ナトリウム冷却高速炉の設計合理化に向けたマルチレベルシミュレーションシステムによる仮想プラントモデルの構築

～米国高速実験炉EBR-II適用による機能確認～

抄録

In Japan Atomic Energy Agency (JAEA), a virtual plant model of the sodium-cooled fast reactor (SFR) plant composed in a computer is being developed to reduce the development cost, by replacing the costly experiments to the numerical simulations with analyses of the physical phenomena accounting for the interaction between components under various plant conditions. To establish the methodology to construct the virtual plant model and perform the coupled analysis, the results of the numerical analysis of a ULOHS test conducted in the U.S. experimental fast reactor named EBR-II was examined. In the virtual plant model of EBR-II, the upper plenum in the reactor vessel and the cold plenum, the core, and other components in heat transport system were modeled by using a multi-dimensional computational fluid dynamics (CFD) code, a coupled method of core thermal hydraulics, thermal deformation of the fuel assemblies, and neutronics analysis codes, and a plant dynamics analysis code, respectively, in the framework of the multi-level simulation system developed in JAEA. Through the numerical analysis of the ULOHS test, applicability of the virtual plant model was confirmed in comparison with the measured data including the core inlet temperature and the reactor power.