process will undoubtedly require some management of this hot air between transition countries (Eastern Europe and Ex USSR) and the other Parties of appendix B still involved in the process. The uncertainties weighing on the future market of emission permits strengthen the strategic significance of the implementation of effective reduction policies within those regions and particularly within Europe. (authors)

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

International Nuclear Information System (INIS)

Cau Dit Coumes, C.

1998-01-01

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

Cross border transport of vitrified residues from France to Germany

International Nuclear Information System (INIS)

Graf, W.; Jussofie, A.

2016-01-01

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

Fuel reprocessing: safety analysis of extraction cycles

International Nuclear Information System (INIS)

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

1991-01-01

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

Calibration of measurement instruments in industrial irradiation environment

International Nuclear Information System (INIS)

Cadiou, A.

2009-01-01

After having recalled the activities of the AREVA NC site in La Hague and its organization, the author describes the missions of the Calibration Laboratory within this establishment, its methods, its metrological means, and outlines the traceability of results

Detecting child abuse based on parental characteristics: does the Hague Protocol cause parents to avoid the emergency department?

Science.gov (United States)

Diderich, Hester M; Fekkes, Minne; Dechesne, Mark; Buitendijk, Simone E; Oudesluys-Murphy, Anne Marie

2015-04-01

The Hague Protocol is used by professionals at the adult Emergency Departments (ED) in The Netherlands to detect child abuse based on three parental characteristics: (1) domestic violence, (2) substance abuse or (3) suicide attempt or self-harm. After detection, a referral is made to the Reporting Center for Child Abuse and Neglect (RCCAN). This study investigates whether implementing this Protocol will lead parents to avoid medical care. We compared the number of patients (for whom the Protocol applied) who attended the ED prior to implementation with those attending after implementation. We conducted telephone interviews (n = 14) with parents whose children were referred to the RCCAN to investigate their experience with the procedure. We found no decline in the number of patients, included in the Protocol, visiting the ED during the 4 year implementation period (2008-2011). Most parents (n = 10 of the 14 interviewed) were positive and stated that they would, if necessary, re-attend the ED with the same complaints in the future. ED nurses and doctors referring children based on parental characteristics do not have to fear losing these families as patients. Copyright © 2014 Elsevier Ltd. All rights reserved.

Las rivalidades hispano-neerlandesas en el Pacífico y la conquista de Australia: de Cornelis de Houtman a Abel Janszoon Tasman (1595-1651

Directory of Open Access Journals (Sweden)

Crespo Solana, Ana

2013-12-01

Full Text Available Early in the 17th century, the VOC —Verenigde Oostindische Compagnie— attempted to identify new places where commercial factories could be built as well as a new route to sail between New Guinea and the Pacific. A general introduction will describe the reasons of for these journeys, and the causes behind the expeditions. Specialised bibliography will be used, including reports, memorials as well as documents from the archives of the East India Dutch Company (VOC Archief located in the National Archives in The Hague.A comienzos del siglo XVII la Verenigde Oostindische Compagnie (VOC pretendía localizar nuevos enclaves que sirvieran como factorías mercantiles y abrir una vía entre Nueva Guinea y el Pacífico. Se realizará una introducción general sobre las razones de estos viajes y un análisis de las causas que motivaron las expediciones holandesas. Se utilizará bibliografía especializada, memoriales e informes de la época, así como documentos del Archivo de la Compañía Holandesa de las Indias Orientales (VOC Archief que se encuentran en el Archivo Nacional de La Haya.

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

International Nuclear Information System (INIS)

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

1994-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Mercier, J P [DES/SESUL (France)

1992-02-01

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

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.)

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-10-15

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

The cobalt radioactive isotopes in environment

International Nuclear Information System (INIS)

2007-01-01

For the year 1993 the total activity released in cobalt is 69 GBq for the whole of nuclear power plants. The part of activity in cobalt for La Hague in 1993 is 8 GBq of 58 Co and 2 GBq of 60 Co. The radioactive isotopes released by nuclear power plants or the reprocessing plant of La Hague under liquid effluents are shared by half between 58 Co and 60 Co. The exposure to sealed sources is the most important risk for the cobalt. The risk of acute exposure can associate a local irradiation of several decades of grays inducing a radiological burns, deep burn to treat in surgery by resection or graft even amputation. A global irradiation of organism for several grays induces an acute irradiation syndrome, often serious. At long term the stochastic effects are represented by leukemia and radio-induced cancers. The increase of probability of their occurrence is 1% by sievert. We must remind that the natural spontaneous probability is 25%. (N.C.)

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

International Nuclear Information System (INIS)

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

1991-01-01

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

Determination of zirconium 93 and molybdenum 93 in reprocessing nuclear waste

International Nuclear Information System (INIS)

Puech, P.

1998-01-01

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

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

International Nuclear Information System (INIS)

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

2004-01-01

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

Stakeholder involvement in the management of effluent discharges from nuclear installations in France

International Nuclear Information System (INIS)

Schneider, T.; Gadbois, S.; Heriard Dubreuil, G.; Oudiz, A.

2004-01-01

The involvement of local stakeholders in the decision-making process regarding health, safety and environmental issues is developing in many countries. As far as the management of effluent discharges from nuclear installations in France is concerned, members of Local Commission of Information, including elected people and NGOs, are playing an increasing role in that respect. To deepen the understanding of these risk governance processes, a working group of experts from different institutions was set up in 2000 by the Institute of Radiation Protection and Nuclear Safety (IRSN). The aim of this working group was to 1) analyse the stakeholder involvement processes already in place in France around nuclear and non-nuclear installations; 2) perform case studies of few national and international experiences around nuclear installations (notably concerning the revision of creation authorisation decree of COGEMA La Hague reprocessing plant, the environmental policy of BNFL Sellafield reprocessing plant, the discharges surveillance of EDF Fessenheim nuclear power plant); 3) study the evolution of the regulatory context for the stakeholder involvement. Four main elements, contributing to the social trust emerge from this analysis: 1) the social dynamics of the consultation process, notably with the emergence of 'new' stakeholders such as elected people and NGOs; 2) the readability of the plant follow-up from the point of view of local stakeholders and their involvement in the decision process (the relay role of these 'new' stakeholders); 3) the contribution of the institutional and pluralist expertise to the social trust (broadening of the range of values taken into account); 4) the issue of the local justification of the plant in the prospect of the sustainable development (no risk being acceptable without counter-parts). This paper will address these different issues on the basis of the case studies in the perspective of examining the radiological risk governance process

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.)

Interpretando el proceso de multiculturalidad en España y la propuesta de ciudadanía cívica de la UE

Directory of Open Access Journals (Sweden)

Zapata-Barrero, Ricard

2005-06-01

Full Text Available We are living an Historical Time characterized by the international migrations. The arrival and permanence of people coming mainly from developing countries increasingly make clear that the current instruments to manage conflicts coming from modernity have difficulties to work with normality. Following the approach of change of paradigm of modernity as interpretation approach (1, i emphasize the three main indicators of multiculturality in Spain: use of populist arguments on the part of traditional political parties, bond between two processes of multiculturalidad: the multinationality and immigration, secularism or the management of religious pluralism (2. My final intention (3 is to underline how this debate also helps us to identify a new fracture within the UE between one more an opened (innovation and closed (tradition policy of immigration. In the end I will do a final balance transferring this dilemma between tradition and innovation in the new frame of immigration policies: the Hague program initiated in November of 2004.

Estamos viviendo un Tiempo Histórico caracterizado por las migraciones internacionales. La llegada y permanencia de personas procedentes mayoritariamente de países en vías de desarrollo ponen cada vez más en evidencia que los instrumentos habituales para gestionar conflictos procedentes de la modernidad tienen dificultades para funcionar con normalidad. Siguiendo el enfoque de cambio de paradigma de la modernidad como enfoque para la interpretación (1, destaco los tres principales indicadores de multiculturalidad en España: uso de argumentos populistas por parte de partidos políticos tradicionales, vínculo entre dos procesos de multiculturalidad: la multinacionalidad y la inmigración, secularismo o la gestión del pluralismo religioso (2. Mi propósito final (3 es destacar cómo este debate nos ayuda también a identificar una nueva fractura dentro de la UE entre una política más abierta (innovación y

Needs and opportunities of adequate interpretation of the Hague convention on the civil aspects of international child abduction in the case of domestic violence

Directory of Open Access Journals (Sweden)

Samardžić Sandra

2013-01-01

Full Text Available At the time when the Hague Convention on the Civil Aspects of International Child Abduction was passed, that was a very logical step and a goal that this Conventionis set before it, and that is prompt return of children wrongfully removed or retained children, was a necessary consequence of the circumstances of that time. Namely, in most cases, men, that is fathers, were those, who illegally took or kept the children. More than thirty years later, the situation in that field has changed in the sense that mothers are now abductors in most cases, mostly seeing that this is the only way to escape from the violence they, or their children, are facing with. In that sense, the question is whether the achievement of the objective of this Convention is still justified, that is would it be justified any other interpretation of the Convention in situations where the unlawful removal or retention of children is a result of domestic violence.

Creation, synthesis and characterisation of nitrogenous poly-heterocyclic new molecules for specific complexation of metallic cations; Conception, synthese et caracterisation de molecules polyheterocycliques azotees pour la complexation specifique de cations metalliques

Energy Technology Data Exchange (ETDEWEB)

Dupont, C.

2010-12-10

In France, the nuclear waste issued from the industrial reprocessing of spent nuclear fuels (by the PUREX process) are currently vitrified at the La Hague plant, waiting for a final disposal in a deep geological repository. The law voted in June 2006 on the management of highly active nuclear waste plans to look for solutions enabling the separation and transmutation of long-lived radionuclides so as to reduce the quantity and noxiousness of the final nuclear waste. To address this issue, the CEA investigates and elaborates advanced separation processes based on specially designed complexing or extracting molecules to selectively extract minor actinides from PUREX raffinates containing fission products like lanthanides, which are neutron scavengers. BTP or bis-triazinyl-pyridines have been extensively studied at the CEA (and in Europe) for actinides(III)/lanthanides(III) separation. They complex actinides(III) selectively. However, they are sensitive to degradation by hydrolysis and radiolysis. Besides, their separation mechanisms are not well understood, especially the influence of their substituting groups on their complexing and extracting properties. The first part of work reports the syntheses of various BTP and BTBP molecules, differently substituted, as well as a new family of poly-aromatic nitrogen-contained ligands: BPBT, presenting a pyridine/triazine sequence that has never been reported in the literature. The second part is devoted to the physico-chemistry studies of the synthesized molecules, such as the determination of their protonation and complexation constants to describe the influence of different substituting groups. Finally, the last part outlines solvent extraction studies by using these ligands either like extractants or like complexants. (author) [French] Resume: La loi du 6 juin 2006 sur la gestion des dechets radioactifs de haute activite et a vie longue prevoit la recherche de solutions permettant la separation et la transmutation des

The organic waste treatment in UP3 - La Hague

International Nuclear Information System (INIS)

Pradel, P.; Dalverny, G.; Lebaillif, M.; Moulin, J.P.; Ginisty, C.; Leybros, J.; Maynadier, P.

1991-01-01

The management of the solvent in the reprocessing plants has always been a difficult problem. Various process reasons lead to discard some contaminated solvent: this spent solvent is an organic waste the volume of which must be minimized. To solve this problem for the UP3 plant, it has been decided to implement a distillation facility in order to split this spent solvent into three parts: recovered diluent and concentrated TBP, to be recycled in the extraction process, and a residue which contain the radioactivity and most of the impurities. As the TBP is not highly volatile and as it is a thermosensitive compound, this distillation is performed at low pressure and temperature, with thin films evaporators, in order to minimize the residence times in heated zones. The paper describes the selected process and the equipment employed. The R and D work which has been performed to define the process, size up the equipment and demonstrate the process is described, including the laboratory works, the pilot plant tests and the results of tests performed with a full scale prototype which has been built to demonstrate the whole process. The industrial facility is described, and the results of the first active runs are described briefly. (author)

Safety highlights of UP2 reprocessing in La Hague

International Nuclear Information System (INIS)

Marc, A.; Dubois, G.

1998-01-01

The UP2-800 reprocessing plant basically implements the same proven process (PUREX) as UP3 plant. However, some evolutions and additions have been realised: - to reprocess high burn up and MOX fuel assemblies; - to dissolve scraps from reprocessing facilities or from the fabrication of MOX fuels such as UO 2 - PuO 2 powders; - to recover plutonium from ash resulting from alpha waste incineration prior to ash conditioning; - to reduce solid waste alpha activity below the regulatory limits for shallow land disposal. Safety considerations relating to these functions have been taken into account in each step of process design. Safety design rules have been implemented for the UP2-800 plant with the same goals as for the UP3 plant: - keeping the discharge of radioactive liquids and gas within the annual limits authorized under normal operating conditions; - reducing the personnel exposure to a minimum so that 'the number of operators whose integrated dose over a year exceeds 5 mSv be nil or practically nil under normal operating conditions'; - preventing the accidental situations and having at one's disposal the dysfunction monitoring and detection systems and the means to limit their consequences. Particular risks prevention related to the UP2-800 specific functions are described in this paper. (author)

The organic waste treatment in UP3-La Hague

International Nuclear Information System (INIS)

Ginisty, C.; Leybros, J.; Maynadier, P.; Pradel, P.; Dalverny, G.; Lebaillif, M.

1991-01-01

Spent solvent is an organic waste the volume of which must be minimized. It has been decided to implement a distillation facility in order to split this spent solvent into three parts: recovered diluent and concentrated TBP, to be recycled, and a residue which contain the radioactivity and most of the impurities. This distillation is performed at low pressure and temperature, with thin films evaporators, in order to minimize the residence times in heated zones. The paper describes the process and the equipment employed. The R and D work which has been performed to define the process, size up the equipment and demonstrate the process is described, including the laboratory works, the pilot plant tests and the results of tests performed with a full scale prototype which has been built to demonstrate the whole process. The industrial facility, and the results of the first active runs are described briefly

Citizen surveillance of the radioactivity in Normandy. Synthesis of gamma analysis results of the first semester 2004 from the Citizen network of watching, information and radioecological evaluation (R.I.V.I.E.R.E.)

