Raepsaet, X.; Damian, F.; Ohlig, U.A.; Brockmann, H.J.; Haas, J.B.M. de; Wallerbos, E.M., E-mail: xraepsaet@cea.fr2003
AbstractAbstract
[en] In the frame of the European contract HTR-N, a work package is devoted to the code validation and method improvements as far as the high temperature gas-cooled reactor (HTGR) core modelling is concerned. Institutions from three countries are involved in this work package: FZJ in Germany, NRG and IRI in the Netherlands, and CEA in France. The present work is based on a benchmark problem proposed by JAERI through the IAEA. It concerns the HTTR's start-up core physics experiments that were a good opportunity for the European partners to validate their calculational tools and methods. The number of fuel columns necessary to achieve the first criticality and the excess reactivity for 18, 24, and 30 fuel columns in the core had to be evaluated. Pre-test and post-test calculational results, obtained by the partners, are compared with each other and with the experiment. Parts of the discrepancies between experiment and pre-test predictions are analysed and tackled by different treatments. In the case of the Monte Carlo code TRIPOLI4, used by CEA, the discrepancy between measurement and calculation at the first criticality is reduced to Δk/k∼0.85%, when considering the revised data of the HTTR benchmark [Fujimoto, private communication]. In the case of the diffusion codes, this discrepancy is reduced to Δk/k∼0.8% (FZJ) and 2.7 or 1.8% (CEA)
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Source
S0029549303000268; Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
Literature Type
Numerical Data
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Raepsaet, X.; Damian, F.; Ohlig, U.A.; Brockmann, H.J.; Haas, J.B.M. de; Wallerboss, E.M.
HTR-2002: Proceedings of the conference on high temperature reactors2002
HTR-2002: Proceedings of the conference on high temperature reactors2002
AbstractAbstract
[en] Within the frame of the European contract HTR-N1 calculations are performed on the benchmark problems of the HTTR's start-up core physics experiments initially proposed by the IAEA in a Co-ordinated Research Programme. Three European partners, the FZJ in Germany, NRG and IRI in the Netherlands, and CEA in France, have joined this work package with the aim to validate their calculational methods. Pre-test and post-test calculational results, obtained by the partners, are compared with each other and with the experiment. Parts of the discrepancies between experiment and pre-test predictions are analysed and tackled by different treatments. In the case of the Monte Carlo code TRIPOLI4, used by CEA, the discrepancy between measurement and calculation at the first criticality is reduced to Δk/k∼0.85%, when considering the revised data of the HTTR benchmark. In the case of the diffusion codes, this discrepancy is reduced to: Δk/k∼0.8% (FZJ) and 2.7 or 1.8% (CEA). (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); European Nuclear Society, Bern (Switzerland); 695 p; 2002; [5 p.]; HTR-2002: Conference on high temperature reactors; Petten (Netherlands); 22-24 Apr 2002; 5 refs, 3 figs, 2 tabs
Record Type
Report
Literature Type
Conference; Numerical Data
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CALCULATION METHODS, COMPUTER CODES, DATA, DIFFERENTIAL EQUATIONS, ENRICHED URANIUM REACTORS, EQUATIONS, EVALUATION, EXPERIMENTAL REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HTGR TYPE REACTORS, INFORMATION, NUMERICAL DATA, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH PROGRAMS, START-UP
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