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May 31–June 3, 2026
Denver, CO|Sheraton Denver
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NRC commissioners talk reforms, roles at Day 1 of RIC 2026
Even a last-minute cancelation from Department of Energy Secretary Chris Wright could not derail the optimism permeating day 1 of the Nuclear Regulatory Commission’s annual Regulatory Information Conference (RIC).
The optimistic theme came up several times during the morning plenary sessions that highlighted Tuesday’s agenda. The NRC commissioners who spoke said the optimism was a result of the “nuclear renaissance” they are encountering that feels different from past nuclear-related revivals that didn’t materialize.
P. Zhang (State Nuclear Power Technology R&D Center), H. J. Chang (State Nuclear Power Technology R&D Center/Tsinghua Univ),
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1142-1154
Liquid entrainment at the tee junction of hot leg to ADS-4 branch (fourth-stage Automatic Depressurization System) is a high priority safety related phenomenon in Westinghouse Advanced Passive pressurized water reactor (AP1000) and Chinese Advanced Passive pressurized water reactor (CAP1400). Previous studies are mainly carried out on reduced scale experimental test facilities. To offer a better understanding of the liquid entrainment phenomenon at tee junction and evaluate the applicability of entrainment models, a full scale test facility is designed and fabricated. The maximum air and water flowrates are 12kg/s and 150kg/s respectively. 16 onset of liquid entrainment tests and 80 entrainment rate tests are carried out on this test facility. Test data is compared with previous entrainment models. Significant differences are founded. This means the applicability of liquid entrainment models in safety analysis code is questionable. Based on the flow regime transition criterion in horizontal pipe, a new onset of liquid entrainment model is proposed. The agreement of the new model to test data is better than previous models.