International Nuclear Information System (INIS)

2006-03-01

Around nuclear installations of La Hague, it is principally cesium 137 that is found. The concentration is a few becquerels by kilogram of dry matter and comes from the fallout of nuclear tests before Chernobylsk accident. An excess of cesium is visible in the Sainte-Helene river where the levels go over the usual levels of a factor 10 then, in the presence of others elements such cobalt 60 (Co 60 ) or ruthenium-rhodium 106 (RuRh 106 ), iodine 129 (I 129 ) is also found. These pollutants find their origin in the gaseous releases of reprocessing plants. Between Granville and Saint Valery-en-Caux, along 500 kilometers of coast, four radioelements are systematically detected: cobalt 60, iodine 129, cesium 137, americium 214. Near the reprocessing plant of La Hague, the artificial radioactivity level increases with the presence of ruthenium-rhodium 106. The radiological situation is near this one of previous semesters, we can speak of stationary state, which improved with the years. It emphasize that the impact of nuclear power plants releases near the coast is not discernible. (N.C.)

The cobalt radioactive isotopes in environment; Les isotopes radioactifs du cobalt dans l'environnement

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

For the year 1993 the total activity released in cobalt is 69 GBq for the whole of nuclear power plants. The part of activity in cobalt for La Hague in 1993 is 8 GBq of {sup 58}Co and 2 GBq of {sup 60}Co. The radioactive isotopes released by nuclear power plants or the reprocessing plant of La Hague under liquid effluents are shared by half between {sup 58}Co and {sup 60}Co. The exposure to sealed sources is the most important risk for the cobalt. The risk of acute exposure can associate a local irradiation of several decades of grays inducing a radiological burns, deep burn to treat in surgery by resection or graft even amputation. A global irradiation of organism for several grays induces an acute irradiation syndrome, often serious. At long term the stochastic effects are represented by leukemia and radio-induced cancers. The increase of probability of their occurrence is 1% by sievert. We must remind that the natural spontaneous probability is 25%. (N.C.)

Plutonium diffusion in the marine environment: a quantitative study on marine species of the channel shores, from Brest (St Mathieu Point) to Honfleur

International Nuclear Information System (INIS)

Fraizier, Albert; Guary, J.-C.

1977-03-01

Plutonium levels were measured on marine species of the Channel shores, from Cancale to Honfleur in 1975, from Brest to the Cap de La Hague in 1976. Measurements carried out on a lichen: Lichina pygmaea, two algae: Corallina officinalis and Fucus serratus, a spongiae: Hymeniacidon sanguinea and a crustacean: Balamus balanoides, showed the effect of waste disposal from La Hague fuel reprocessing plant on the radioactivity levels of these organisms. This effect, decreasing progressively, appeared at distances of about 150 km from the point of release. As compared to value observed for samples taken at the far West of Brittany and to plutonium levels in the marine environment resulting from atmospheric fallout only, the levels observed in the studied area were higher and varying according to the geographic position, increasing by a factor of 100 near the emissary. These data are an actual instance of radioactive dispersal following disposal into the sea; they should bring valuable information for the assessment of the radiological capacity of a given coastal area [fr

The iodine reactivity; La reactivite de l'iode

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

The iodine is an important element because it has long life isotopes (such as iodine 129) and a great mobility in natural media. Iodine presents a complex chemistry because of its volatility and its strong redox reactivity. The S.E.C.R. works to better understand the reactivity of this element in different natural, industrial or biological environments. It plays a part in thermochemical sites as a possible way of hydrogen formation. This seminar gives some aspects relative to the chemical reactivity of iodine, since its thermochemistry in the I/S cycles to produce hydrogen to its reactivity in the natural medium and its potential radiological impact. This document includes 4 presentations transparencies dealing with: the {sup 129}I cycle rejected in the low radioactive gaseous and liquid effluents of the La Hague reprocessing plant (C. Frechou); a bibliographic review of iodine retention in soils (F. Bazer-Bachi); the hydrogen production and the iodine/sulfur thermochemical cycle (role of iodine in the process); and the direct characterization by electro-spray ionization mass spectroscopy of iodine fixation by fulvic acids (P. Reiller, B. Amekraz, C. Moulin, V. Moulin)

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

Headquarters Vienna

International Nuclear Information System (INIS)

1985-01-01

This film presents the IAEA safeguards system showing six inspectors at their work in the nuclear power plants Kozloduy (Bulgaria), Mihama (Japan) as well as in the reprocessing plant La Hague (France). The results of inspections are checked at the IAEA Headquarters in Vienna. The film shows all modern techniques applied in the IAEA safeguards system

Headquarters Vienna

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-12-31

This film presents the IAEA safeguards system showing six inspectors at their work in the nuclear power plants Kozloduy (Bulgaria), Mihama (Japan) as well as in the reprocessing plant La Hague (France). The results of inspections are checked at the IAEA Headquarters in Vienna. The film shows all modern techniques applied in the IAEA safeguards system

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)

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)

Experience and trends at the Belgonucleaire plant

International Nuclear Information System (INIS)

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

2000-01-01

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

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

A.C.R.O. activity report 2002

International Nuclear Information System (INIS)

2002-01-01

control organisation, with the Minister of health international colloquium on the risk management, S.F.R.P. congress on radiation protection, university colloquium on risk management, S.F.R.P. congress on carbon 14, S.F.R.P. congress I.R.P.A. european congress on radiation protection presentation of the working group in radiation protection, S.F.R.P. congress on evaluation and surveillance of radioactive releases of nuclear installations, european commission stake holders conference on approaches to the management of environmental radioactivity, ethical lesson and society at the national school of the Departments of civil engineering, think tank and working groups, participation to the local commission of information (C.L.I.) and in its regular publication 'the nuclear chronicle', participation to the superior council of nuclear safety and information (C.S.S.I.N.); about the environmental surveillance two environments are the object of a regular follow-up: the plateau of La Hague (reprocessing plant and Manche plant where are treated and stored radioactive waste), Touraine area where is situated the nuclear power plant of Chinon; Radio ecological follow through of the aquatic environment both continental and marine of the sea-coast of Normandy from 2001 to 2003; Radio ecological monitoring of the environment of the Cogema la Hague building site in the Moulinets cove; measurements of radon; inventory of the tritium levels in the drinking water of the Manche department; radiation monitoring of the effluents released by the hospitals in the town of Caen. (N.C.)

Gauging in volumetric activity of the L.B.123 in order to study release dispersion in 85Kr

International Nuclear Information System (INIS)

Label, D.

2001-01-01

The L.B.123 is a krypton detector. The calculations of the different beta and gamma yields have allowed to confirm that the LB123 is low sensitive to gamma radiations and in the case of krypton 85 the only beta contribution is to be considered. This detector can be used to study the dispersion modes of gaseous releases in the environment of La Hague. (N.C.)

Radiological monitoring. Controlling surface water pollution

International Nuclear Information System (INIS)

Morin, Maxime

2018-01-01

Throughout France, surface waters (from rivers to brooks) located at the vicinity of nuclear or industrial sites, are subject to regular radiological monitoring. An example is given with the radiological monitoring of a small river near La Hague Areva's plant, where contaminations have been detected with the help of the French IRSN nuclear safety research organization. The sampling method and various measurement types are described

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

Perspective on the French closed fuel cycle: Open towards energy future and sustainability

International Nuclear Information System (INIS)

Tinturier, Bernard; Debes, Michel; Delbecq, Jean-Michel

2006-01-01

Energy sustainability and nuclear energy nowadays are far reaching issues with many implications and as a consequence, any long term sustainable strategy needs to be flexible. In France, nuclear energy (427 TWh in 2004, 80% of national electricity production) is a major asset for clean electricity production and for meeting Kyoto protocol objective in France. The decision to build a future EPR reactor in France has been taken. Regarding back end and fuel cycle, the current reprocessing and recycling strategy, with the existing industrial system (Cogema La Hague and Melox), has proven to be reliable and efficient. It enables to meet sustainability requirements, now and in the long run: ensuring a good management of high level waste through vitrification, reducing the amount of nuclear spent fuel in interim storage, recycling valuable nuclear material (Pu), keeping the possibility to use Pu concentrated in MOX spent fuel to start FBR in the future. To maintain this possibility for the far future, EDF considers that the Generation IV program is of major importance in order to develop future fast reactors able to use plutonium and to ensure a full utilization of uranium resource, while optimizing high level waste management. EDF strategy is to keep the nuclear option open in the future, with a two-steps approach for the renewal of the current nuclear fleet: first, around 2020, with the launching of generation III reactors like EPR, and second, depending on the energy demand, launching of Generation IV systems, around 2040 or beyond. To meet this energy prospect, R and D efforts must be devoted to fast breeder reactors (sodium cooled, which benefits already from industrial experience, and gas cooled, under consideration for R and D). Globally, this strategy is open to future progress and optimisation as needed to meet long term energy sustainability. It appears the necessity of a good consistency between all the components of the nuclear system: reactors, fuel cycle

UP2 400 High Activity Oxide Legacy Waste Retrieval Project Scope and Progress-13048

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

The High Activity Oxide facility (HAO) reprocessed sheared and dissolved 4500 metric tons of light water reactor fuel the fuel of the emerging light water reactor spent fuel between 1976 and 1998. Over the period, approximately 2200 tons of process waste, composed primarily of sheared hulls, was produced and stored in a vast silo in the first place, and in canisters stored in pools in subsequent years. Upon shutdown of the facility, AREVA D and D Division in La Hague launched a thorough investigation and characterization of the silos and pools content, which then served as input data for the definition of a legacy waste retrieval and reconditioning program. Basic design was conducted between 2005 and 2007, and was followed by an optimization phase which lead to the definition of a final scenario and budget, 12% under the initial estimates. The scenario planned for the construction of a retrieval and reconditioning cell to be built on top of the storage silo. The retrieved waste would then be rinsed and sorted, so that hulls could subsequently be sent to La Hague high activity compacting facility, while resins and sludge would be cemented within the retrieval cell. Detailed design was conducted successfully from 2008 until 2011, while a thorough research and development program was conducted in order to qualify each stage of the retrieval and reconditioning process, and assist in the elaboration of the final waste package specification. This R and D program was defined and conducted as a response and mitigation of the major project risks identified during the basic design process. Procurement and site preparatory works were then launched in 2011. By the end of 2012, R and D is nearly completed, the retrieval and reconditioning process have been secured, the final waste package specification is being completed, the first equipment for the retrieval cell is being delivered on site, while preparation works are allowing to free up space above and around the silo, to

Safety assessment of UP3-A reprocessing plant

International Nuclear Information System (INIS)

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

1992-02-01

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

The reprocessing of irradiated fuels improvement and extension of the solvent extraction process

International Nuclear Information System (INIS)

Faugeras, P.; Chesne, A.

1964-01-01

Improvements made in the conventional tri-butylphosphate process are described, in particular. the concentration and the purification of plutonium by one extraction cycle using tri-butyl-phosphate with reflux; and the use of an apparatus working continuously for precipitating plutonium oxalate, for calcining the oxalate, and for fluorinating the oxide. The modifications proposed for the treatment of irradiated uranium - molybdenum alloys are described, in particular, the dissolution of the fuel, and the concentration of the fission product solutions. The solvent extraction treatment is used also for the plutonium fuels utilized for the fast breeder reactor (Rapsodie) An outline of the process is presented and discussed, as well as the first experimental results and the plans for a pilot plant having a capacity of 1 kg/day. The possible use of tn-lauryl-amine in the plutonium purification cycle is now under consideration for the processing plant at La Hague. The flowsheet for this process and its performance are presented. The possibility of vitrification is considered for the final treatment of the concentrated radioactive wastes from the Marcoule (irradiated uranium) and La Hague (irradiated uranium-molybdenum) Centers. Three possible processes are described and discussed, as well as the results obtained from the operation of the corresponding experimental units using tracers. (authors) [fr

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

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)

A.C.R.O. activity report 2003; A.C.R.O. rapport d'activite 2003

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

Normandy from 2001 to 2003; Radio ecological monitoring of the environment of the Cogema la Hague building site in the Moulinets cove;Inventory of the radioactivity of the catchment area and the Brest Harbour (achieved in march 2003); Radiological measures of the earthly environment of the establishment of the G.I.P. CYCERON in Caen year 2003; Radiological characterization of D.I.S. and technical aid in relation to the directive 96/29 EURATOM. (N.C.)

A.C.R.O. activity report 2003

International Nuclear Information System (INIS)

2003-01-01

2003; Radio ecological monitoring of the environment of the Cogema la Hague building site in the Moulinets cove;Inventory of the radioactivity of the catchment area and the Brest Harbour (achieved in march 2003); Radiological measures of the earthly environment of the establishment of the G.I.P. CYCERON in Caen year 2003; Radiological characterization of D.I.S. and technical aid in relation to the directive 96/29 EURATOM. (N.C.)

Immediate supervision of the coastal site at the La Hague centre

International Nuclear Information System (INIS)

Scheidhauer, J.

1968-01-01

The disposal into the sea of the residual waters from a plant processing irradiated fuels means that a very close watch has to be kept on the corresponding coastal zone. The material organisation of such a supervision, and the sampling techniques, are described. These latter concern: flora, fauna, sediments and sea-water. Results obtained using various analytical and routine measurement methods are presented. (author) [fr

On line measurements and process control for La Hague UP3

International Nuclear Information System (INIS)

Lamarque, G.; Frejaville, G.; Lavergne, J.

1987-01-01

A reprocessing plant is allowed of specialized work-rooms in varying functions: fuel receipt and storage, mechanical treatment, chemical dissolution, purification, waste treatment, waste conditioning. At the different reprocessing stages, it is necessary to know a big number of parameters to assure that each work-room works in a satisfactory condition with respect to safety, performances and nuclear matter management. In this paper the author gives an overview of the control methods used in UP3 [fr

Final closure of a low level waste disposal facility

International Nuclear Information System (INIS)

Potier, J.M.

