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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
IAEA again raises global nuclear power projections
Noting recent momentum behind nuclear power, the International Atomic Energy Agency has revised up its projections for the expansion of nuclear power, estimating that global nuclear operational capacity will more than double by 2050—reaching 2.6 times the 2024 level—with small modular reactors expected to play a pivotal role in this high-case scenario.
IAEA director general Rafael Mariano Grossi announced the new projections, contained in the annual report Energy, Electricity, and Nuclear Power Estimates for the Period up to 2050 at the 69th IAEA General Conference in Vienna.
In the report’s high-case scenario, nuclear electrical generating capacity is projected to increase to from 377 GW at the end of 2024 to 992 GW by 2050. In a low-case scenario, capacity rises 50 percent, compared with 2024, to 561 GW. SMRs are projected to account for 24 percent of the new capacity added in the high case and for 5 percent in the low case.
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.
