APPLICABILITY OF HYDRIDE MATERIALS FOR RADIATION SHIELDING IN HELICAL REACTOR FFHR-D1

作者：Tanaka Teruya^*; Muta Hiroaki; Hishinuma Yoshimitsu; Tamura Hitoshi; Muroga Takeo; Sagara Akio

来源：Fusion Science and Technology, 2015, 68(3): 705-710.

DOI：10.13182/FST15-110

Performance and applicability of hydride shielding materials are investigated in the helical reactor FFHR-d1 design. Performance of ZrH2 and TiH2 in fast neutron shielding are close to that of WC, which is most effective among candidate materials, for both in-vessel and out-vessel use. The investigation confirms that neutron shielding performance of a two-layered terrific steel (FS)/ZrH2 or TiH2 shield is similar to that of a one-layered ZrH2 or TiH2 shield with the same total thickness. This shielding property is an important feature to maintain consistency with the structure design of FFHRd1. In attenuation of direct neutrons from the core plasma in a bending duct, the hydride duct walls show superior performance compared with FS + B4C and WC duct walls. While controls for temperature (at <300 degrees C) and hydrogen concentration in the coolant gas would be required particularly for in-vessel use, the lower weight densities and quick decay of contact dose rates compared with other candidate materials would be reasons to select these hydride shielding materials.

• 出版日期2015-10