Abstract
An improved understanding of the diffusion of select fission product systems in materials representative of tristructural-isotopic (TRISO) coated particle fuel are being sought to improve the safety and efficiency of high temperature gas-cooled reactors. Novel diffusion couple samples have been produced to explore diffusion under neutron irradiation and at temperatures representative of safety testing conditions. An update on the status of the neutron irradiation study and high temperature thermal testing is discussed which build upon prior reporting
Original language | English |
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Place of Publication | United States |
DOIs | |
State | Published - 2018 |
Keywords
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS