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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).
Hongdong Zhen, Songtao Yin, Lei Zhang, Ningning Wang, Bo Xu, Haijun Wang
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 54-61
Technical Paper | doi.org/10.1080/00295450.2020.1739994
Articles are hosted by Taylor and Francis Online.
This paper aims to revise the critical flow criterion and flashing inception of the analytical critical flow model and to further explore the effect of upstream conditions on critical mass fluxes. The flashing inception of the model is considered to be affected by the Reynolds number and the Jakob number. Model predictions show strong similarities with test results compared with other models, with average errors of less than 10.1% for simulated slits and 15.8% for natural cracks. Upstream parameters of the liquid, such as the stagnation pressure, subcooling, and aspect ratio, directly influence the rate of depressurization, the thermodynamic nonequilibrium constant, and the friction pressure drop, respectively, which determine the critical mass flux. This research provides the theoretical basis for accurate assessment of critical crack, providing safeguards for monitoring nuclear reactor leaks.