Neutron Irradiation Effects on Thermal Shock Resistances and Fracture Mechanical Properties of Fuel Compacts for the HTTR

概要

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To simulate the nuclear fuel for the High Temperature Engineering Test Reactor (HTTR), a fuel compact model using SiC-kernel coated particles instead of UO_2-kernel coated particles was prepared under the same conditions as those for the real fuel compact. The mechanical and fracture mechanics properties were studied at room temperature. The thermal shock resistance and fracture toughness for thermal stresses of the fuel compact model were experimentally assessed by means of arc discharge heating applied at a central area of the disk specimens. These model specimens were then neutron irradiated in the Japan Material Testing Reactor (JMTR) for fluences up to 1.7×10^<21>n/cm^2 (E>29fJ) at 900℃±50℃. The effects of irradiation on a series of fracture mechanical properties were evaluated and compared with the cases of graphite IG-110 used as the core materials in the HTTR.fuel compactthermal shock resistancethermal shock fracture toughnessneutron irradiationHTTR
東北大学の論文
1994-09-16