Mechanical Properties of BC-A6N01SS-T1 for Basket Material of Transport and Storage Cask

概要

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BC-A6N01SS-T1 is an aluminum alloy with boron carbide particles uniformly dispersed in it. In order to apply this material to basket of spent nuclear fuel cask, registration to the “Rules on Transport / Storage Packagings for Spent Nuclear Fuel(JSME S FA1-2007)” is required. After the designated material testings required for the registration, this article exclusively describes effects of thermal aging and irradiation on mechanical properties of the basket material, which are especially important factors in long-term reliability as a basket material. Consequently, allowable design stress has been determined by considering reduction in strength during thermal aging based on results of accelerated aging test. On the other hand, it was found that irradiation level assumed for the basket material for storage of sixty years did not significantly affect tensile properties of BC-A6N01SS-T1.