浜岡１号機原子炉圧力容器に関する研究 ―廃止措置プラントを活用した材料研究―
概要
Fact finding survey of actual reactor pressure vessel in decommissioning Hamaoka nuclear power station has been conducted. All boat samples was already transported to a domestic post irradiation examination (PIE) facility. During the PIE, un-irradiated archive materials was also investigated for better understanding of cladding HAZ in base metal, as introduced in the 14th JSM conference. This is the progress report describing some new results obtained after the conference.