1995-01-01

The low-level radioactive waste disposal facility operated by the Agence Nationale pour la Gestion des Dechets Radioactifs near La Hague, France was opened in 1969 and is scheduled for final closure in 1996. The last waste package was received in June 1994. The total volume of disposed waste is approximately 525,000 m 3 . The site closure consists of covering the disposal structures with a multi-layer impervious cap system to prevent rainwater from infiltrating the waste isolation system. A monitoring system has been set up to verify the compliance of infiltration rates with hydraulic performance objectives (less than 10 liters per square meter and per year)

20. ATSR congress - Book of abstracts

International Nuclear Information System (INIS)

1999-01-01

, CNRS, Nantes Univ.); - Conference: 16 - Works of art expertise using X-ray spectroscopy (Albert Adam, CEA-Saclay); - Effects on the organism: 17 - health issues with high level wastes (Jacques Lafuma, Academy of Sciences, Academy of Medicine); 18 - Summary of epidemiological studies of the leukemia risk near nuclear sites (Dominique Laurier, IPSN Fontenay-aux-Roses); 19 - Quantification of leukemia risk in relation with a chronic exposure to ionising radiations: lessons learnt by the Nord-Cotentin radioecological group (Catherine Rommens, Dominique Laurier, IPSN Fontenay-aux-Roses); - Radioecology: 20 - From radiation to risk: the Nord-Cotentin radioecological group model (Aurelie Merle-Szeremeta, Catherine Rommens, Caroline Drombry, IPSN Fontenay-aux-Roses); 21 - Interpretation of calculation code results about the radiological impacts of radioactive releases (Henri Maubert, SPR/CEA Cadarache); - Use of radiations at hospitals: 22 - Improvement of the radioactive waste management of a regional cancer centre (Sandrine Laugle, Jean-Claude Houy, Eugene Marquis Centre Rennes); 23 - Detection of a radioactive source in an incineration plant dumpster: decision-making study according to the activity calculation (Jean-Claude Houy, Sandrine Laugle, Eugene Marquis Centre Rennes); - Environment: 24 - Model or measurements: what strategy for an environmental contamination estimation? (Caroline Drombry-Ringeard, Hemispheres Egly, Catherine Rommens, IPSN Fontenay-aux-Roses); 25 - Radiological risks magnitude (Jean Charles ABBe, CNRS, Nantes Univ.); 26 - Radiological monitoring of La Hague site environment (Philipp Blaise, H. Truffert, Cogema La Hague); - Posters: Po 01 - Inter-laboratory comparison of French low-energy anthropo-diametric measurements (D. Franck, Ph. Berard, C. Dubiau, R. Soulie, IPSN Fontenay-aux-Roses); Po 02 - Modification principles of the CEA Cadarache radiological monitoring plan (Elodie Panaiva-Pouzol, Serge Escallon, Henri Maubert, SPR/CEA Cadarache)

Fast breeder reactor fuel reprocessing in France

International Nuclear Information System (INIS)

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

1984-08-01

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

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.)

Zirconium molybdate hydrate precipitates in spent nuclear fuel reprocessing

International Nuclear Information System (INIS)

Magnaldo, A.; Noire, M.H.; Esbelin, E.; Dancausse, J.P.; Picart, S.

2004-01-01

This paper presents through 2 posters a general overview studies realised by CEA teams on deposits observed in the La Hague plant dissolution facilities. Their main constituents are metallic debris bound together with zirconium molybdate hydrate. A comprehensive study of zirconium molybdate hydrate formation included nucleation and growth kinetics was developed. Fouling mechanisms were consequently explained as influenced by the operation conditions. Pu insertion was also overviewed. Its behaviour is important when curative and preventive chemical treatments are considered. (authors)

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)

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)

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.)

NTL 11 spent fuel flask - meeting the challenge of regulatory and technological change

International Nuclear Information System (INIS)

Cory, A.R.

2004-01-01

By June 2005, when shipments of spent fuel for reprocessing from Germany are concluded, the NTL11 flask type will have been responsible for transporting a total of 1500 tonnes of heavy metal in the form of spent fuel. Excluding domestic transports in France and the UK, this represents 25% of the total European spent fuel transported for reprocessing since the flasks came into service in 1977. Approximately 40% of the total for the flask type will have been transported to BNFL's Sellafield facility, the remainder to Cogema at La Hague. The NTL11 flask can justifiably be described as being the workhorse of BNFL's European spent fuel transport business. The NTL11 flask started life under the ownership of Nuclear Transport Limited, an associate company of BNFL, and in recent years the original fleet of five flasks has been absorbed into the BNFL inventory. A recent build programme has seen a further four flasks added to the fleet, an expedient measure to cope with the additional transport requirements imposed by the need to meet the June 2005 deadline for the removal of contracted fuels from Germany. While there have been certain evolutionary changes affecting the package design, there have also been more significant changes in the Design Safety Case. These have sometimes been necessary to meet regulatory changes, or the challenges posed by the regulators. In other cases advantage has been taken of improvements in analytical techniques to demonstrate increased margins of operational safety. Where possible those margins have also been increased by other means, such as taking advantage of commercial trends to reduce package thermal loads. The NTL11 flask was designed around the reactor and fuel characteristics prevailing in the 1970's. Over the lifetime of the flask the responsible engineering teams have faced and met the successive challenges to develop the capability of the Package to face the changing requirements of the industry and the Transport Regulations. Both

The pollution of the North Sea

International Nuclear Information System (INIS)

1981-01-01

The subject is covered in chapters entitled: the North Sea and its rivers; the uses of the North Sea (shipping; exploitation of oil and gas; fishing; recreation; land reclamation; industrial islands; waste dumping); the nature of the dumping problem (nuclear waste; organic chemicals; inorganic chemicals; oil; sewage; rubble and dredged spoils; ash); pollution legislation; Greenpeace activities in the North Sea (the nuclear campaigns (Windscale; Cap de la Hague; Atlantic waste dumping); the chemical campaigns); what is needed in the future; references; the Oslo Convention. (U.K.)

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.)

Sauvez un enfant: Le soutien humanitaire néerlandais aux réfugiés algériens pendant la guerre d'Algérie 1954-1962

NARCIS (Netherlands)

Pas, N.

2014-01-01

This article is about the humanitarian support of the Netherlands destined to Algerian refugees in Morocco and Tunisia during the Algerian war of independence (1954-1962). At the political level, in The Hague, the Franco-Algerian conflict went largely unnoticed for the reason that the Netherlands, a

PAREX, a numerical code in the service of La Hague plant operations

Energy Technology Data Exchange (ETDEWEB)

Bisson, J.; Huron, P.; Huel, C. [AREVA NC, La Hague Plant, Technical Direction, 50444, Beaumont-Hague (France); Dinh, B. [CEA, Centre de Marcoule, Nuclear Energy Division, Radiochemistry and Process Department, F-30207, Bagnols-sur-Ceze (France)

2016-07-01

The PAREX code developed by the CEA is able to simulate the PUREX process in steady or transient state. From an operator point of view, this numerical code for simulation of liquid-liquid extraction operations is an outstanding tool as an aid for plant operation through process flow sheet optimization, troubleshooting and safety analysis calculations. This paper focuses on two examples. The first concerns the evaluation of the available operating margin of the extraction zone of the first purification cycle flowsheet. The second example concerns a uranium-plutonium splitting operation where the code was used to explain a shift of plutonium concentration in the solvent outlet. (authors)

The new Rotterdam Rules: An overwiew on the main differences with the international regulations in force on carriage of goods by sea

OpenAIRE

Rimaboschi, Massimiliano

2009-01-01

This new instrument, that will enter into force once it has been ratified by at least twenty States, deals with the international carriage of goods and is closely connected with the international trade. International transport law is currently regulated by two main international Conventions, the Hague Rules and the Hamburg Rules. Many countries have adopted the Hague Rules as amended by two Protocols, respectively adopted in Brussels on 1968 (the Hague Visby Rules – 30 contracting States) and...

Annual progress report 1980

International Nuclear Information System (INIS)

1981-01-01

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

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)

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)

Glass packages in interim storage

International Nuclear Information System (INIS)

Jacquet-Francillon, N.

1994-10-01

This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO 2 . The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ''source term'' models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs

The MELOX MOX fabrication facility: history of an industrial success and future prospects

International Nuclear Information System (INIS)

Arslan, M.; Jacquet, R.; Krellmann, J.

2005-01-01

Along with the La Hague reprocessing plant, MELOX is part of the two industrial facilities that ensure the closure of the nuclear fuel cycle in France. Since started up in 1995, MELOX has specialized into recycling separated plutonium recovered from reprocessing operations performed at La Hague on spent UO 2 fuel. Capitalizing on the unique know-how acquired through thirty years of plutonium-based fuel fabrication at the Cadarache plant, this subsidiary of AREVA group has quickly become a worldwide expert in the industrial process of fabricating MOX: a fuel blend comprised of both uranium and plutonium oxides that allows at safely exploiting the energetic potential of plutonium. In order to address the various factors responsible for this industrial breakthrough, we will first present an overview of MELOX's history in regards of the emergence of a global MOX market. The added-value provided through treatment and recycling operations on spent fuel will be further described in terms of waste volume and radiotoxicity reduction. The emphasis will then be put on the total quality management policy that is at the core of MELOX's corporate strategy. Because MELOX has succeeded in meeting both productivity requirements and stringent quality constraints, it has won confidence from its European and Japanese clients. With increased production capacity of diversified MOX designs, MELOX is demonstrating the industrial efficiency of a new concept of MOX plants that is inspiring large construction projects in Japan, the US, and Russia. (authors)

Glass packages in interim storage; Les verres dans les stockages

Energy Technology Data Exchange (ETDEWEB)

Jacquet-Francillon, N

1994-10-01

This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO{sub 2}. The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ``source term`` models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs.

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.

HLW vitrification in France industrial experience and glass quality

International Nuclear Information System (INIS)

Desvaux, J.L.; Delahaye, P.

1994-01-01

This paper describes the vitrification process, the technology and process improvements at the La Hague plant in R 7 and T 7 facilities. The main achievements relate to the process flexibility, the reliability of the equipment and solid waste management. The quality of the vitrified glass produced and canisters compliance with agreed specifications are demonstrated through characterization studies. Since the active start-up of R 7/T 7 facilities, canisters compliance with specifications relies upon a complete quality assurance/quality control program including process control. 1 tab., 1 fig

Mathematical model of 125Sb transport and dispersion in the [English] Channel

International Nuclear Information System (INIS)

Salomon, J.C.; Breton, M.; Guegueniat, P.

1991-01-01

A mathematical model of the English Channel is used to describe the fate of radionuclides discharged by La Hague nuclear reprocessing plant. The modelling technique is described and the results discussed. A permanent and average wind-tide situation is used to determine mean trajectories and time scales of retention and evacuation to the North Sea. Comparison with in situ measurements are satisfactory. Two additional simulations in the case of no wind and in the case of an easterly one are then used to investigate the variability linked to atmospheric conditions. (Author)

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

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

International Nuclear Information System (INIS)

2009-10-01

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

Neptunium-237 in the marine environment determination in animal and plant species in the English Channel

International Nuclear Information System (INIS)

Germian, P.

1990-01-01

The uptake of 237 Np was studied in marine plants and animals belonging to several phyla. Samples were collected from the end of January 1986 to March 1986 in a sampling station near the fuel reprocessing plant at La Hague. 237 Np was determined by neutron activation analysis. The transfer modes of 237 Np to the various species as a function of their trophic levels are discussed as well as the distribution among the organs in the species consumed and the radiological impact of human consumption. (author) 27 refs.; 2 figs.; 1 tab

Progress report file for 1997 Synthesis

International Nuclear Information System (INIS)

Anon.

1998-01-01

In this work are studied the following subjects: the working conditions of temporary employees in E.D.F nuclear power plants, the future of fast neutrons reactors, the radiological impact of the reprocessing plant of La Hague and the management of radioactive wastes, as well as the distribution of iodine tablets around nuclear sites. Others problems have some importance such the accounting of radioactive materials.These points were the essential of activities of the D.S.I.N (Direction of the Safety of Nuclear Installations) for the year 1997. (N.C.)

Exporting nuclear wastes to Russia: how Greenpeace contributed to make a traffic stop which has been lasting for nearly 40 years

International Nuclear Information System (INIS)

2010-01-01

After having recalled how Greenpeace discovered the existence of contracts between the French CEA (and later AREVA) and Russia for the export of nuclear wastes to Russia, this document specifies which kinds of wastes are concerned: depleted uranium (from the EURODIF plant in Tricastin) and reprocessed uranium (from La Hague). It briefly reports the different actions performed by Greenpeace about this trade which occurred against the Russian law on the protection of the environment and against a European directive. It finally denounces the posture and statements of AREVA about a possible use of these wastes

Solid and liquid radioactive wastes

International Nuclear Information System (INIS)

Cluchet, J.; Desroches, J.

1977-01-01

The problems raised by the solid and liquid radioactive wastes from the CEA nuclear centres are briefly exposed. The processing methods developed at the Saclay centre are described together with the methods for the wastes from nuclear power plants and reprocessing plants. The different storage techniques used at the La Hague centre are presented. The production of radioactive wastes by laboratories, hospitals and private industry is studied for the sealed sources and the various radioactive substances used in these plants. The cost of the radioactive wastes is analysed: processing, transport, long term storage [fr

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

International Nuclear Information System (INIS)

Goasmat, F.

1984-01-01

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

The new duty of care for nuclear power plant operators in Sec. 9a subpara. 2a AtG; Zur neuen Sorgepflicht der Kraftwerksbetreiber gem. paragraph 9a Abs. 2a AtG

Energy Technology Data Exchange (ETDEWEB)

Posser, Herbert [Freshfields Bruckhaus Deringer LLP, Duesseldorf (Germany)

2014-07-15

The new stipulation in Sec. 9a subpara. 2a AtG - pursuant to which operators of nuclear power plants are no longer entitled to use the interim storage facility in Gorleben for radioactive waste stemming from the reprocessing plants in Sellafield and La Hague, but have to establish further capacities in their own facilities for spent nuclear fuels at the site of the power plants - is illegal under constitutional law. It imposes an unproportional burden on the plant operators as well as on GNS, and infringes property rights without pursuing a legitimate purpose. (orig.)

The new duty of care for nuclear power plant operators in Sec. 9a subpara. 2a AtG

International Nuclear Information System (INIS)

Posser, Herbert

2014-01-01

The new stipulation in Sec. 9a subpara. 2a AtG - pursuant to which operators of nuclear power plants are no longer entitled to use the interim storage facility in Gorleben for radioactive waste stemming from the reprocessing plants in Sellafield and La Hague, but have to establish further capacities in their own facilities for spent nuclear fuels at the site of the power plants - is illegal under constitutional law. It imposes an unproportional burden on the plant operators as well as on GNS, and infringes property rights without pursuing a legitimate purpose. (orig.)

