Development of multiscale numerical simulation method for thermal transient phenomena of sodium-cooled fast reactors, 1; Outline of simulation method development

Tanaka, Masaaki  ; Hiyama, Tomoyuki ; Murakami, Satoshi*; Doda, Norihiro  ; Ohshima, Hiroyuki

In order to improve the accuracy of the numerical estimation method for the thermal transient phenomena in the sodium-cooled fast reactor has been conducted by using code coupling technology with the system analysis code for plant dynamics analysis, the multi-dimensional code for analysis of thermal-hydraulics in the plenum, and numerical estimation code of structural integrity for the local region, in viewpoint of enhancement of safety measures in sodium-cooled fast reactor. In this presentation, outline of simulation method development is introduced.