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Volume 43 Issue 6
Dec.  2022
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Wang Chengcai, Xu Hui, Zhang Xueyong, Yang Zhaodong, Yan Guizhen, Wang Yanhui, Yang Zhongwei. Design Optimization of Retention Coil for 2 MWt Liquid Fuel Thorium-based Molten Salt Experimental Reactor[J]. Nuclear Power Engineering, 2022, 43(6): 133-138. doi: 10.13832/j.jnpe.2022.06.0133
Citation: Wang Chengcai, Xu Hui, Zhang Xueyong, Yang Zhaodong, Yan Guizhen, Wang Yanhui, Yang Zhongwei. Design Optimization of Retention Coil for 2 MWt Liquid Fuel Thorium-based Molten Salt Experimental Reactor[J]. Nuclear Power Engineering, 2022, 43(6): 133-138. doi: 10.13832/j.jnpe.2022.06.0133

Design Optimization of Retention Coil for 2 MWt Liquid Fuel Thorium-based Molten Salt Experimental Reactor

doi: 10.13832/j.jnpe.2022.06.0133
  • Received Date: 2021-12-24
  • Rev Recd Date: 2022-02-23
  • Publish Date: 2022-12-14
  • The retention coil of liquid fuel thorium-based molten salt experimental reactor is an important nuclear safety equipment in the tail gas treatment system of molten salt reactor, which provides a closed environment for the decay of short-lived nuclides in the tail gas, removes the decay heat at the same time, and reduces the temperature of the iodine adsorption bed and the activated carbon adsorption bed downstream it. This paper introduces the problems existing in the original design scheme of the retention coil of the 2 MWt liquid fuel thorium-based molten salt experimental reactor provided by the owner and the new design scheme after structural optimization. The optimized design scheme of retention coil has the advantages of good heat dissipation, few leakage points (few welds), easy welding, easy inspection, monitoring and maintenance, less materials, etc., and has good reliability and economy.

     

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  • [1]
    FORSBERG C W, TERRANI K A, SNEAD L L, et al. Fluoride-salt-cooled high-temperature reactor (FHR) with silicon-carbide-matrix coated-particle fuel[Z]. Oak Ridge: Oak Ridge National Lab., 2012.
    [2]
    江绵恒,徐洪杰,戴志敏. 未来先进核裂变能−TMSR核能系统[J]. 中国科学院院刊,2012, 27(3): 366-374. doi: 10.3969/j.issn.1000-3045.2012.03.016
    [3]
    中华人民共和国国家质量监督检验检疫总局, 中国国家标准化管理委员会. 钢制对焊管件 类型与参数: GB/T 12459−2017[S]. 北京: 中国标准出版社, 2017: 7
    [4]
    The American Society of Mechanical Engineers. Rules for construction of nuclear facility components: ASME BPV code section III division 1 subsection ND class 3 components[S]. New York: The American Society of Mechanical Engineers, 2019: 37-41
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