原子炉圧力容器鋼材(A302B 鋼)溶接継手の中性子照射試験

概要

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The fast-neutron irradiation embrittlement of structural steels is an important problem in the design of the pressure vessel of a nuclear power reactor. Many studies have been made on the irradiation embrittlement of steels in foreign countries. In Japan, plans are also in progress on the irradiation tests of domestic structural steels, and some have already been carried out by Research Commitee of Irradiation Embrittlement of Steels, The Iron and Steel Institute of Japan, acting as the center's. The present paper shows a part of above studies, the results of irradiation tests with JRR-2 of JAERI and also of the postirradiation tests of domestic steels, namely ASTM A302B steel, aluminium-killed steel and their weld metals. The contents of this paper include (1) irradiation condition of JRR-2,(2) test rig for irradiation, (3) apparatus for the post-irradiation test, and (4) results of the irradiation embrittlement tests and tensile test. The results obtained are as follows : (1) The transition temperature shifts for brittle fracture at 6∿9n/(cm)^2 neutron doses were 67℃ on A302B base metal, 107℃ on its weld metal and 95℃ on its bond metal. (2) The change of tensile property due to neutron irradiation in aluminium-killed steel was larger than in A302B steel.
社団法人溶接学会の論文
1969-06-25