U-50Zr helical cruciform fuel performance analysis based on MOOSE framework

被引:1
|
作者
Hou, Yandong [1 ]
Dong, Yiliang [1 ]
Gao, Chuntian [1 ]
Chen, Bowen [1 ]
Zhang, Chao [1 ]
Li, Weichao [1 ]
Xiang, Yan [2 ]
机构
[1] Northeast Elect Power Univ, Sch Energy & Power Engn, Jilin, Peoples R China
[2] Royal Inst Technol KTH, Stockholm, Sweden
关键词
Helical cruciform fuel; Performance analysis; MOOSE-based Application; Reactivity-initiated accident; METALLIC FUEL; DELTA-UZR2; ZIRCONIUM; BEHAVIOR;
D O I
10.1016/j.anucene.2024.110529
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Helical Cruciform Fuel (HCF) represents a groundbreaking innovation that merges unique geometric structure with advanced metallic alloy materials. Due to the heat transfer optimization resulting from its distinctive geometric structure, HCF demonstrates the potential to achieve higher power output. Moreover, the utilization of U-Zr metal fuel in HCF contributes to enhancing the accident tolerance of the fuel system. Fuel performance analysis encompasses a series of intricate physical processes. To effectively model and simulate the 3D multiphysics coupling of these processes, advanced computational tool and software platform MOOSE framework is essential. In this work, thermo-mechanical capability for analysis of HCF was conducted in MOOSE-based fuel performance code PHOENIX. The operation of high burnup HCF behavior and reactivity-initiated accident (RIA) conditions are simulated. As the irradiation and burnup processes persist, the distribution of stress within the fuel tends towards a state of uniformity, with the stress concentration within the cladding occurring predominantly at the concave arc position. During RIA, the central height position of fuel stress exhibits a sharp increase and significant stress drop at the concave arc position of cladding, rendering it incapable of supporting the fuel. Furthermore, the cladding at various heights exhibits distinct mechanical behaviors, which can be categorized into three regions: a region relatively unaffected by the accident, a transition region, and a plastic deformation region.
引用
收藏
页数:19
相关论文
共 50 条
  • [31] Atomistic calculations of the surface energy as a function of composition and temperature in γ U-Zr to inform fuel performance modeling
    Beeler, Benjamin
    Casagranda, Albert
    Aagesen, Larry
    Zhang, Yongfeng
    Novascone, Stephen
    JOURNAL OF NUCLEAR MATERIALS, 2020, 540
  • [32] EFFECT OF Zr DIFFUSION BARRIER PROPERTIES ON THE IRRADIATION PERFORMANCE OF U-10MO MONOLITHIC FUEL PLATE
    Mohamed, Walid
    Ozaltun, Hakan
    Roh, Hee Seok
    PROCEEDINGS OF THE ASME POWER CONFERENCE, 2019, 2019,
  • [33] Multidimensional multiphysics simulations of the supercritical water-cooled fuel rod behaviors based on a new fuel performance code developed on the MOOSE platform
    Liu, Zhouyu
    Xu, Xiaobei
    Wu, Hongchun
    Cao, Liangzhi
    NUCLEAR ENGINEERING AND DESIGN, 2021, 375
  • [34] Analysis of Composition, Density, and Thermal Properties of U-Zr-Nb Alloy Powder for Nuclear Fuel
    Masrukan
    Yanlinastuti
    Alhasa, M. H.
    Sasongko, Arif
    SYMPOSIUM OF EMERGING NUCLEAR TECHNOLOGY AND ENGINEERING NOVELTY (SENTEN 2018), 2019, 1198
  • [35] Dissolution behavior of (U,Zr)O2-based simulated fuel debris in nitric acid
    Ikeuchi, Hirotomo
    Ishihara, Miho
    Yano, Kimihiko
    Kaji, Naoya
    Nakajima, Yasuo
    Washiya, Tadahiro
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2014, 51 (7-8) : 996 - 1005
  • [36] Multi-physics coupling analysis of test heat pipe reactor KRUSTY based on MOOSE framework
    Chen, Hongli
    Wang, Weixiang
    Wu, Aoguang
    Zhang, Kefan
    Pan, Rui
    Duan, Wenshun
    Yang, Guangliang
    Qin, Chong
    Luo, Xiao
    NUCLEAR ENGINEERING AND DESIGN, 2023, 414
  • [37] A Framework For The Performance Analysis Of Component Based Systems
    Bharathi, B.
    2015 INTERNATIONAL CONFERENCED ON CIRCUITS, POWER AND COMPUTING TECHNOLOGIES (ICCPCT-2015), 2015,
  • [38] Development of PRIME for irradiation performance analysis of U-Mo/Al dispersion fuel
    Jeong, Gwan Yoon
    Kim, Yeon Soo
    Jeong, Yong Jin
    Park, Jong Man
    Sohn, Dong-Seong
    JOURNAL OF NUCLEAR MATERIALS, 2018, 502 : 331 - 348
  • [39] An analysis framework for event-based sensor performance
    Cox, Joseph
    Ashok, Amit
    Morley, Nicholas
    UNCONVENTIONAL IMAGING AND ADAPTIVE OPTICS 2020, 2020, 11508
  • [40] TH-U METALLIC FUEL - LMFBR POTENTIAL BASED ON EBR-II DRIVER-FUEL PERFORMANCE
    SEIDEL, BR
    EINZIGER, RE
    WALTER, CM
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 27 (NOV): : 282 - 283