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Two steps forward for U.K. advanced nuclear
This week, two significant announcements have emerged from the United Kingdom’s advanced reactor sector.
On June 14, Rolls-Royce, the United Kingdom National Nuclear Laboratory, and the Japan Atomic Energy Agency announced that they had signed two trilateral memorandums of cooperation to collaborate on “advanced modular reactor (AMR) technology, specifically high-temperature gas-cooled reactors (HTGR), and the coated particle fuel these reactors will use.”
Separately, on June 16, Bellevue, Wash.–based TerraPower announced that its Natrium reactor design has been formally submitted for U.K. regulatory review. The company also announced the formation of a new subsidiary, TerraPower UK Ltd.
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.