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Neutron damage of austenitic stainless steels as candidate materials of blanket-components in a fusion reactor

M.P. Tanaka, M. Suzuki, S. Hamada, A. Hishinuma, T. Kondo1989年Fusion Engineering and DesignIF 1.7出版社

Base materials of type 316 and Ti-modified austenitic steel (JPCA) and weld-joints of these materials were irradiated in HFIR at 55 °C to fluences up to 1.12×1027 neutrons/m2 (> 0.1 MeV), which produced up to 56 dpa and 3630 appm He. Tensile tests at room temperature showed a large increase in strength properties and that the weld-joints are weaker than the base-materials. The ductility of all materials was reduced by irradiation. For the irradiated weld-joint, deformation and fracture occurred mainly in part of the weldment. This data shows that the benefit of a cold-worked material (which is high strength) could no longer be expected in the weld-joint. The increase in strength and work-hardening rate by MC-precipitates, with the addition of Ti and Nb to the filter metal, is necessary to improve the deformation behavior of the irradiated weld-joints in type 316 stainless steel and JPCA.

日本語訳

316型およびTi添加オーステナイト鋼(JPCA)を母材とする材料と、これらの材料の溶接継手をHFIRにおいて55°Cで1.12×10^27 neutrons/m^2(>0.1 MeV)まで照射し、これにより最大56 dpaおよび3630 appm Heを生成させた。室温引張試験の結果、強度特性は大幅に増加し、溶接継手は母材よりも弱いことが示された。全材料の延性は照射により低下した。照射済み溶接継手では、変形と破断は主に溶接金属部で生じた。このデータは、冷間加工材(高強度)の利点が溶接継手では期待できなくなることを示している。TiおよびNbを溶加金属に添加することによるMC析出物の増加と加工硬化率の向上が、316型ステンレス鋼およびJPCAの照射済み溶接継手の変形挙動を改善するために必要である。

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