Ionizing radiations and health. Exposures, epidemiological surveillance and sociological monitoring measurements

International Nuclear Information System (INIS)

Spira, Alfred; Boutou, Odile

1999-01-01

This paper draws attention to the epidemiological effect of natural and artificial ionizing radiation exposures on man. It describes ionizing radiation sources from nuclear facilities and medical establishments. The case here is in the region of La Hague in France where 4800 employees are exposed to ionizing radiations. The topic of leukemia research and thyroid studies for children in the region are discussed. The impact of radiations on fertility, life quality is covered. Finally, national propositions to establish a monitoring measurement system is also discussed including the personnel and the general population exposed

Technico-Economical study of retreated uranium reenrichment

International Nuclear Information System (INIS)

Patillon, L.

1985-03-01

Spent fuel from nuclear power plants is reprocessed at La Hague reprocessing plant in France. Recovered and stored reprocessed uranium has an energy potential unutilized so far. A modelisation is proposed in this paper for evaluating the economic interest reprocessed uranium reenrichment for using it again in a power plant. After briefly recalling the fuel cycle in light water reactors and reprocessed uranium specificities, a mathematical model for multi-isotope enrichment gives a differential system governing isotopic separation. Different solutions are proposed and compared. A. de la Garza analytical model's is retained. An economic value is attributed to reprocessed uranium. Results are presented as curves for determining the sensitivity of this value to simulation parameters (natural uranium cost, enrichment required by the electricity board etc.) [fr

Cargo liability regimes

Science.gov (United States)

2001-01-01

There are at present at least three international regimes of maritime cargo liability in force in different countries of the world - the original Hague rules (1924), the updated version known as the Hague-Visby rules (1968, further amended 1979), and...

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)

Analog study of the second re-extraction line of the La Hague plant

International Nuclear Information System (INIS)

Bory, M.; Francois, N.

1966-01-01

This study, realized on an analog computer, aims to determine the behavior of an uranium and plutonium re-extraction line in dynamical state. The system perturbations are temperature and acidity variations of aqueous phase and variations of the TBP of the solvent. The uranium contents variations are described. (A.L.B.)

Reprocessing of fast reactor fuels in the UP2 plant at La Hague

International Nuclear Information System (INIS)

Chenevier, F.; Grellard, J.; Wauquier, J.M.

The installations of the UP2 plant and particularly the geometry of the HAO shop equipment were defined for reprocessing fuels from the ordinary water system. The high fissile substance level of fuels from the fast neutron system necessitated certain modifications to the installations and some operating restrictions so that they could be treated in the existing installation. After reviewing the characteristics of the reference fuel and describing the particular restrictions to be respected for safety-criticality, the choices made with respect to installation modifications and operating restrictions are presented. The observations made during a first treatment campaign confirm the validity of the options chosen [fr

Seismic characterisation for geothermal energy prospecting

NARCIS (Netherlands)

Huck, A.; Groot, P. de; Simmelink, E.; Vandeweijer, V.P.; Willemsen, A.

2009-01-01

The city of The Hague intends to use geothermal energy to heat approx. 4000 houses in a planned urban development area called The Hague South-West. This paper describes the application of advanced seismic interpretation workflows to help positioning a geothermal doublet consisting of one injector -

research document no. 27 bis. After the Hague, Bonn and Marrakech: the future international market for emissions permits and the issue of hot air

International Nuclear Information System (INIS)

Blanchard, O.; Criqui, P.; Kitous, A.

2002-01-01

The main objective of this paper is to assess the Bonn-Marrakech agreement, in terms of abatement cost and emission trading as compared with the initial agreement reached in Kyoto (the Kyoto Protocol). Our reference case (the Initial Deal) does not include the use of sinks credits, as the Kyoto Protocol does not give explicit figures nor method to estimate them. In addition, two hypothetical situations are considered. The first describes the ''missed compromise'' that could have emerged among all Parties in November 2000 in The Hague. The second is a virtual case where the US is assumed to be part of the Bonn-Marrakech Agreement, along with all the other Parties. These two cases contribute to shed the light on the Bonn-Marrakech Agreement potential pitfalls. In the current situation, the US is out of the negotiation process and has no emission reduction commitment. Given the projections of carbon dioxide (CO 2 ) emissions used in this study, the Former Soviet Union countries (FSU) and the Eastern European Economies (EEE) that are part of the Annex B have potentially enough Hot Air to fulfill the overall commitment of the Annex B bubble, without any domestic abatement effort from the other Annex B countries. We show that in the theoretical case where no limit would be imposed on the selling of Hot Air, the permit price according to the POLES model would be zero as no market equilibrium could take place. This is why, next, we examine the economic impacts of restrictions to hot air trading, for FSU and EEE as well as for the other countries. We shed the light on the potential market power of the former countries that arises from the Bonn-Marrakech Agreement. (author)

Nuclear transport

International Nuclear Information System (INIS)

Anon.

2003-01-01

During january and february 2003, a unique event concerning nuclear transport was reported and rated 1 on the INES scale. This event concerns the absence of a maintenance operation on a shipping cask. This shipping cask was used for several years for nuclear transport inside La-hague site before being re-assigned to transport on public thoroughfare. The re-assignment of the cask should have been preceded and conditioned by a maintenance operation whose purpose is to check the efficiency of its radiation shield. During this period 2 on-site inspections concerning the transport of nuclear materials were performed. (A.C.)

Nondestructive determination of burnup and fissile isotope balance in spent fuel assemblies of water cooled reactors

International Nuclear Information System (INIS)

Pinel, J.

1983-03-01

Two non-destructive methods for measuring fuel assemblies in storage pools have been developed: a gamma fuel scanning method, using the 134 Cs - 137 Cs and 144 Ce gamma rays, and the measurement of the neutron flux emitted by the fuel assembly. For interpreting the measurement, we have used calculated correlations to establish a connection between the measured phenomena and the parameters to be determined. A measurement campaign involving 58 assemblies from the C.N.A. reactor was conducted in the reprocessing plant of LA HAGUE. The results obtained show that the objectives can be achevied within an industrial environment [fr

Radio-phobias, leukaemias and disinformation; Radiophobies, leucemies... et desinformation

Energy Technology Data Exchange (ETDEWEB)

Brissonnet, J.

2002-07-01

The author answers to a letter sent by a reader after a previous article inspired by the attitude of media after the discovery of a high radioactive level on a beach in Camargue. Here, the author discusses some information about the risks associated with radioactive irradiation, notably in terms of genetic impact (risk of trisomy). He discusses the results of an epidemiological survey concerning La Hague, and outlines how these data have been somehow misinterpreted. Finally, while noticing that some famous scientists committed themselves in strange and highly questionable studies, he comments the issue of the quality of information sources

Radio-phobias, leukaemias and disinformation

International Nuclear Information System (INIS)

Brissonnet, J.

2002-01-01

The author answers to a letter sent by a reader after a previous article inspired by the attitude of media after the discovery of a high radioactive level on a beach in Camargue. Here, the author discusses some information about the risks associated with radioactive irradiation, notably in terms of genetic impact (risk of trisomy). He discusses the results of an epidemiological survey concerning La Hague, and outlines how these data have been somehow misinterpreted. Finally, while noticing that some famous scientists committed themselves in strange and highly questionable studies, he comments the issue of the quality of information sources

Is it possible to recycle nuclear wastes? Costs, risks and stakes of the plutonium industry

International Nuclear Information System (INIS)

2009-01-01

This document, published by the French association 'Sortir du nucleaire' (Get out of nuclear), gives some information on the chain reaction from uranium to plutonium, the difference between reprocessing (which does not reduce waste volumes but multiply waste types) and recycling, the high risks associated with plutonium transport, La Hague as the most dangerous nuclear site in France, reprocessing as the alibi for the French nuclear industry, Areva as an expert in propaganda, reprocessing as an absurd world strategy, plutonium as a fuel for proliferation, the myth of unlimited energy with the breeder reactors, and so on

The transport of irradiated fuel. An activity closely related to reprocessing

International Nuclear Information System (INIS)

Lenail, B.; Curtis, H.W.

1987-01-01

With a proven reprocessing capacity of 400 tonnes of uranium per year and the rapid expansion of this capacity, the need to feed the reprocessing plants at La Hague has become vital to ensure continuous and economic reprocessing. The programming of transports by the reprocessor and transporter to ensure a constant supply of fuel for reprocessing has therefore become increasingly important. These transports use the public roads and the railway system and the reprocessor and transporter must cooperate in maintaining the highest possible standards of safety. Safety must take priority over all other factors, including the economics of the operation

Is it possible to recycle nuclear wastes? Costs, risks and stakes of the plutonium industry; Peut-on recycler les dechets nucleaires? Couts, risques et enjeux de l'industrie du plutonium

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

This document, published by the French association 'Sortir du nucleaire' (Get out of nuclear), gives some information on the chain reaction from uranium to plutonium, the difference between reprocessing (which does not reduce waste volumes but multiply waste types) and recycling, the high risks associated with plutonium transport, La Hague as the most dangerous nuclear site in France, reprocessing as the alibi for the French nuclear industry, Areva as an expert in propaganda, reprocessing as an absurd world strategy, plutonium as a fuel for proliferation, the myth of unlimited energy with the breeder reactors, and so on

Industrial experience of irradiated nuclear fuel reprocessing

International Nuclear Information System (INIS)

Delange, M.

1981-01-01

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

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

77 FR 74490 - Implementation of Immigrant Visa DHS Domestic Processing Fee

Science.gov (United States)

2012-12-14

... the United States under the Orphan or Hague Process will be exempt from the USCIS Immigrant Fee. The... seeking admission to the United States under the Orphan or Hague Process. In addition, the Director has... USCIS Immigrant Fee collection process is now in place and that USCIS will begin collecting the fee in...

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

A reasoned use of the notion of concernment: mobilizations about the nuclear industry; De l'usage raisonne de la notion de concernement: mobilisations locales a propos de l'industrie nucleaire

Energy Technology Data Exchange (ETDEWEB)

Brunet, Ph. [Universite d' Evry Val d' Essonne, Centre Pierre Naville, TEPP/FR-CNRS 3126, 87 - Panazol (France)

2008-10-15

Discussing the mobilization of environmental associations from the sole sociological viewpoint of interest and calculations is no longer workable. Similarly, although the processual analysis of commitment has obvious heuristic virtues, it could be usefully completed to understand how it emerges and gets structured. This is why, in order to further develop this kind of analysis, we shall explore the processes leading to forms of organized commitment. To do so, Canguilhem's research about the epistemology of living organisms will be used. It shows that, when the resolution of problems between individuals and their milieu is attempted, it is always initiated by the former. By using the notion of 'concernment' and articulating it with those of environment and orientated behaviour, we intend to emphasize the singularity of the social dynamics that aim to solve the tensions inherent in environmental issues. Furthermore, through sociological analysis, one may get a glimpse of forms of similarity between 'concernment', commitment and cognitive mobilization. Our research is based on comparative data drawn from two surveys on the nuclear industry in France: one in Limousin concerning the uranium industry and another in La Hague, North Cotentin, dealing with radioactive waste. (author)

Guidance-Control-Navigation Automation for Night All-Weather Tactical Operations Held at Hague (Netherlands) on 21-24 May 1985.

Science.gov (United States)

1985-11-01

PROESEURTRITMEN VDE DE DIE GESTION ET BALAYAGE D’ASSERVISSEMENT SYNCHROS LIAISON SX VIDEO VIDEO VERS BGS OBSERVATEUR I i 1.2 1 ra,im rrnali prrPCO ci EC.A...est cormmune A toutes les missions ndvales 00 terrestres , mais son importance varie selon la mission. IElle constitue par exemple 1’essentiel do vol...tactique se retrouvent dans les missions de type AMromobilitk terrestre " telles quy la reconnaissance. 1 identification dv cible. les missions Air

Advanced high throughput MOX fuel fabrication technology and sustainable development

International Nuclear Information System (INIS)

Krellmann, Juergen

2005-01-01

The MELOX plant in the south of France together with the La Hague reprocessing plant, are part of the two industrial facilities in charge of closing the nuclear fuel cycle in France. Started up in 1995, MELOX has since accumulated a solid know-how in recycling plutonium recovered from spent uranium fuel into MOX: a fuel blend comprised of both uranium and plutonium oxides. Converting recovered Pu into a proliferation-resistant material that can readily be used to power a civil nuclear reactor, MOX fabrication offers a sustainable solution to safely take advantage of the plutonium's high energy content. Being the first large-capacity industrial facility dedicated to MOX fuel fabrication, MELOX distinguishes itself from the first generation MOX plants with high capacity (around 200 tHM versus around 40 tHM) and several unique operational features designed to improve productivity, reliability and flexibility while maintaining high safety standards. Providing an exemplary reference for high throughput MOX fabrication with 1,000 tHM produced since start-up, the unique process and technologies implemented at MELOX are currently inspiring other MOX plant construction projects (in Japan with the J-MOX plant, in the US and in Russia as part of the weapon-grade plutonium inventory reduction). Spurred by the growing international demand, MELOX has embarked upon an ambitious production development and diversification plan. Starting from an annual level of 100 tons of heavy metal (tHM), MELOX demonstrated production capacity is continuously increasing: MELOX is now aiming for a minimum of 140 tHM by the end of 2005, with the ultimate ambition of reaching the full capacity of the plant (around 200 tHM) in the near future. With regards to its activity, MELOX also remains deeply committed to sustainable development in a consolidated involvement within AREVA group. The French minister of Industry, on August 26th 2005, acknowledged the benefits of MOX fuel production at MELOX: 'In

The Carriage of goods by Sea Act 1971 (Commencement, Order 1977)

International Nuclear Information System (INIS)

1977-01-01

This Order (S.I. No 981) brought into force the Carriage of Goods by Sea Act 1971 giving effect at internal level to the 1968 Protocol to the International Convention on Certain Rules of Law relating to Bills of Lading 1924 (the Hague Rules). The 1971 Act introduces an amendment to the Nuclear Installations Act 1965 which lays down, as does the Paris Convention, that none of its provisions shall affect the operation of international transport agreements in force in the United Kingdom, and in particular, the Hague Rules. As of now, and in accordance with the 1968 Protocol, the Nuclear Installations Act 1965 no longer reserves application of the Hague Rules. (NEA) [fr

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

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

Energy. Saving 'Private' Areva

International Nuclear Information System (INIS)

Dupin, Ludovic

2015-01-01

While Areva keeps on loosing money (billions of euros for 2014), the saving of this company is at stake. Staff is already planned to be reduced in La Hague, and other staff reductions might occur after the failure of a previous strategic plan. Various activities could be sold (dismantling, mining). The article outlines the difficult relationships between Areva and EDF and the problems also faced by EDF. Some actors think that Areva should remain independent from EDF in order to be free to compete on international bidding. The rapprochement between these two companies is said to be necessary for the Ministry but seems very difficult to achieve

Status of radioactive material transport

International Nuclear Information System (INIS)

Kueny, Laurent

2012-01-01

As about 900.000 parcels containing radioactive materials are transported every year in France, the author recalls the main risks and safety principles associated with such transport. He indicates the different types of parcels defined by the regulation: excepted parcels, industrial non fissile parcels (type A), type B and fissile parcels, and highly radioactive type C parcels. He briefly presents the Q-system which is used to classify the parcels. He describes the role of the ASN in the control of transport safety, and indicates the different contracts existing between France or Areva and different countries (Germany, Japan, Netherlands, etc.) for the processing of used fuels in La Hague

Experimental and in situ investigations on americium, curium and plutonium behaviour in marine benthic species: transfer from water or sediments

International Nuclear Information System (INIS)

Miramand, P.

