Multiphysics Modeling of Thorium-Based Fuel Performance With Cr-Coated SiC/SiC Composite Under Normal and Accident Conditions

被引:4
作者
Liu, Shengyu [1 ]
Liu, Rong [1 ]
Qiu, Chengjie [1 ]
Zhou, Wenzhong [2 ,3 ]
机构
[1] South China Univ Technol, Sch Elect Power, Guangzhou, Peoples R China
[2] City Univ Hong Kong, Dept Mech Engn, Kowloon, Hong Kong, Peoples R China
[3] City Univ Hong Kong, Ctr Adv Nucl Safety & Sustainable Dev, Kowloon, Hong Kong, Peoples R China
来源
FRONTIERS IN ENERGY RESEARCH | 2021年 / 9卷
基金
中国国家自然科学基金;
关键词
thorium-based fuel; CAMPUS; fuel performance; Cr-coated SiC; SiC composite cladding; accident condition; SILICON-CARBIDE; WATER REACTOR; CHROMIUM;
D O I
10.3389/fenrg.2021.677606
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
Using the finite element multiphysics modeling method, the performance of the thorium-based fuel with Cr-coated SiC/SiC composite cladding under both normal operating and accident conditions was investigated in this work. First, the material properties of SiC/SiC composite and chromium were reviewed. Then, the implemented model was simulated, and the results were compared with those of the FRAPTRAN code to verify the correctness of the model used in this work. Finally, the fuel performance of the Th0.923U0.077O2 fuel, Th0.923Pu0.077O2 fuel, and UO2 fuel combined with the Cr-coated SiC/SiC composite cladding and Zircaloy cladding, respectively, was investigated and compared under both normal operating and accident conditions. Compared with the UO2 fuel, the Th0.923U0.077O2 and Th0.923Pu0.077O2 fuels were found to increase the fuel centerline temperature under both normal operating and reactivity-initiated accident (RIA) conditions, but decrease the fuel centerline temperature under loss-of-coolant accident (LOCA) condition. Moreover, compared to the UO2 fuel with the Zircaloy cladding, thorium-based fuels with Cr-coated SiC/SiC composite cladding were found to show better mechanical performance such as delaying the failure time by about 3 s of the Cr-coated SiC/SiC composite cladding under LOCA condition, and reducing the plenum pressure by about 0.4 MPa at the peak value in the fuel rod and the hoop strain of the cladding by about 16% under RIA condition.
引用
收藏
页数:14
相关论文
共 35 条
  • [1] Analysis of Key Safety Metrics of Thorium Utilization in LWRs
    Ade, Brian
    Worrall, Andrew
    Powers, Jeffrey
    Bowman, Steve
    [J]. NUCLEAR TECHNOLOGY, 2016, 194 (02) : 162 - 177
  • [2] Armstrong P.E., 1964, T AIME, V230
  • [3] Thermo-mechanical analysis of LWR SiC/SiC composite cladding
    Ben-Belgacem, M.
    Richet, V.
    Terrani, K. A.
    Katoh, Y.
    Snead, L. L.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 447 (1-3) : 125 - 142
  • [4] KINETICS AND MECHANISMS OF HIGH-TEMPERATURE CREEP IN SILICON-CARBIDE .2. CHEMICALLY VAPOR-DEPOSITED
    CARTER, CH
    DAVIS, RF
    BENTLEY, J
    [J]. JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1984, 67 (11) : 732 - 740
  • [5] Characterization of SiC-SiC composites for accident tolerant fuel cladding
    Deck, C. P.
    Jacobsen, G. M.
    Sheeder, J.
    Gutierrez, O.
    Zhang, J.
    Stone, J.
    Khalifa, H. E.
    Back, C. A.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2015, 466 : 667 - 681
  • [6] The TRANSURANUS mechanical model for large strain analysis
    Di Marcello, Valentino
    Schubert, Arndt
    van de Laar, Jacques
    Van Uffelen, Paul
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2014, 276 : 19 - 29
  • [7] Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactor
    Duz, Mehtap
    [J]. FRONTIERS IN ENERGY RESEARCH, 2021, 9
  • [8] POWDER METALLURGICAL CHROMIUM
    ECK, R
    MARTINZ, HP
    SAKAKI, T
    KATO, M
    [J]. MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 1989, 120 : 307 - 312
  • [9] Frazer D., 2015, COMPOSITE MAT A
  • [10] Minimization of the fission product waste by using thorium based fuel instead of uranium dioxide
    Galahom, A. Abdelghafar
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2017, 314 : 165 - 172