Development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR

被引:0
|
作者
Higashi, Yuma [1 ]
Murakami, Nozomu [1 ]
Yodo, Tadakatsu [1 ]
Yamamoto, Teruhisa [2 ]
机构
[1] Mitsubishi Heavy Ind Co Ltd, Hyogo Ku, 1-1 Wadasaki Cho 1 Chome, Kobe, Hyogo 6528585, Japan
[2] Mitsubishi Nucl Fuel Co Ltd, 622-1 Funaishikawa, Tokai, Ibaraki 3191197, Japan
来源
MECHANICAL ENGINEERING JOURNAL | 2021年 / 8卷 / 04期
关键词
Pressurized water reactor (PWR); Fuel; Cladding; Pellet cladding mechanical interaction (PCMI); Fission gas; Swelling;
D O I
10.1299/mej.20-00541
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
Pellet-Cladding Mechanical Interaction (PCMI) failure is one of the failure mode which must be evaluated in nuclear fuel safety. PCMI is caused by mechanical load to the cladding due to fuel pellet expansion. Under high fuel burnup condition, the fuel cladding may become degraded by embrittlement under neutron-induced irradiation and hydrogen accumulation due to the waterside corrosion. In order to consider the further deterioration of the material with higher burnup, evaluation using mechanical indicators, e.g. strain and stress, might be required. As fuel burnup proceeds, cracks occur in the pellet due to an internal temperature gradient, which induces the fuel pellet relocation, and fission gas may be accumulated in the pellet and the gap between pellet and cladding. Cracks and fission gas may cause more deformation of the pellet under the power excursion than in low burnup condition. In this study, a transient model is developed, which can mechanistically evaluate the PCMI behavior, in particular, for fuel rods under higher burnup condition. The model is incorporated in a fuel behavior analysis code and verified by benchmarks with other similar codes. The PCMI predictability of this code is validated using the experimental test data.
引用
收藏
页数:8
相关论文
共 50 条
  • [1] DEVELOPMENT OF THE FUEL BEHAVIOR ANALYSIS CODE FOR MECHANICAL FUEL CLADDING FAILURE DURING REACTIVITY INSERTION EVENT IN PWR
    Higashi, Yuma
    Murakarmi, Nozomu
    Yodo, Tadakatsu
    Yamamoto, Teruhisa
    PROCEEDINGS OF THE 2020 INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE2020), VOL 1, 2020,
  • [2] THERMAL BEHAVIOR ANALYSIS OF PWR FUEL DURING RIA AT VARIOUS FUEL BURNUPS USING MODIFIED THEATRe CODE
    Nawaz, Amjad
    Hidekazu, Yoshikawa
    Yang, Ming
    Hussain, Anwar
    NUCLEAR TECHNOLOGY & RADIATION PROTECTION, 2016, 31 (04): : 307 - 317
  • [3] Development of Computational Methods to Describe The Mechanical Behavior of PWR Fuel Assemblies
    Wanninger, Andreas
    Seidl, Marcus
    Macian-Juan, Rafael
    ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2016, 61 (10): : 612 - 616
  • [4] Brittle failure analysis and modeling of high-burnup PWR fuel cladding alloys
    Simbruner, Kai
    Billone, Michael C.
    Zencker, Uwe
    Liu, Yung Y.
    Voelzke, Holger
    KERNTECHNIK, 2025, 90 (01) : 44 - 52
  • [5] POTENTIAL FOR FUEL MELTING AND CLADDING THERMAL FAILURE DURING A PCM EVENT IN LWRS
    ELGENK, MS
    CROUCHER, DW
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 508 - 510
  • [6] ALCYONE: the fuel performance code of the PLEIADES platform dedicated to PWR fuel rods behavior
    Introini, C.
    Ramiere, I.
    Sercombe, J.
    Michel, B.
    Helfer, T.
    Fauque, J.
    ANNALS OF NUCLEAR ENERGY, 2024, 207
  • [7] Microstructural understanding on the fouling behavior of crud on PWR fuel cladding surface
    Yang, Jianqiao
    Wang, Jiahuan
    Liu, Junkai
    Wang, Shuzhong
    Yun, Di
    Ma, Dayan
    Li, Yanhui
    Xu, Donghai
    JOURNAL OF NUCLEAR MATERIALS, 2023, 582
  • [8] COMPUTATIONAL MODELS FOR CLADDING MECHANICAL-BEHAVIOR OF PWR FUEL-ELEMENT UNDER LOCA CONDITIONS
    BUJAN, A
    ADAMIK, V
    JADERNA ENERGIE, 1984, 30 (10): : 351 - 358
  • [9] ABAQUS analysis of the SiC cladding fuel rod behavior under PWR normal operation conditions
    Li, Wei
    Shirvan, Koroush
    JOURNAL OF NUCLEAR MATERIALS, 2019, 515 : 14 - 27
  • [10] Thermal-hydraulics analysis during fuel element failure in an operating PWR
    Chen, Wenzhen
    Yang, Lei
    Xiao, Hongguang
    Chen, Zhiyun
    PROGRESS IN NUCLEAR ENERGY, 2015, 85 : 694 - 700