Characterization of LWRS Hybrid SiC-CMC-Zircaloy-4 Fuel Cladding after Gamma Irradiation

Rooyen, Isabella J van

Idaho National Laboratory

关键词: 22 General Studies Of Nuclear Reactors Light Water Reactor Sustainability Program;    Light Water Reactor Sustainability Program;   

DOI  :  10.2172/1055817
RP-ID  :  INL/EXT-12-27188
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1055817

美国|英语

来源: UNT Digital Library

【 摘 要 】

The purpose of the gamma irradiation tests conducted at the Idaho National Laboratory (INL) was to obtain a better understanding of chemical interactions and potential changes in microstructural properties of a mock-up hybrid nuclear fuel cladding rodlet design (unfueled) in a simulated PWR water environment under irradiation conditions. The hybrid fuel rodlet design is being investigated under the Light Water Reactor Sustainability (LWRS) program for further development and testing of one of the possible advanced LWR nuclear fuel cladding designs. The gamma irradiation tests were performed in preparation for neutron irradiation tests planned for a silicon carbide (SiC) ceramic matrix composite (CMC) zircaloy-4 (Zr-4) hybrid fuel rodlet that may be tested in the INL Advanced Test Reactor (ATR) if the design is selected for further development and testing