Material data acquisition activities to develop the material strength standard for sodium-cooled fast reactors

ナトリウム冷却高速炉の材料強度基準策定に向けた材料データ取得活動

豊田 晃大 ; 鬼澤 高志  ; 若井 隆純 ; 橋立 竜太 ; 加藤 章一 

Toyota, Kodai; Onizawa, Takashi; Wakai, Takashi; Hashidate, Ryuta; Kato, Shoichi

Adopting the 60-year design is regarded as one of the most effective means for the practical realization of Sodium-cooled Fast Reactor (SFR), which improves the economic efficiency and reduces the radioactive waste of SFR. In addition, since the happening of the severe accident (SA) at the Fukushima Daiichi Nuclear Power Plant, the structural integrity evaluation of SA has been emphasized on SFR as well. As for the practical realization of SFR, it is indispensable to improve materials strength standards such as the extremely high temperature material properties which is required for the application of structural integrity evaluation during the happening of SA. In order to make it possible to evaluate the structural integrity during 60-year design and SA, JAEA is working on the sophistication of the material strength standards. Moreover, material strength tests such as high temperature tensile tests, creep tests and fatigue tests are conducted systematically. In the paper, the overall picture of material testing that we have acquired or plan to acquire in order to establish the JSME standard will be reported.