1984-06-01

The tranfer of transuranic elements -americium, curium and plutonium- from the sediments containing them to some marine benthic species (endofauna and epifauna) was studied with a twofold approach - laboratory and in-situ investigation. The experimental investigations, divided into three parts, made it possible to specify concentration factors (F.C.), transfer factors (F.T.) and to understand the process involved for 5 benthic species. The result were refined by an in-situ study that brought new data on the marine distribution of the transuranic elements released by the La Hague plant. Finally, the localization of americium and plutonium in the tissues and cells of these species was determined by autoradiography [fr

New Resin for the Selective Extraction of {sup 129}I

Energy Technology Data Exchange (ETDEWEB)

Bombard, A.; Happel, S. [TrisKem International, Bruz (France); Zulauf, A. [NUKEM Technologies GmbH, Alzenau (Germany); Streng, R. [Radiochemistry, Department of Chemistry, Philipps-University Marburg, Marburg (Germany)

2013-07-15

{sup 129}I is an ideal tracer of the marine environment. It has been used for some years particularly in the northeast Atlantic, Nordic seas and Arctic to determine its distribution after its discharges from La Hague and Sellafield reprocessing plants. Various methods for {sup 129}I determination exist. A new resin selective for iodine has been developed, characterized and tested on environmental samples. In order to allow {sup 129}I determination and to obtain accurate and precise results, the samples have to pass a number of sample preparation steps; among these steps are chemical separation and purification. The results of the analysis of seawater samples are presented. (author)

Radioactivity of French coast of the Channel due to the release of technectium 99 and iodine 129: modelisation and measurements

International Nuclear Information System (INIS)

Robeau, D.; Patti, F.; Charmasson, S.

1988-01-01

Radioactive releases of Iodine 129 are controlled by measurements of the radioactivity in the liquid effluents before it is released in to the sea from the outlet of the reprocessing plant of La Hague. The effects on the marine environment are examined by a radioactive survey of Technecium 99 and Iodine 129 in Fucus (common seaweed). This radioactivity is measured along the north coast of France from Roscoff in the west of Brittany to Wimereux close to the Belgian frontier. The theoretical study of dispersion of radionuclides in the Channel has permitted a simulation model of the transfer of pollutants and particularly Technecium 99 and Iodine 129 to be formulated. (author)

France: Thrust and parry over nuclear risks

International Nuclear Information System (INIS)

Balter, M.

1997-01-01

Claims about the health risks posed by nuclear-power installations are always controversial, but nowhere more so than in France, where some 75% of the nation's electricity is generated from nuclear energy. So, it was no surprise that publication of a study by two French epidemiologists earlier this month claiming to show a link between cases of childhood leukemia and the nuclear-waste reprocessing plant at La Hague on the Normandy coast sparked fireworks in the French press. Several French epidemiologists sharply criticized the study's methodology and conclusions. Their attacks have now drawn an unusual response from the British Medical Journal (BMJ), in which the paper appeared

Panorama of mining activities in France during 1995

International Nuclear Information System (INIS)

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

1996-01-01

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

LA BIOÉTICA, LA MUERTE Y LA FICCIÓN

Directory of Open Access Journals (Sweden)

Omar Parra Rozo

2015-01-01

Full Text Available La narrativa cumple un papel determinante en la relación paciente-médico-enfermedad. Ponerse en el lugar del médico, del enfermo, de la enfermedad y del contexto mismo constituye una fuente rica y plena de entendimiento y comprensión del desequilibrio, de la carencia de la salud y de las posibilidades de explicación del dolor y de la experiencia de la enfermedad y de la muerte. Las metáforas dadas por la literatura, u otras formas narrativas, brindan la posibilidad de visualizar el papel de la bioética, los agentes e intervinientes en el proceso de alteración de la salud y el proceso en sí mismo. La narrativa y las ficciones estéticas como mediaciones en la curación y el cuidado suponen unos elementos básicos sobre los cuales se establece la comunicación, el diálogo y el contexto entre los curadores, los cuidadores, el paciente, la enfermedad y la muerte. La metáfora de ponerse en el lugar de otro, aun en la personificación de la enfermedad, la memoria o la muerte facultan la eliminación de obstáculos, brindan la posibilidad de un análisis objetivo y hacen pensar en la necesidad de fomentar una competencia narrativa en los agentes intervinientes en el proceso.

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

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

Operating in the Human Domain Lessons of a Decade of War for the Dutch Army

Science.gov (United States)

2014-06-13

Plasschaert, Minister of Defense, In Het Belang Van Nederland [in the Interest of the Netherlands] (The Hague, The Netherlands: Ministry of Defense... Nederland [in the Interest of the Netherlands]. The Hague, The Netherlands: Ministry of Defense, 2013. Klem, M. H. Het Nederlandse Veiligheidsbeleid...in Een Veranderende Wereld, Verkennende Studie Voor Het WRR-Rapport Nederland in De Wereld. [the Dutch Security Policy in a Changing World, Scoping

LA BIOÉTICA, LA MUERTE Y LA FICCIÓN

OpenAIRE

Omar Parra Rozo

2015-01-01

La narrativa cumple un papel determinante en la relación paciente-médico-enfermedad. Ponerse en el lugar del médico, del enfermo, de la enfermedad y del contexto mismo constituye una fuente rica y plena de entendimiento y comprensión del desequilibrio, de la carencia de la salud y de las posibilidades de explicación del dolor y de la experiencia de la enfermedad y de la muerte. Las metáforas dadas por la literatura, u otras formas narrativas, brindan la posibilidad de visualizar el papel de l...

Databases in the documentation management for big industrial projects; Les bases de donnees dans la gestion documentaire des grands projets industriels

Energy Technology Data Exchange (ETDEWEB)

Cauchet, A; Chevillard, F; Parisot, Y; Tirefort, C [Societe EURODOC, Saint Quentin en Yvenlines (France)

1990-05-01

The documentation management of a big industrial project involves a continuous update of information, both in the study and realization phase or in the operation phase. The organization of the technical documentation for big industrial projects requests complex information systems. In the first part of this paper are presented the methods appropriate for the analysis of documentation management procedures and in the second part are presented the tools by the combination of which a documentation system for the user is provided. The case of the documentation centres for the Hague reprocessing plant is described.

LA ERRADICACIÓN DE LA POLIOMIELITIS EN LA REGIÓN EUROPEA DE LA ORGANIZACIÓN MUNDIAL DE LA SALUD

Directory of Open Access Journals (Sweden)

Aurora Limia Sánchez

2013-01-01

Full Text Available Desde finales del siglo XIX la poliomielitis comenzó a comportarse como una enfermedad epidemica con gran importancia para la salud pública. Con la disponibilidad de vacunas efectivas para prevenir la enfermedad desde mediados del siglo XX, los países de la Región Europea de la Organización Mundial de la Salud (OMS comenzaron a implementar programas de vacunación con un importante impacto en la incidencia de la enfermedad. La Asamblea Mundial de la Salud adoptó, en mayo de 1988, la resolución para la erradicación mundial de poliovirus y estableció los mecanismos para supervisar los progresos en las diferentes Regiones. Este artículo repasa brevemente la historia de la poliomielitis en la Región Europea, el proceso de certificación y mantenimiento, las estrategias para la erradicación y la situación actual en la Región Europea y en el mundo. La Región Europea de la OMS está libre de poliomielitis desde su certificación en el año 2002. Sin embargo, en el mundo existen todavía tres países endémicos y varios países que utilizan vacunas atenuadas, el riesgo de reintroducción y la aparición de brotes de poliomielitis existe, por lo que es necesario asegurar altas coberturas de vacunación y unos sistemas de vigilancia de calidad.

La industria de la moda a la luz de la propiedad intelectual

Directory of Open Access Journals (Sweden)

Brenda Salas Pasuy

2013-11-01

Full Text Available Cuando se habla de moda se piensa en algo cambiante y efímero. Sin embargo, tras la producción de una prenda de vestir son muchos los factores que conducen a un resultado final atractivo para el consumidor. La moda supone no solamente la venta de una prenda de vestir, involucra la imagen y el prestigio de aquel que la crea. El proceso de creación y producción de la misma conduce a valorar su importancia en el marco del comercio internacional. En efecto, se trata de un bien protegido por las reglas propias de la propiedad intelectual. El artículo analiza la importancia de la moda en el marco de esta disciplina, es decir, su régimen de protección, que se caracteriza por no ser uniforme a nivel internacional y respecto del cual solo pocas legislaciones han entrado a regular directamente esta rama de la industria.

UXO Detector for Underwater Surveys Using Low-Frequency Sonar

Science.gov (United States)

2015-06-01

Oude Waalsdorperweg 63 The Hague The Netherlands 9. SPONSORING / MONITORING AGENCY NAME(S) AND ADDRESS(ES...remaining number of false alarms will be further reduced. The application of these two rules to the data shown in Figure 6-3, leads to removal of...Box 96864, 2509 JG The Hague , The Netherlands, +31 88 866 0902, alan.hunter@tno.nl Abstract: Detection of unexploded ordnance is challenging in the

50 CFR 648.200 - Specifications.

Science.gov (United States)

2010-10-01

..., unless an OY that exceeds MSY in a specific year is consistent with a control rule that ensures the... northerly along the Hague Line to the U.S.-Canadian border, to include state and Federal waters adjacent to...., northeasterly to the Hague Line at 42°53′14″ N. lat., 67°44′35″ W. long. [72 FR 11277, Mar. 12, 2007, as amended...

Study of molybdenum (VI) complexation and precipitation by zirconium (IV) in strongly acid medium. Application to nuclear spent fuel dissolution; Etude de la complexation et de la precipitation du molybdene (VI) par le zirconium (IV) en milieu tres acide. Application a la dissolution du combustible nucleaire irradie

Energy Technology Data Exchange (ETDEWEB)

Esbelin, E

1999-07-01

These last years the formation of solid deposits has been observed in the dissolution workshops of the La Hague plant. A sample of the solid was withdrawn for expertise: molybdenum and zirconium are the two major components of the solid, identified as zirconium molybdate. This thesis consisted in the approach of the mechanisms in solution liable to induce precipitate formation. After a bibliographical overview on the chemistry of Mo(VI) in highly acidic solution, this system was studied by absorption spectrophotometry in perchloric medium. The implication of two major forms of Mo(VI) in a dimerization equilibrium was confirmed by this way and by {sup 95}Mo NMR. The principal parameters governing this equilibrium were identified. It is thus shown that the molybdenum dimerization reaction is exothermic. Disturbance of the Mo(VI) system in highly acidic solution by Zr(IV) was also studied. In a restricted experimental field, for which 'conventional' exploitation methodologies had to be adapted to the system, a main complex of stoichiometry 1:1 between Mo(VI) and Zr(IV) was found. The precipitation study of Mo(VI) by Zr(IV) under conditions close to those of the dissolution medium of nuclear spent fuel was undertaken. The main parameters which control precipitation kinetics were identified. The results obtained reveal that precipitation is controlled by a single macroscopic process and therefore can be described by a single equation. The solid obtained is composed of only one phase presenting a Mo:Zr non-stoichiometry when compared to the theoretical formula ZrMo{sub 2}O{sub 7}(OH){sub 2},2H{sub 2}O. At last, on the basis of the research results, a descriptive mechanism of the system is proposed in which intervenes a 1:1 intermediate complex, much more soluble than a probable 2:1 precipitation precursor. (author)

La plaza de la salud

OpenAIRE

Pracilio, Horacio Oscar; Zelayeta, Adrián Rogelio; Diaczuk, Teresa; Mendes, Claudia Andrea; Mamonde, Mario Valentín

2016-01-01

La estrategia de promoción de la salud, propiciada por la Organización Mundial de la Salud en la Carta de Otawa (1986), propone entre las líneas de acción para intervenir sobre los determinantes de la salud, la “creación de entornos favorables a la salud” y el “desarrollo de aptitudes personales”. Según numerosas investigaciones epidemiológicas sobre factores causales y de riesgo de enfermedades transmisibles y crónicas no transmisibles, la salud de la población depende no solo de intervencio...

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

La violencia escolar desde la infancia hasta la juventud

Directory of Open Access Journals (Sweden)

Laura Oliva-Zárate

2013-12-01

Full Text Available La violencia escolar se ha convertido en foco de atención no sólo de investigadores, sino de todos aquellos involucrados en el quehacer educativo y de la sociedad en general. Lo anterior debido a la creciente ola de violencia que se presenta en los distintos ámbitos de la actividad humana. El punto de interés del presente estudio tiene como objetivo la descripción de la violencia narrada por los mismos alumnos de los distintos niveles educativos. Para ello, se utilizó la técnica de grupo de discusión para rescatar los discursos individuales y colectivos de 37 estudiantes (16 mujeres y 21 varones entre 3 y 22 años provenientes de 27 escuelas de diversos niveles educativos de la ciudad de Xalapa, México. El análisis cualitativo de los datos se realizó mediante el programa ATLAS.ti. Los resultados indicaron la existencia de violencia en todos los niveles escolares estudiados. Sin embargo, las formas, tipos, lugares y la dirección de la violencia, así como el género en la expresión de la violencia cambió desde niños preescolares hasta jóvenes universitarios. Los resultados señalaron que con respecto a la dirección de la violencia, el maltrato entre iguales se presentó con mayor frecuencia al igual que la violencia de tipo psicológico. Respecto a las formas predominaron los golpes y las agresiones verbales con manifestación principalmente en el baño y los espacios abiertos de la escuela. Los datos encontrados en cada nivel escolar permiten concluir que el comportamiento violento se encuentra relacionado con la edad y que junto con la influencia cultural determinan su expresión.

