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Oak Ridge focuses neutron scattering studies on TRISO fuels
Oak Ridge National Laboratory is reporting a development in TRISO fuel research that could help evaluate high-temperature gas reactor fuels. ORNL researchers used the Spallation Neutrons and Pressure Diffractometer at the lab’s Spallation Neutron Source to make neutron scattering measurements on TRISO fuel particles containing high-assay low-enriched uranium (HALEU).
Minsuk Seo
Nuclear Technology | Volume 207 | Number 12 | December 2021 | Pages 1902-1912
Technical Paper | doi.org/10.1080/00295450.2020.1860614
Articles are hosted by Taylor and Francis Online.
Ensuring the thermal stability of heat-generating nuclear waste glass canisters in interim storage and the thermal stability of bentonite in the deep geological repository are crucial to preserving the function of the waste form. Yet thermal stability might be challenged by further heated air conditions and excessive heat load in the waste form, such that the maximum temperature would be higher than the glass transition temperature undesirably. The finite element method was carried out for the n × n × 4 (n = 1, 3, 5) multicanister system for the sake of predicting the maximum temperatures of interim storage. The internal heat source amount and exiting air temperature of the system were varied to see different storage environments. The maximum heat load of a 15.8 kW/m3 canister was in a safe range (glass transition temperature of 500°C), whereas an 18.6 kW/m3 canister was not. There is a possibility to extend thermal stability to a system larger than n = 5 for 15.8 kW/m3 based on the converging maximum temperature trends. Besides, the maximum temperature of the canister and bentonite clay in a deep geological repository is potentially below the thermal criterion if the canister cools down for about 65 to 70 years.