高速炉の原子炉格納容器の弾塑性解析条件と破損判定圧力の関係に関する検討

抄録

Containment vessel (CV) is an important structure to prevent a significant and sudden radioactive release; however, the safety margin of the containment vessel against the internal pressure is not numerically clarified. In order to evaluate pressure toughness of containment vessel boundary for the Light water reactors, the Japan society of mechanical engineers established the evaluation guidelines as “Structural integrity evaluation guideline under severe accident condition”. To evaluate the features of the response in the CV of Fast reactor under the pressure and temperature exceeding the specifications, a series of inelastic analysis for the CV of the Fast reactor was performed referring to the guideline for the Light water reactors. Material properties, tightening torque of the equipment hatch and coefficient of friction were varied in the analysis. Relationships between the response of the CV and the analysis parameters were discussed on the basis of the calculated results.