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
  • [21] Development of Fuel Performance Analysis Code for Liquid Metal Cooled Fast Reactor Based on MOOSE Platform
    Shao S.
    Liu Z.
    Xu X.
    Zong Y.
    Cao L.
    Wu H.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2024, 58 (03): : 539 - 548
  • [22] Performance of FCCI barrier foils for U-Zr-X metallic fuel
    Ryu, Ho Jin
    Lee, Byoung Oon
    Oh, Seok Jin
    Kim, Jun Hwan
    Lee, Chan Bock
    JOURNAL OF NUCLEAR MATERIALS, 2009, 392 (02) : 206 - 212
  • [23] Research on U-Zr-based Metallic Fuel Additives and Performance Improvement for Fuel-Cladding Chemical Interaction and Phase Optimization
    Zhuo W.
    Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 : 158 - 162
  • [24] Preliminary Thermal-Mechanical coupled modeling of U-10Mo helical cruciform fuel rods under the unirradiated and irradiated conditions
    Cai, Mengke
    Cong, Tenglong
    Xiao, Yao
    Gu, Hanyang
    ANNALS OF NUCLEAR ENERGY, 2023, 181
  • [25] Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code BISON
    Galloway, J.
    Unal, C.
    Carlson, N.
    Porter, D.
    Hayes, S.
    NUCLEAR ENGINEERING AND DESIGN, 2015, 286 : 1 - 17
  • [26] Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment
    Greenquist, Ian
    Cunningham, Kaylee M.
    Hu, Jianwei
    Powers, Jeffrey J.
    Crawford, Douglas C.
    JOURNAL OF NUCLEAR MATERIALS, 2021, 553
  • [27] Numerical analysis of Neutronics and Thermal-Hydraulic properties of Helical-Cruciform fuel assembly with Helium-Xenon gas mixture
    Ju, Wenxuan
    Ning, Kewei
    Xie, Lin
    Zhao, Fulong
    Tan, Sichao
    NUCLEAR ENGINEERING AND DESIGN, 2024, 430
  • [28] Preparation, analysis and irradiation of hydrided U-Th-Zr alloy samples for a new fuel
    Yamamoto, T
    Suwarno, H
    Ono, F
    Kayano, H
    Yamawaki, M
    JOURNAL OF ALLOYS AND COMPOUNDS, 1998, 271 : 702 - 706
  • [29] Performance Analysis of Agent Based Framework
    Sindhuja, K.
    Monisha, A., V
    Padmavathi, S.
    GRAPH ALGORITHMS, HIGH PERFORMANCE IMPLEMENTATIONS AND ITS APPLICATIONS (ICGHIA 2014), 2015, 47 : 37 - 44
  • [30] PERFORMANCE OF ADVANCED U-PU-ZR ALLOY FUEL ELEMENTS UNDER FAST-REACTOR CONDITIONS
    BECK, WN
    BROWN, FL
    KOPROWSK.BJ
    KITTEL, JH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1967, 10 (01): : 106 - &