抄録
Thermal transient stress at core support structure of advanced fast reactor was evaluated using thermal hydraulic-structure total analysis method with experimental design. Maximum thermal stress is calculated 15〜18% larger than nominal thermal stress by uncertainty of system parameters. Maximum thermal stress was evaluated 63〜68% larger than nominal thermal stress when predicted by the past deign method, therefore about 40% excessive imaginary stress could be appropriate by thermal hydraulic-structure total analysis.
