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AbstractAbstract
[en] The main trends in the CERCA company (France) activity connected with production of fuel elements and fuel assemblies for research reactors are considered. The CERCA company has contributed much in solution of the problem of research reactor conversion for low-enriched (less than 20%) fuel on the base of uranium silicide (U3Si2)
Original Title
Sovershenstvovanie tekhnologii nizkoobogashchennogo topliva
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Translted from English: Nuclear Engineering International (1991) v. 33(449) p. 50-51.
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Tissier, A.
Proceedings of the 1990 International Meeting on Reduced Enrichment for Research and Test Reactors1993
Proceedings of the 1990 International Meeting on Reduced Enrichment for Research and Test Reactors1993
AbstractAbstract
[en] The objective of this paper is to present the changes which occurred at CERCA's manufacturing facility, related to the use of silicide LEU fuel. Today, CERCA is producing routinely more than twice as many plates as in the year 1988. These plates contain either UAlx or UeSi2 fuel. We will examine how CERCA managed to do so in a short period of time and succeeded to stabilize its production. Also, we will take the opportunity to present our status of silicide irradiation program. Finally, the increase from 1986 to 1990 in the use of LEU 19,75 % U235 enriched uranium, to produce MTR fuel at CERCA will be exposed
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Argonne National Lab., IL (United States); 447 p; Jul 1993; p. 51-65; International meeting on reduced enrichment for research and test reactors; Newport, RI (United States); 23-27 Sep 1990; Also available from OSTI as DE94006497; NTIS
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Durand, J.P.; Fanjas, Y.; Tissier, A.
Reduced enrichment for research and test reactors: Proceedings1993
Reduced enrichment for research and test reactors: Proceedings1993
AbstractAbstract
[en] CERCA has initiated a fundamental research program for better understanding the behaviour of materials during the fuel plate manufacturing process. Thanks to a major breakthrough and a careful and systematic experimental validation of fabrication parameters, CERCA succeeded to set up an advanced production process adapted to high densities up to 6 g UT/cm3. The fabrication test was carried out on full size plates with pure U3Si2 in industrial conditions (on 50 plates). Next development steps include checking the stability of obtained results on large scale production and evaluating the cost increase due to the use of advanced process. Furthermore irradiation tests are necessary to qualify the 6 g density in reactor
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Argonne National Lab., IL (United States); 376 p; Jul 1993; p. 50-62; 1992 international meeting on reduced enrichment for research and test reactors; Roskilde (Denmark); 27 Sep - 1 Oct 1992; Also available from OSTI as DE94012405; NTIS
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AbstractAbstract
[en] CERCA's main objective is to satisfy its customers, improving quality of its products, and maintaining the costs as low as possible. Its Research and Development program reveals this goal. Different R and D topics under development at short (recycling of scraps), at medium (X-ray imaging machine) and at long term (improvement of fuel materials) are presented as evidence of this will. (orig.)
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Thamm, G. (ed.); Brandt, M. (ed.); Forschungszentrum Juelich GmbH (Germany). Zentralabteilung Forschungsreaktoren und Kerntechnische Betriebe; Konferenzen des Forschungszentrums Juelich; v. 4; 577 p; ISBN 3-89336-063-8; ; 1991; p. 51-58; 12. international meeting on reduced enrichment for research and test reactors (RERTR-12); Berlin (Germany); 10-13 Sep 1989; ISSN 0938-6521; ; Available from FIZ Karlsruhe
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[en] A new X-ray Inspection Machine based on directly numerized signals has been developed by CERCA. For U-distribution check, this machine presents specific advantages with respect to the previously used equipments. It also allows image processing for further developments
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Argonne National Lab., IL (United States); 376 p; Jul 1993; p. 85-91; 1992 international meeting on reduced enrichment for research and test reactors; Roskilde (Denmark); 27 Sep - 1 Oct 1992; Also available from OSTI as DE94012405; NTIS
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AbstractAbstract
[en] CERCA's main objective is to satisfy its customers, improving quality of its products, and maintaining the costs as low as possible. Its Research and Development program reveals this goal. Different R and D topics under development at short (recycling of scraps), at medium (X-ray imaging machine) and at long term (improvement of fuel materials) are presented as evidence of this will. (orig.)
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Thamm, G.; Brandt, M. (eds.); Forschungszentrum Juelich GmbH (Germany). Zentralabteilung Forschungsreaktoren und Kerntechnische Betriebe; 597 p; ISBN 3-89336-063-8; ; 1991; p. 51-58; 12. international meeting on reduced enrichment for research and test reactors (RERTR-12); Berlin (Germany); 10-14 Sep 1989; ISSN 0938-6521; ; Also available from FIZ Karlsruhe
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AbstractAbstract
[en] An update on research, development and creations at the CERCA firm in the area of research reactor fuels
[fr]
Le point sur la recherche et developpement et les realisations conduites par la societe CERCA dans le domaine des combustibles destines aux reacteurs de rechercheOriginal Title
Le developpement des combustibles a bas enrichissement
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Tissier, A.; Fanjas, Y.
IGORR 2: Proceedings of the 2. meeting of the International Group On Research Reactors1992
IGORR 2: Proceedings of the 2. meeting of the International Group On Research Reactors1992
AbstractAbstract
[en] The new FRM II design is based on a compact core. The uranium fuel is silicide U3Si2. A particularity of the fuel plates relates to the uranium distribution in the meat which consists of 2 areas of different uranium densities: 3 g/cm3 and 1,5 g/cm3. In the first part, this paper describes the main characteristics of the fuel plates. In the second part, the results of preliminary fabrication tests are given. Full size fuel plates have been produced using depleted uranium and adjusting the parameters of the production processes. These tests show that the fuel plates can be produced on industrial scale. Additional developments are carried out to set up series inspection techniques adapted to this double density product. (author)
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Commissariat a l'Energie Atomique, Grenoble Cedex (France); Technicatome, Gif sur Yvette Cedex (France); 501 p; 1992; [14 p.]; IGORR 2: 2. meeting of the International Group On Research Reactors; Saclay (France); 18-19 May 1992; 2 refs, figs
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ACTINIDE COMPOUNDS, ACTINIDES, ELEMENTS, ENRICHED URANIUM REACTORS, FUEL ELEMENTS, HEAVY WATER MODERATED REACTORS, METALS, PHYSICAL PROPERTIES, POOL TYPE REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SILICIDES, SILICON COMPOUNDS, TESTING, THERMAL REACTORS, URANIUM, URANIUM COMPOUNDS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
[en] Cerca has been actively contributing to R+D worldwide on low-enrichment (LEU < 20%) fuels for research reactors. In 1982 Cerca developed the silicide fuel
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[en] The French company CERCA played a leading part in the international effort to develop new Low Enriched Uranium (less than 20%) silicide fuel (U3Si2) for research reactors. Now it is focusing its research on improving the production process, particularly with regard to quality and safety. (author)
Original Title
Low enriched uranium fuel
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