| 内容記述 | The liquid-metal fast reactor (LMFR) safety analysis computer code SIMMER-III successfully reached its first milestone with development of Version 2, a two-dimensional, three-velocity-field, multiphase, multicomponent, Eulerian, fluid-dynamics code coupled with a spase-dependent neutron kinetics model. The development and assessment of SIMMER-III has been participated internationally by Forschungszentrum Karlsruhe, Germany and Commissariat 'a l'Energie Atomique, France. To advance the code as a next-generation standard tool for LMFR safety analysis, it was agreed among the partners that a joint code assessment program should be conducted comprehensively and systematically. This program consists of a two-step effort: Phase 1 for fundamental or separate-effect assessment of individual code models; and Phase 2 for integral assessment of key physical phenomena relevant to LMFR safety. THis report describes the achivement of the SIMMER-III Phase 2 assessment program. The report details the results of each of the 34 test problems analyzed, conducted in five major categories of key LMFR safety phenomena, and synthesizes the outcome of the analyses. Through this extensive study, effectively utilizing the international collaboration scheme and world experimental database available, the SIMMER-III code has proved to be basically valid both numerically and physically, with significantly enhanced applicability and flexibility over its predecessor, SIMMER-II. Thus the code is now applicable to integral reactor safety calculations. The study has also identified limitations and problem areas on which future code development and assessment should focus.
著者所属: 日本原子力研究開発機構(JAEA) |
