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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
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.