A new structure design to extend graphite assembly lifespan in small modular molten salt reactors

被引:11
|
作者
Wang, Yong [1 ,2 ]
Guo, Wei [1 ,2 ]
Zhu, Gui-Feng [2 ]
Dai, Ye [2 ]
Zhong, Yu [1 ]
Zou, Yang [1 ,2 ]
Chen, Jin-Gen [1 ,2 ]
Cai, Xiang-Zhou [1 ,2 ]
机构
[1] Univ Chinese Acad Sci, Beijing, Peoples R China
[2] Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China
基金
中国国家自然科学基金;
关键词
assembly structure; dimensional change; graphite lifespan; molten salt reactor; CORE; OPTIMIZATION; BEHAVIOR;
D O I
10.1002/er.6361
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
Dimensional change of the graphite assemblies due to irradiation is a key factor in limiting the service lifespan of the reactor core in small modular molten salt reactors. The graphite assembly structure, determining the fast neutron flux distribution and temperature distribution, has a notable impact on its dimensional change and hence its lifespan. In this article, we put forward an innovative solid hexagonal prism assembly (HPA) surrounded by fuel salt to prolong the lifespan of the graphite assemblies and compare it with the traditional hexagonal round channel assembly (RCA) with fuel salt flowing through its central round channel. Under the single-cell model, the calculation results prove that the neutron flux distribution and temperature distribution in the HPA are more uniform than those in the RCA. The HPA deforms more slowly than the RCA under the same operating conditions. The lifespan of the RCA, defined as when it expands back to its original size, is 7.5 years under the 100 MW/m(3) power density of fuel salt, while the lifespan of the proposed HPA is 8.4 years. The HPAs also allow a further expansion in the radial direction due to its noncontact arrangement in the core. It will take 14.9 years for the HPA assemblies to contact each other, which displays a significant improvement in lifespan.
引用
收藏
页码:12247 / 12257
页数:11
相关论文
共 50 条
  • [31] Design considerations of the supercritical carbon dioxide Brayton cycle of small modular molten salt reactor for ship propulsion
    Lee, Wonkoo
    Yoo, Sunghyun
    Park, Dong Kyou
    Lee, Kwon-Yeong
    PROGRESS IN NUCLEAR ENERGY, 2023, 163
  • [32] Direct characterization of ion implanted nanopore pyrolytic graphite coatings for molten salt nuclear reactors
    Zhang, Heyao
    Lei, Qiantao
    Song, Jinliang
    Liu, Min
    Zhang, Can
    Gao, Yantao
    Zhang, Wenting
    Xia, Huihao
    Liu, Xiangdong
    RSC ADVANCES, 2018, 8 (59): : 33927 - 33938
  • [33] Characterization of the effect of He plus irradiation on nanoporous-isotropic graphite for molten salt reactors
    Zhang, Heyao
    He, Zhao
    Song, Jinliang
    Liu, Zhanjun
    Tang, Zhongfeng
    Liu, Min
    Wang, Yong
    Liu, Xiangdong
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (06) : 1243 - 1251
  • [34] Irradiation Characteristics of Non-Impregnated Micropore Graphite for Use in Molten Salt Nuclear Reactors
    Lian, Pengfei
    Li, Pengda
    Huang, Hefei
    Song, Jinliang
    Tang, Zhongfeng
    Liu, Zhanjun
    C-JOURNAL OF CARBON RESEARCH, 2024, 10 (02):
  • [35] GRAPHITE AND XENON BEHAVIOR AND THEIR INFLUENCE ON MOLTEN-SALT REACTOR DESIGN
    SCOTT, D
    EATHERLY, WP
    NUCLEAR APPLICATIONS AND TECHNOLOGY, 1970, 8 (02): : 179 - &
  • [36] INSERVICE TESTING PROGRAM IMPROVEMENTS FOR NEW REACTORS SMALL MODULAR REACTORS (SMRs)
    Lippy, Ronald C.
    PROCEEDINGS OF THE ASME SMALL MODULAR REACTORS SYMPOSIUM, 2014, 2014,
  • [37] Neutrino-detector design for safeguarding small modular reactors
    Houston, Emma
    Bogetic, Sandra
    Akindele, Oluwatomi
    Bergevin, Marc
    Bernstein, Adam
    Dazley, Steven
    PHYSICAL REVIEW APPLIED, 2024, 21 (06):
  • [38] INSTRUMENTATION AND CONTROLS DESIGN AND MAINTENANCE STRATEGY FOR SMALL MODULAR REACTORS
    Hashemian, Alex H.
    Hashemian, Hash M.
    Thomasson, Tommy C., III
    Kapernick, Jeffrey R.
    PROCEEDINGS OF THE ASME SMALL MODULAR REACTORS SYMPOSIUM, 2014, 2014,
  • [39] DESIGN AND NON-PROLIFERATION VIABILITY OF SMALL MODULAR REACTORS
    Koreshi, Zafar Ullah
    PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 1, 2018,
  • [40] ATWS accident analysis of rod withdrawal in small modular molten salt reactor
    Xu T.
    Zou Y.
    Xu B.
    Zhu G.
    Sun Q.
    He Jishu/Nuclear Techniques, 2022, 45 (05):