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AbstractAbstract
[en] In this work, the full core modelling is performed to improve neutronic analyses capability for nuclear research reactors using SCALE4.4 code system. KENOV.a module of SCALE4.4 code system is utilized for full core neutronic analysis. The ORIGEN-S module is coupled with the KENOV.a module to perform burnup dependent neutronic analyses. Results of neutronic calculations for 1st cycle of Cekmece TR-2 research reactor are presented. In particular, coupling of KENOV.a and ORIGEN-S modules of SCALE4.4 is discussed. The preliminary results of 2-D burnup dependent neutronic calculations are also given. These results are extended to burnup dependent core calculations of TRIGA Mark-II research reactors. The code system developed here is similar to the code system that couples MCNP and ORIGEN2.(author)
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Jencic, I.; Glumac, B. (Nuclear Society of Slovenia (Slovenia)) (eds.); Nuclear Society of Slovenia, Ljubljana (Slovenia). Funding organisation: Inst. Jozef Stefan, Ljubljana (Slovenia); European Nuclear Society, Brussels (Belgium); Ministry of Education, Science and Sport of Slovenia, Ljubljana (Slovenia); Slovenian Nuclear Safety Administration, Ljubljana (Slovenia); Agency for Radwaste Management, Ljubljana (Slovenia); Faculty of Mechanical Engineering, Univ. of Ljubljana (Slovenia); Graduate Program Nucelar Engineering, Univ. of Ljubljana (Slovenia); Inst. of Metals and Technology, Ljubljana (Slovenia); The Inst. of Metal Constructions, Ljubljana (Slovenia); The Milan Vidmar Electroinstitute, Ljubljana (Slovenia); Welding Inst., Ljubljana (Slovenia); NPP Krsko (Slovenia); Framatome, Paris (France); Westinghouse Electric Systems Europe S.A., Brussels (BE); Elmont d.o.o., Krsko (Slovenia); Inetec, Zagreb (Croatia); NUMIP d.o.o, Krsko (Slovenia); Q Techna d.o.o., Krsko (Slovenia); SIAP d.o.o., Krsko (Slovenia); 97.2 Megabytes; ISBN 961-6207-17-2; ; 2001; [9 p.]; International Conference Nuclear Energy in Central Europe 2001; Portoroz (Slovenia); 10-13 Sep 2001; Also available from Slovenian Nuclear Safety Administration, Zelezna cesta 16, Ljubljana (SI) or Nuclear Society of Slovenia, Jamova 39, Ljubljana (Slovenia); 4 refs., 2 tabs., 9 figs.
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ACCIDENTS, COMPUTER CODES, EDUCATION, ENRICHED URANIUM REACTORS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, STRUCTURAL MODELS, THERMAL REACTORS, TRIGA TYPE REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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