ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
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.
Zhi’ao Huang, Huifang Miao, Huai-En Hsieh, Yifen Chen, Ning Li (Xiamen Univ), Chao Guo (China General Nuclear Power Research Inst Co. Ltd.)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 379-387
Recently, with the development and application of full-scope level 2 probabilistic safety assessment (PSA) method around the world, severe accident phenomena during shutdown and low power conditions have aroused extensive attention in nuclear industry. And the shutdown severe accident management guideline is claimed to be developed, and the verification of the entry condition is the first consideration in this procedure. Diverse parameters have been monitored to identify their applicability as the alternative shutdown severe accident management guideline (SSAMG) entry conditions based on SBO scenarios in this paper, also the maximum core temperature 1350 K is chosen as the indicator of core damage instead of traditional peak cladding temperature 1024 ? which is thought to be much conservative. The results explain the complex severe accident progression during mid-loop operation in different scenarios and several parameters (i.e. mole fraction of H2 in containment and the mass of noble gas in containment. et.al) are identified to be useful as alternative SSAMG entry conditions in certain scenario. What’s more, the hot leg (in the loop with pressurizer) pipe surface temperature is identified to be the most appropriate parameter to be used as alternative SSAMG when the traditional entry conditions (core exit temperature and the radioactivity in containment) are not available, since it has strong relationship with the maximum core temperature.