``Distribution and behaviour of plutonium in the waters of the channel and of the seine estuary``; ``Distribution et comportement du plutonium dans les eaux de la manche et de l`estuaire de la seine``

Energy Technology Data Exchange (ETDEWEB)

Garcia, K

1998-12-31

Excess dissolved plutonium has been measured in the coastal waters of the Channel, from Granville to Boulogne, probably due to sorption-desorption processus. In the Seine estuary, in situ measurements and experimental studies showed that the plutonium desorbs himself from particles in low salinity waters. The desorbed plutonium originates in marine and/or fluvial dissolved Pu. Marine dissolved Pu(V), originating from La Hague plant discharges and from atlantic waters, is reduced and sorbed when the salinity decreases onto estuarial particles: Isotopic Activity Ration {sup 238}Pu/{sup 239}, Pu(IR) of marine dissolved Pu(V) is about 0.7. Fluvial dissolved plutonium originates from atmospheric fallout and from an internal river source: fallout plutonium (IR=0.05) is unreactive with salinity while 45% of river plutonium (IR>1.7) flocculates at 0.5 g l{sup -1}. Desorbed plutonium may have various origins, depending on the Seine liquid discharges and on the tidal coefficient. When the marine waters do not migrate upstream, the low salinity waters encounters particles marked essentially with marine plutonium and the IR of desorbed Pu is about 0.7. The activities of desorbed plutonium are too low to have any influence on the distribution of plutonium in the coastal waters on the Seine Bay. When the marine waters migrate upstream, the low salinity waters meet particles marked essentially with river plutonium (IR>1.7) and desorbed plutonium has a very high IR. These estuarine conditions are encountered five to seven month a year and implicate an increase of the IR of 0.1 of the plutonium present in the coastal waters of the Seine bay (1.2.-1.3.). (author).

Prescription by the 2013-2015 PNGMDR defined at the article 7.1 of the decree Nr 2013-1304: historical storages of radioactive wastes

International Nuclear Information System (INIS)

2014-01-01

Within the frame of the French national plan for the management of radioactive wastes (PNGMDR), this report aims at confirming that, within basic nuclear installations, secrete basic nuclear installations, or in areas which have been historically used as outbuildings or satellite of these installations, there isn't any historical waste storage site which would not have been mentioned in statements made to the Andra for the inventory of radioactive materials and wastes. Thus, the report contains a synthesis of information on various sites: Areva NC La Hague, Somanu, Areva NC Malvesi, Areva NC Melox, Areva NC Pierrelatte, SET (Plant Georges Besse II), Eurodif Production, Socatri, FBFC Romans, SIGN Veurey, and SIGN Annecy

Observations on the in situ contamination of some marine species

International Nuclear Information System (INIS)

Guegueniat, Pierre; Lucas, Yves

1969-09-01

Measurements carried out in 1966-1968 in the Bay of Ecalgrain in the La Hague region which is subjected to radioactive waste disposal, have made it possible to begin an in-situ study of fission product transfer, in particular of ruthenium 106, in marine waters. A certain number of concentration factors have been determined and compared to those obtained experimentally. From the monitoring point of view, attention is drawn to the following species which, because of their high accumulation power, give a more sensitive indication of the contamination of the site (indicator species), in particular for ruthenium: Sea-weed: Corallina officinalis; Spongiae: Pachymatisma johnstoni (amongst other species of spongiae); Ascidium: Dendrodoa grossularia. (author) [fr

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

La asistencia al final de la vida: la ortotanasia

OpenAIRE

Gamarra, Maria del Pilar

2011-01-01

La muerte es un hecho natural e inevitable, que pone fin a la vida. En un sistema sanitario construido sobre el modelo de la terapia curativa, los profesionales de la salud han sido formados y han desarrollado su actividad como si el proceso de la muerte no existiera.Muchos profesionales no tienen incorporada la actuación en el abordaje del paciente en el final de su vida, cómo comunicar la verdad de la situación irreversible, los tratamientos paliativos y el apoyo emocional al paciente y a s...

LA IDENTIDAD ENSAMBLADA: LA ORDENACIÓN DE LA FELICIDAD

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Helena Bejar

2015-01-01

Full Text Available Inscrito dentro de la sociología de la cultura, el presente trabajo constituye un análisis crítico de la psicología positiva, que se toma como ejemplo paradigmático del actual imperativo cultural de la felicidad. El contexto teórico es el de la individualización contemporánea y la cultura psicoterapéutica, que preconizan una concepción del yo reflexiva y autoconstituida, al margen de una comprensión moral y social de la identidad personal. He estudiado las técnicas para lograr la “positividad”, constituyendo su análisis crítico el grueso de este trabajo. Asimismo he analizado los valores, los lenguajes morales de la psicología positiva y las tensiones de los diversos repertorios de significado. He tratado los textos que se encuentran a medio camino entre la psicología científica y la popular, que sirven como ejemplos de la literatura de consejos, que contiene normas explícitas de conducta y alude a las buenas y malas emociones, con la intención de definir un modelo de identidad personal concreto.

De Haagse School en het nationale landschap

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W. Krul

2006-01-01

Full Text Available Wessel Krul, The Hague School and the national landscapeFrom the 1870s onward, the so-called ‘Hague School’ was credited with the invention of a type of landscape painting which was felt to be truly national, in the sense that it realistically depicted the atmospheric qualities of the Dutch countryside. This connection between painting and national identity retained its influence until far into the twentieth century. The main characteristics of the new landscape painting were said to be ‘simplicity and veracity’. These ideals, however, had already been propagated in Dutch art criticism for a very long time. Wessel Krul examines the relationship between the changing concept of national identity in the Netherlands and the evolution of landscape painting from the Biedermeier style of B.C. Koekkoek and his followers to the new ‘realism’ of the Hague School. The identification of the new landscape painting with modern national sentiments was closely connected with the rise of the progressive liberal movement in the 1870s. Although the idea seemed convincing to several generations, the conception of the Hague School as the ‘true expression’ of the Dutch nation was as much a myth as the attempts at nationalism in painting that preceded it.

La maternidad en la empresa

OpenAIRE

Sánchez González, Mª Inmaculada

2012-01-01

Con este estudio se pretende visualizar la gran disfunción existente en nuestra sociedad actual entre la realización personal y profesional de la mujer. Uno de los motivos de esta disparidad consideramos que lo constituye la maternidad, en cuanto que siempre ha estado encuadrada en la esfera privada de la mujer, chocando por tanto con la esfera pública que supone una actividad laboral. Por tanto, pretendemos llevar a cabo un breve esbozo de la repercusión que la maternidad tien...

Tensión Entre la Calidad y la Equidad, la Calidad y la Eficiencia.

OpenAIRE

Gustavo Malagón Londoño

2004-01-01

Si calidad significa el conjunto de características o circunstancias que un usuario requiere para satisfacer sus necesidades, o el máximo de esfuerzos para satisfacer las necesidades del usuario o los mejores servicios con la mas esmerada tecnología para la óptima satisfacción del usuario, se está mencionando que la meta de la calidad es la satisfacción del usuario; en el caso de la salud, del paciente o cliente externo, como quiera llamársele. A la vez eficiencia representa la mejor alternat...

LA NECROSIS AVASCULAR EN LA DISPLASIA DE LA CADERA

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Valentín Malagón

1978-10-01

Full Text Available

Presentado en el III Congreso Nacional de la Sociedad Colombiana de Cirugía Infantil y XXIII Curso de Ortopedia para Post Graduados. Bogotá. Marzo 1978.

1. La Necrosis Avascular de la extremidad proximal del fémur es una de las complicaciones más frecuentes y temibles en el tratamiento de la displasia de la cadera.

2. Un mejor conocimiento de su etiopatogenia, de su historia natural, de su patología y
de su cuadro radiológico, aporta bases para prevenirla y tratarla en forma adecuada.

3. Por ser una lesión esencialmente iatrogénica relacionada con la aplicación de conductas
inapropiadas de tratamiento, la depuración de esas técnicas puede evitar su aparición.

4. Un diagnóstico precoz de la displasia de la cadera, un programa adecuado de tracción
previa a la reducción, con tenotomía de los músculos aductores, en el momento de la
reducción, maniobras suaves de reducción e inmovilización en una posición fisiológica
humana (flexión de 900, abducción de 450 reducen notablemente la frecuencia de la
necrosis avascular como complicación en el tratamiento de la displasia de la cadera.

5. La reducción abierta de la cadera, asociada a la osteotomía del hueso innominado, precedida de una tracción adecuada y en niños mayores de 18 meses, reduce igualmente en este tipo de pacientes el porcentaje de esta complicación.

El seguimiento de los principios enumerados en el Departamento de Ortopedia del Hospital
Infantil, ha conseguido en el curso de 20 años disminuir la incidencia de necrosis avascular
del 35 al 5.20/0.

La igualdad de oportunidades en la escuela de la diversidad

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Joan J. Muntaner

2000-01-01

Full Text Available La sociedad actual ha vivido en estos últimos años una acumulación de cambios en los valores, actitudes y prácticas, que se reflejan en los planteamientos de la educación y en la realidad de la escuela. Uno de estos cambios se refiere al reconocimiento de la diversidad del alumnado, que obliga a la búsqueda de alternativas didácticas en la educación y en la práctica de la escuela: desde el reconocimiento explícito del derecho de todos a la educación y de que ésta se desarrolle atendiendo a la igualdad de oportunidades; donde la diversidad sea un valor enriquecedor y positivo para todos. Estas alternativas se fundamentan en el paso de un modelo de intervención compensatoria a introducir prácticas coherentes con la inclusión educativa, que se fundamenta en la implantación de un currículum comprensivo común y a la determinación de apoyos normalizados para alcanzar una real integración de todos los alumnos.

Influence de la concentration de la solution nutritive sur la croissance et la nutrition minérale de la tomate

OpenAIRE

Morard, Philippe; Caumes, Edith; Silvestre, Jérôme

2004-01-01

L’influence de deux concentrations de solution nutritive a été étudiée sur la croissance et la nutrition minérale de la tomate en culture hydroponique sous serre au stade début floraison. La force ionique de la solution nutritive la plus concentrée était de 20.00 meq L–1 (SNC), valeur proche de celle qui est habituellement utilisée pour la culture de la tomate ; celle de la solution diluée (SND) était de 3.25 meq L–1. Pendant les deux semaines de l’expérimentation, la concentration du milieu ...

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)

LA EDUCACIÓN, ENTRE LA CIENCIA Y LA TÉCNICA

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José Alberto Rivera Piragauta

2012-01-01

Full Text Available Este artículo plantea una reflexión filosófica sobre la educación. Pretende ser un acercamiento, a modo de disertación, redescubriendo el papel que tiene la educación cuando se mueve en coordenadas tan claramente definidas como lo es la ciencia y la técnica, sin desconocer que la mirada está puesta en el horizonte de la educación desde la virtualidad. La metodología consistió en la revisión y el posterior análisis de algunos textos que se referencian a lo largo del escrito, y que son posibles caminos que orientan al lector en temas interesantes y a su vez actuales sobre la educación. Así las cosas, la hipótesis a desarrollar es: El objeto técnico es el punto de encuentro de la ciencia y la técnica que justifica la nueva metodología de la educación en los ambientes virtuales de aprendizaje. Es una reflexión que se fundamenta en la riqueza propia de la historia del pensamiento humano y de sus aportes a la ciencia y, por ende, al conocimiento, si y solo si tiene su necesaria réplica en la educación. Dicha reflexión tiene una carga bastante fuerte en literatura filosófica, que sirve de base para elaborar un posterior discurso sobre la educación en medio del mundo tecnológico, ya familiar para todo el género humano. Basta, por ahora invitar al lector a descubrir las aristas y los puntos de interés para propiciar nuevas indagaciones sobre el tema.

La violencia escolar desde la infancia hasta la juventud

OpenAIRE

Laura Oliva-Zárate

2013-01-01

La violencia escolar se ha convertido en foco de atención no sólo de investigadores, sino de todos aquellos involucrados en el quehacer educativo y de la sociedad en general. Lo anterior debido a la creciente ola de violencia que se presenta en los distintos ámbitos de la actividad humana. El punto de interés del presente estudio tiene como objetivo la descripción de la violencia narrada por los mismos alumnos de los distintos niveles educativos. Para ello, se utilizó la técnica de grupo de ...

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

De la timocracia a la democracia

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MANUEL SALES Y FERRÉ

1996-01-01

Full Text Available Pasaje del Tratado de Sociología. Se explica la transición de la sociedad desde la timocracia a la democracia. La timocracia es descrita como una sociedad en la cual el status se basa en la riqueza. En Europa y América, esto fue desestabilizado por el extraordinario ascenso de la riqueza, la rápida progresión de las ciencias y el avance de la cultura. Sin embargo aún no ha sido completamente reemplazada por la democracia, existe aún desigualdad y galopante individualismo (capitalismo y ha producido galopante colectivismo en la forma de socialismo, comunismo y anarquía.

Relaci??n entre la masa muscular, la densidad mineral ??sea, la fuerza muscular, la aptitud funcional y la calidad muscular en personas mayores

OpenAIRE

Pati??o Villada, Fredy Alonso

2015-01-01

294 p. La tesis pretende determinar la frecuencia de la sarcopenia y osteporosis , problemas que afectan a la salud de las personas mayores, y analizar la relaci??n entre la masa muscular, la densidad mineral ??sea (DMO), la fuerza muscular, la aptitud funcional y la calidad muscular (CM). La muestra estudiada fue la formada por un grupo de 83 hombres y 175 mujeres mayores de Le??n (Espa??a). El estudio transversal eval??a ??ndices de masa grasa y densidad mineral ??sea y niveles d...

