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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).
John B. Case, Harris R. Greenberg, Bruce E. Kirstein
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 62-73
Technical Paper | doi.org/10.1080/00295450.2020.1747837
Articles are hosted by Taylor and Francis Online.
Analytical solutions for temperatures in an infinite region bounded internally by a cylinder have proved to be useful for thermal analysis of heat-producing nuclear waste disposal scenarios where the thermal design criteria are peak temperatures. The practicality of an analytical solution for the temperature of the host rock used in forced-ventilation thermal analyses has been illustrated by a computational time of a few seconds. Prior to the use of an analytical temperature solution for the host rock, the computation time was on the order of hours. However, the published analytical temperature solution for the infinite region bounded internally by a cylinder with constant heat flux applied at the cylinder wall does not satisfy the boundary condition. This temperature solution is shown to be correct herein with respect to temperature predictions derived from a solution that does satisfy the boundary condition.