La Leche: consideraciones sobre la higiene y la alimentacion

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Gonzalo Luque Forero

1988-08-01

Full Text Available

I. De acuerdo con estudios realizados en las Universidades Nacional y de los Andes y la Secretaría de Salud, un alto porcentaje de las leches que se consumen en el Distrito Especial, presentaron adulteraciones y deficiente calidad fisicoquímica y microbiológica.

Un bajo porcentaje cumplió con todas las normas del Ministerio de Salud y se trata de Plantas que reciben y procesan leches de hatos, en donde las instalaciones, la alimentación, la sanidad, la calidad genética y la producción
están a la altura de los países industrializados.

II. El consumo de leche en el país es bajo y no alcanza los niveles recomendados por los organismos de Salud.

III. La leche es susceptible de contaminarse por la ignorancia, negligencia, prácticas fraudulentas o el empleo de técnicas inadecuadas en su procesamiento, transporte, conservación, comercialización e industrialización.

IV. Se plantean interrogantes sobre la presencia en la leche, de residuos de antibióticos, pesticidas, hormonas, tranquilizantes, compuestos inorgánicos y la forma como puedan estar afectando la salud humana.

V. La contaminación cada vez mayor del ambiente, el rápido transporte de los alimentos; sus técnicas de elaboración, los cambios en los hábitos alimentarios, han aumentado los peligros de enfermedades que se pueden trasmitir por los alimentos.

VI. La Salud depende en buena parte de la alimentación y si los alimentos de origen animal son medios de propagación de agentes patógenos y tóxicos, la respuesta a este interrogante no es solamente cómo aumentar la producción, sino cómo alimentar una población afectada por pobreza y desnutrición con alimentos sanos.

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

La identidad ensamblada: la ordenación de la felicidad

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Helena Bejar

2015-09-01

Full Text Available Inscrito dentro de la sociología de la cultura, el presente trabajo constituye un análisis crítico de la psicología positiva, que se toma como ejemplo paradigmático del actual imperativo cultural de la felicidad. El contexto teórico es el de la individualización contemporánea y la cultura psicoterapéutica, que preconizan una concepción del yo reflexiva y autoconstituida, al margen de una comprensión moral y social de la identidad personal. He estudiado las técnicas para lograr la “positividad”, constituyendo su análisis crítico el grueso de este trabajo. Asimismo he analizado los valores, los lenguajes morales de la psicología positiva y las tensiones de los diversos repertorios de significado. He tratado los textos que se encuentran a medio camino entre la psicología científica y la popular, que sirven como ejemplos de la literatura de consejos, que contiene normas explícitas de conducta y alude a las buenas y malas emociones, con la intención de definir un modelo de identidad personal concreto.

La ciudad, encrucijada de la historia y la literatura

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Antonio MORALES

2010-02-01

Full Text Available La poética urbana no significa tanto una teoría sobre la ciudad, sino un enfoque, una propuesta, compatible, obviamente, con otras, para su conocimiento. Supone tomar posesión simbólica del patrimonio cultural urbano, sin el que no hay memoria posible, identificando y localizando personas -los hombres y mujeres que física y espiritualmente hicieron la ciudad- acontecimientos, situaciones..., encuadrados en sus paisajes propios, para lo que será necesario el recurso a la historia y al documento, a la literatura y a la imaginación, al monumento arquitectónico o escultórico, al cuadro, el grabado y la fotografía, a la música..., en una plural y compleja lectura.

La vulnerabilidad social en la bioetica

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Ricardo Páez Moreno

2017-10-01

Full Text Available La vulnerabilidad en la bioética suele ser entendida desde la perspectiva individual, debido en parte al modo en que se concibe la salud bajo el modelo biomédico. La ética de la salud pública lleva a la comprensión de la vulnerabilidad desde el ángulo de lo social, incorporando características de aquella como son la prevención o el evitar el daño ante situaciones estructurales de dominación o dependencia. La toma de conciencia de la vulnerabilidad social en la investigación puede ayudar a evitar el abuso por una falta de autonomía en los sujetos.

Evaluando la paridad y la alternancia

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Hugo Picado León

2014-07-01

Full Text Available Este artículo tiene por objeto explicar cómo se formulan y funcionan la paridad y la alternancia de género según la legislación y la jurisprudencia costarricense, así como evaluar sus resultados a cuatro años de su introducción en la legislación nacional. El texto consta de dos partes; la primera describe los fundamentos conceptuales, teóricos y jurisprudenciales de la paridad y la alternancia, así como sus alcances sobre la representación en cargos electos, sobre la integración de los órganos partidarios y sobre las actividades de capacitación partidaria. La segunda parte procura explicar los resultados de la paridad y la alternancia en las elecciones legislativas de 2014, tomando en cuenta los resultados del anterior sistema de cuota

La libertad en la era digital

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Rafael Capurro

2014-10-01

Full Text Available La conferencia trata en la primera parte del concepto de sociedades de la información y del conocimiento en el marco de un reciente estudio de la UNESCO. Se explica luego la  diferencia entre ética o filosofía moral y moralidad entendida como las costumbres y reglas sociales que rigen en una sociedad. La tarea de la ética de la información como teoría descriptiva y emancipadora es presentada en la segunda parte, especialmente en relación a modos de comunicación oral, impresa y digital. En la segunda parte se analizan algunos problemas éticos de la sociedades de la información y del conocimiento relacionados con los cambios generados por el ‘cibermundo’, por ejemplo en el campo de las bibliotecas, así como en las formas en que instrumentos como el smart phone cambian la vida diaria de la gente creando nuevas oportunidades pero también nuevas formas de ‘teledesprecio’ (phubbing. En la última parte se documenta el debate actual sobre el tema de la vigilancia global que demuestra las posibilidades y límites de la libertad en las actuales sociedades de mensajes.

LA ULTIMA FASE. LA ELIMINACIÓN

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Rafael Nájera Morrondo

2013-01-01

Full Text Available En este artículo se presentan lo que se considera la última fase de la erradicación de la poliomielitis en España, la cual llevó 25 años, duran- te el período 1963-88, a raiz del brusco descenso que produjo en la incidencia de la enfermedad la introducción de la vacuna Sabin con cepas atenuadas en el año 1963. Ello debería haber conducido a la desaparición de la enfermedad en un corto período de tiempo, aunque no fue así a causa de la disminución de la vacunación y la vigilancia epidemiológica, que no se retomaron con seriedad hasta 1976. El último caso autóctono se produjo en 1988. Tras asumir Rafael Nájera la dirección del centro Nacional de Microbiología, Virología e Inmunología Sanitarias, el primer objetivo de su equipo fue la erradicación de la poliomielitis de nuestro país, introduciendo los criterios de clasificación de la OMS y los estudios de caracterización intertípica de las cepas aisladas de virus.

La genitalidad en la copla

OpenAIRE

Rozo Gauta, José; Rojas Peña, Víctor Raúl

2010-01-01

Antecedentes: por emisoras de la ciudad (Chiquinquirá) se vienen realizando concursos copleros, con la participación de los campesinos del área de influencia radial, quienes envían cartas para ganar premios. Con estos materiales se ha venído trabajando el pensamiento campesino, fundamentalmente en los siguientes 3 aspectos:1. La aprehensión del mundo actual.2. La estructura familiar y su reproducción en la copla.3. La manifestación sexual de los campesinos de la región.

LA PRUEBA DE LA INCONSTITUCIONALIDAD

OpenAIRE

Gugliano Herani, Renato

2015-01-01

La presente ponencia se construye de acuerdo con la legislación y experiencias del sistema de control de constitucionalidad brasileño. Propone un modelo de explicación dogmática de la interrelación entre dos institutos tradicionales del derecho aparentemente antagónicos: la prueba y la (in)constitucionalidad, resultando en la sistematización de la prueba de inconstitucionalidad en el derecho procesal constitucional brasileño. El estudio parte del reconocimiento de un déficit de investigación ...

La violencia intrafamiliar, el uso de drogas en la pareja, desde la perspectiva de la mujer maltratada

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Vaiz Bonifaz Rosa G.

2004-01-01

Full Text Available El presente estudio tiene la finalidad de visibilizar la violencia que afecta a las mujeres, teniendo como principales elementos precipitantes de la actitud violenta del agresor la ingesta de alcohol y/o drogas. Los objetivos del presente estudio son: conocer los significados que la mujer le atribuye a la violencia; reconocer los diferentes factores relacionados a la ocurrencia de la violencia intrafamiliar e identificar como se procesa el consumo de drogas en la pareja. El tipo de estudio es exploratorio y descriptivo, se utilizó la metodología cualitativa, el recorte empírico lo constituyeron seis mujeres, quienes acudieron a realizar su denuncia a la Comisaria de Mujeres de Lima. Los hallazgos muestran que el tiempo de unión osciló entre dos meses y dieciocho años, ocurriendo el maltrato en casi todo el tiempo de unión. Con respecto al tipo de violencia sufrida la de mayor magnitud fue la física; de forma más sutil la psicológica, la violencia sexual no fue referida, el dinero y celos fueron referidos como focos desencadenantes de las discusiones, las que están asociados al uso de alcohol y droga en el agresor. Las categorías establecidas fueron: el tipo de violencia sufrida por las mujeres, el contexto de la violencia, la repercusión de la violencia sufrida por la mujer en su salud y la reacción de violencia sufrida por medio de la denuncia. Como principales conclusiones tenemos que la violencia contra las mujeres se revela como tema social y sanitario, con repercusiones en la morbi-mortalitad y en términos de calidad de vida de las mujeres., en el campo de la salud, es necesario reconocer a las mujeres en situación de violencia, considerar como factores de riesgo para la pareja el uso de alcohol y drogas, las mujeres ocultan por vergüenza la problemática que viven, el personal de salud debe ser capaz de diagnosticar la violencia en sus diferentes formas, expresadas por quejas o dolores crónicos sin causas aparentes.

La violencia intrafamiliar, el uso de drogas en la pareja, desde la perspectiva de la mujer maltratada

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Rosa G. Vaiz Bonifaz

Full Text Available El presente estudio tiene la finalidad de visibilizar la violencia que afecta a las mujeres, teniendo como principales elementos precipitantes de la actitud violenta del agresor la ingesta de alcohol y/o drogas. Los objetivos del presente estudio son: conocer los significados que la mujer le atribuye a la violencia; reconocer los diferentes factores relacionados a la ocurrencia de la violencia intrafamiliar e identificar como se procesa el consumo de drogas en la pareja. El tipo de estudio es exploratorio y descriptivo, se utilizó la metodología cualitativa, el recorte empírico lo constituyeron seis mujeres, quienes acudieron a realizar su denuncia a la Comisaria de Mujeres de Lima. Los hallazgos muestran que el tiempo de unión osciló entre dos meses y dieciocho años, ocurriendo el maltrato en casi todo el tiempo de unión. Con respecto al tipo de violencia sufrida la de mayor magnitud fue la física; de forma más sutil la psicológica, la violencia sexual no fue referida, el dinero y celos fueron referidos como focos desencadenantes de las discusiones, las que están asociados al uso de alcohol y droga en el agresor. Las categorías establecidas fueron: el tipo de violencia sufrida por las mujeres, el contexto de la violencia, la repercusión de la violencia sufrida por la mujer en su salud y la reacción de violencia sufrida por medio de la denuncia. Como principales conclusiones tenemos que la violencia contra las mujeres se revela como tema social y sanitario, con repercusiones en la morbi-mortalitad y en términos de calidad de vida de las mujeres., en el campo de la salud, es necesario reconocer a las mujeres en situación de violencia, considerar como factores de riesgo para la pareja el uso de alcohol y drogas, las mujeres ocultan por vergüenza la problemática que viven, el personal de salud debe ser capaz de diagnosticar la violencia en sus diferentes formas, expresadas por quejas o dolores crónicos sin causas aparentes.

La agresividad en la infancia

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Beatriz Gregoret

2012-10-01

Full Text Available Desde hace un tiempo, nos enfrentamos conmocionados, con hechos de violencia en las escuelas. Sabemos que esto no ocurre sólo en las instituciones educativas, sino que se constituye como un fenómeno social que preocupa a los distintos sectores de la comunidad. Proponemos pensar esta problemática desde el marco teórico del Psicoanálisis. Es preciso diferenciar la agresividad como correlato de la constitución subjetiva del sujeto, de la violencia, definida como la agresividad en su dimensión radical y provocada por el  desalojo, por la falta de palabras que alojen a cada sujeto en la trama familiar y social. Apostamos a la posibilidad de pensar diferentes estrategias de aplicación en la praxis escolar como respuestas inventadas a la luz de los impasses, que estas situaciones de agresión y violencia plantean.

La lengua y lo afro: de la literatura oral a la oralitura

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Iván Rodrigo Mendizábal

2012-11-01

Full Text Available Este ensayo aborda la oralitura, concepto que alude a la comunicación que inscribe las prácticas orales, rituales, sociales performativas, además de las prácticas de escritura en las comunidades afro. Pasando por los procesos de inscripción de la lengua española durante la colonia, en las que éstas tuvieron que aceptar y adaptar la institución lingüística dominante de forma violenta; la asunción local y personal de la lengua mediante inflexiones para derivar en la onomatopeya; hasta la apropiación colectiva de la lengua y la incorporación en ésta de una cosmovisión; el ensayo discute los postulados de la sociolingüística frente a los de la etnometodología. La idea es ver cómo los afroamericanos elaboran sus narrativas. La oralitura vendría a ser el dispositivo comunicacional como lenguaje-nación.

La historia de la ciencia en la enseñanza de la célula

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Laura Carrillo

2012-04-01

Full Text Available A través de este artículo se propone aportar ideas para sustentar la incorporación de la historia de la ciencia en la enseñanza de la biología. Para ello, se realiza una breve reconstrucción histórica y posteriormente, un análisis exploratorio sobre cuáles son los conceptos acerca de la célula que se incorporan en los libros de texto y sí éstos, tienen relación con cómo se construyó la teoría celular. Con esta propuesta se deja en evidencia que los libros de texto, sólo enseñan conceptos sobre la estructura y función de la célula, relacionados principalmente con aportes del Siglo XIX y que poco se promueven conceptos para la comprensión de la célula como unidad hereditaria de origen, estructuras y funciones de los organelos celulares, cuyas propuestas se consolidaron durante el S.XX.

Impacto de la nube en la productividad de la PYME

OpenAIRE

Mucci Garcia, Ernesto

2010-01-01

El objetivo principal de este proyecto, es estudiar una forma de que la PYME aproveche las ventajas que se intuye que ofrece la Nube. Para lograrlo se crea una base de datos que almacene la información de los servicios de la Nube útiles para la PYME. Posteriormente se define un prototipo de una aplicación informática, que permite encontrar servicios Nube usando la BD. Además de poder buscar los servicios con una serie de criterios útiles para la empresa, se genera una lista de cinco recomenda...

“La posición de la Gran Logia de la Isla de Cuba ante la crisis de 1929 a 1933: su reflejo en la revista La Gran Logia”

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Haens Beltrán Alonso

2012-01-01

Full Text Available La Gran Logia de la Isla de Cuba, principal organismo simbólico de la masonería cubana sufrió durante los años 1929-1933 la grave crisis que afectó a la sociedad cubana. El presente trabajo aborda el posicionamiento de este gobierno masónico ante la situación política, utilizando como fuente fundamental los planteamientos vertidos en su órgano de prensa oficial la revista La Gran Logia. Se parte de la premisa de que la masonería no es una institución política, pero que su funcionamiento la obliga a adoptar una posición ante los problemas que la afectan. ¿Cuál fue la posición de la Gran Logia de la Isla de Cuba sobre la crisis imperante? ¿Cómo expresó su posición sin violar los preceptos masónicos de no discutir sobre política? Estas son las preguntas que en este trabajo se pretenden responder.

La Hispania prerromana en la historia de la escritura

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Javier de HOZ

2009-12-01

Full Text Available RESUMEN: Las escrituras paleohispánicas presentan la particularidad de ser una mezcla de alfabeto y silabario, que presenta interés no sólo en sí sino como problema general de la historia de la escritura. En el artículo se discute el origen del sistema, partiendo de la idea de que la más primitiva escritura paleohispánica, todavía no identificada, se originó como adaptación de la escritura fenicia que era un silabario con valores vocálicos no explícitos. A la vista de la escritura del SO, que parece ser un alfabeto redundante (con signos distintos pata una misma oclusiva en distintas posiciones antevocálicas, se defiende la posibilidad de que el excesivamente rico inventario fenicio de oclusivas diese lugar a la aparición del alfabeto redundante y éste a la del semisilabario.ABSTRACT: Early Hispanic writings are anomalous, part syllabic, part alphabetical systems, and of general interess from the point of view of the history of writing. This article discuss the origin of the system as adaptation of the Phoenician consonatal syllabary. There is evidence in the writing from the South-West for an alphabet with redundancy, born from the rich Phoenician inventory of stops; the syllabic component of the other Hispanic writings was a development of this redundancy.

La mejora de la participación de la comunidad en la escuela con grupos interactivos

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Carmen Álvarez-Álvarez

2017-07-01

Full Text Available La revisión de la literatura científica sobre la participación de la comunidad en los centros educativos ha demostrado sus beneficios en el clima de las escuelas y en el nivel de aprendizaje de sus alumnos. Sin embargo, la participación real y efectiva de la comunidad sigue siendo una asignatura pendiente en la mayoría de los centros educativos. Este artículo explora las posibilidades de aumentar dicha participación a partir de una estrategia específica a nivel de aula: los grupos interactivos. Esta práctica ha sido identificada por la investigación europea como una forma efectiva de mejorar el aprendizaje y la convivencia entre los estudiantes. El artículo presenta un estudio de caso en España que analiza el incremento de la participación de la comunidad cuando se asocia a esta práctica de apoyo directo al aprendizaje. Los resultados confirman que los grupos interactivos eliminan barreras para la participación de la comunidad y tienen un efecto de “bola de nieve” al aumentar la participación en otros ámbitos escolares. Finalmente, se comentan las implicaciones del estudio para futuras investigaciones.

La política de la libertad en la posguerra europea y la transición española a la democracia

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Manuel Álvarez Tardío

2009-12-01

Full Text Available El novecientos fue, para Europa, la centuria de la conquista de la democracia y de un indudable progreso social, económico y político. Pero también del totalitarismo, de la re- volución, de los campos de concentración y de la gran depresión. En España, como en muchas otras regiones vecinas, la conquista de la democracia fue tardía y problemática, no exenta de una fuerte polarización y un alto grado de violencia política. El siglo XX español también cul- minó con la conquista de la libertad y la democracia, pero más tarde que en otras partes y tras un camino traumático. Este artículo analiza las bases intelectuales sobre las que se compatibili- zaron libertad y participación tras el final de la dictadura de Franco. Se estudia la cultura política de los principales actores y se sostiene que, al igual que en otros contextos de la posguerra eu- ropea de los años cuarenta, la política de la libertad estuvo precedida de una aproximación de las culturas políticas de las elites, derivada de un análisis crítico del pasado reciente. El artículo incluye, por tanto, un análisis previo de la política de la libertad, la reconstrucción y el bienestar en la posguerra europea, así como de los fundamentos liberales de las nuevas democracias atlánticas.

La Facultad de Medicina de la Universidad Nacional, sus exalumnos, aexmun, la comunidad y la televisión

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Antonio Ramirez Solo

1998-10-01

Full Text Available Es imperioso dar permanentemente instrucción a la comunidad en un campo fundamental e imprescindible para el bienestar del individuo y la sociedad como es el de la salud, en respuesta a las crecientes necesidades existentes y a los grandes avances científicos y tecnológicos desde el punto de vista de la prevención, la atención y la rehabilitación, a favor de la niñez, la persona adulta, la mujer embarazada y la tercera edad, con el fin de disminuir la morbimortalidad, con incremento de bienestar y de productividad, a través de la instrucción audiovisual por un medio masivo y objetivo como es la televisión.

Contamination of North Sea and Baltic Sea with long-living iodine-129 and other anthropogenic radionuclides; Kontamination von Nord- und Ostsee mit langlebigem Iod-129 und anderen anthropogenen Radionukliden

Energy Technology Data Exchange (ETDEWEB)

Tosch, Luebbert

2010-10-12

The radionuclide iodine-129 (T{sub 1/2} = 15.7 Ma) is produced in nature by spontaneous fission of uranium-238 and by cosmic ray induced spallation of xenon. Due to the military and civil use of neutron-induced fission of uranium-235 and plutonium-239 a huge amount of iodine-129 has been released into the environment. The main sources of anthropogenic {sup 129}I are the reprocessing plants in La Hague (France) near the English Channel and in Sellafield (UK) close to the Irish Sea. The natural equilibrium {sup 129}I/{sup 127}I-isotopic ratios are estimated to 1.5 . 10{sup -12} for the marine hydrosphere and to 3.0 . 10{sup -13} for the terrestrial biosphere respectively. Due to the emissions of anthropogenic iodine-129 the {sup 129}I/{sup 127}I-isotopic ratios have been increased in all compartments of the environment. Surface water samples taken from the English Channel, the North Sea, the Baltic Sea, the Irish Sea, and the North Atlantic give information about anthropogenic changes. Iodine turns out to be a conservative tracer in seawater. The iodine-127 concentrations in seawater except for coastal areas are rather constant (40.7 ± 6.2 ng/g). The observed {sup 129}I/{sup 127}I-isotopic ratios range between 10{sup -10} and more than 10{sup -6}. The variation of the {sup 129}I/{sup 127}I-isotopic ratios is caused by the admixture of anthropogenic iodine-129. Water samples taken far away from the reprocessing plants show the lowest isotopic ratios. The highest {sup 129}I/{sup 127}I-isotopic ratios are found near the reprocessing plants. The transport of {sup 129}I from La Hague has a rather clear pattern. It can be observed along the coasts of France, Belgium, the Netherlands, Germany and Denmark. The iodine-129 emissions from Sellafield can be followed northbound along the Scottish coast. The results of other anthropogenic radionuclides are used for discussing transport processes in the North Sea and the Irish Sea. Large areas in the North Sea are characterised by

La mirada de la autopoiesis respecto de la constitución

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Germano Schwartz

2015-01-01

Full Text Available En el presente ensayo se pretende –al encontrar evidencias de cuestionamientos acerca de la constitución como la norma superior del ordenamiento jurídico– estudiar la ley mayor desde otra base de análisis i.e. la sistémico-autopoiética, ante la insuficiencia de los modelos jurídicos tradicionales respecto de la posición de una ley fundamental en el contexto de la sociedad actual. El presente trabajo parte de la premisa de que la constitución solamente puede ser comprendida desde la diferenciación funcional entre el sistema político y el sistema jurídico, representando el acoplamiento estructural entre ambos sistemas. En este sentido, la autopoiesis de la constitución opera en virtud de su auto-referencialidad, contando al mismo tiempo con una apertura hacia los otros subsistemas. La jerarquía constitucional kelseniana ya no responde a los anhelos de una sociedad de riesgo y de indeterminación. La circularidad decisional adapta y transforma la constitución a partir de sus propios elementos jurídicos y con base en una nueva lógica, más apta para responder a las influencias comunicacionales de los demás subsistemas sociales. En este razonamiento, la superioridad de la constitución y su carácter de ley fundamental no son insumos para una definición estática. Tales características son (reconstruidas en el interior del sistema a partir de su lógica interna propia.

La arquitectura de la eurozona y la crisis de su periferia

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Víctor Manuel Cuevas Ahumada

2015-01-01

Full Text Available Este trabajo analiza las causas de la crisis económica de la periferia de la eurozona y propone medidas orientadas tanto a recuperar el crecimiento económico en el corto plazo, como a hacerlo sostenible en el largo plazo. Las medidas de reactivación económica y las reformas estructurales propuestas parten de un estudio de las vulnerabilidades que el diseño institucional de la eurozona generó y la crisis financiera de EE.UU. exacerbó. Como podrá verse, la inconsistencia entre la arquitectura de la eurozona y las características económicas de algunas naciones participantes fue responsable de los desequilibrios fiscales y los dife - renciales de competitividad que imperan en la región. Las dificultades para desvalorizar la deuda pública y recuperar el equilibrio fiscal, así como el proceso deflacionario en curso, han sido asimismo consecuencia de la adopción de la moneda única y de los cambios en la política macroeconómica asociados a esta. En este contexto, se plantean modificaciones al marco institucional de la eurozona que repercutirían positivamente en la competitividad internacional, las finanzas públicas y la salud de las instituciones financieras. Derechos Reservados©2015 Universidad Nacional Autónoma de México, Facultad de Contaduría y Administración. Este es un artículo de acceso abierto distribuido bajo los términos de la Licencia Creative Commons CC BY-NC-ND 4.0.

LA CONSERVACIÓN DE LOS PAISAJES ATERRAZADOS EN LA TOSCANA: ENTRE LA UTOPÍA Y LA REALIDAD

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María Hernández Hernández

1995-01-01

Full Text Available Las notables transformaciones que se producen tras la Segunda Guerra Mun- dial en la estructura socio-económica italiana, se han traducido en profundos cambios en la agricultura tradicional. Hecho que ha generado notables degrada- ciones ambientales. Áreas que, con la difusión de la nueva filosofía ambiental, pueden adquirir un nuevo valor. Así, frente a la función productiva, en crisis, estos espacios podrían enarbolar la bandera del valor ambiental, cultural o paisajístico. Sin embargo, para lograrlo, es necesario la adopción de una serie de disposiciones tendentes a la conservación de la sistematización hidráulica y agraria dieciochesca, su principal atractivo. Sin embargo, ésta choca con una serie de dificultades entre las que destacan la escasez de financiación, la lentitud en aplicar la legislación o el carácter contradictorio de ciertas normativas.

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

LA DINÁMICA DE LA POBLACIÓN EN LA PROVINCIA DE ALICANTE DURANTE LA GUERRA CIVIL

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Vicente Gozálvez Pérez

1993-01-01

Full Text Available Durante la guerra civil española de 1936-39, la provincia de Alicante, pese a su situación de retaguardia, tuvo un movimiento natural con graves dificultades, sobre todo en 1939, a resultas del clima de inseguridad y las dificultades económicas creadas por el conflicto; el fuerte aumento de la mortalidad infantil entre 1937 y 1941, así como la sobremortalidad acumulada durante 1936-41, subrayan la fortísima incidencia del con- flicto. La migración neta, negativa para la provincia entre 1888 y 1930, fue muy positiva en 1931-40, debido, entre otras causas, a los desplazamientos provocados por la guerra, especialmente significativos para la ciudad de Alicante.

La violencia sexual como un atentado contra la dignidad de la mujer

OpenAIRE

Gil Millan, Maximiliana

2015-01-01

La violencia sexual contra la mujer es la manifestación extrema de la desigualdad y del sometimiento en el que viven las mujeres en el mundo. Constituye un atentado contra el derecho a la vida, a la libertad, y la dignidad de las mujeres. Por tanto, para

La salud en el marco de la psicología de la religión y la espiritualidad

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Japcy Margarita Quiceno

2009-01-01

Full Text Available El siguiente trabajo tiene como objetivo presentar una descripción del impacto que ha tenido en la salud "la psicología de la religión y la espiritualidad". Se muestra la evolución histórica de este constructo a lo largo del siglo XX, hasta llegar a las investigaciones basadas en la evidencia de las relaciones de la religión y la espiritualidad con la salud mental y física, y de investigaciones sobre los procesos de intervención en salud, enfocadas desde la espiritualidad. En conclusión, son muchas las investigaciones que plantean que la religión y la espiritualidad son variables moderadoras y amortiguadoras ante eventos traumáticos de la vida como lo es una enfermedad

La depresión incluida en la historia de la familia

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María Concepción Silva Pezo

2004-01-01

Full Text Available La depresión ejerce un impacto sobre quien es portador y sus familiares cuando ésta se incluye en la vida de la familia. Este estudio de tipo etnográfico tuve como objetivo describir las vivencias del portador de depresión y sus familiares en el proceso de inserción de la enfermedad en el grupo familiar. Para la recolección de los datos se utilizó las técnicas de la observación participante y la entrevista del contexto familiar de 13 familias peruanas quienes conviven uno de sus miembros con el diagnóstico de depresión, procedentes de dos consultorios de salud mental pertenecientes a una Institución Psiquiátrica Peruana. Fueron considerados los aspectos éticos referidos por la referida Institución de Salud Mental. El tema cultural fue “La depresión insertada en la vida de la familia” que refleja el sufrimiento causado por la enfermedad en los miembros de la familia. El bagaje cultural está presente en las actitudes y el pensamiento de las familias que conviven con el miembro portador de depresión