Criticality safety analysis for eccentric loading of fuel assemblies in spent nuclear fuel cask

被引:0
|
作者
Cho, Seok Geun [1 ]
Il Cha, Keon [1 ]
Cha, Kyoon Ho [1 ]
机构
[1] Sejong Univ, Nucl Engn Dept, 209 Neungdong Ro, Seoul 143747, South Korea
关键词
Criticality safety analysis; Spent nuclear fuel cask; Random displacement; Eccentric loading; Reactivity; UNCERTAINTY ANALYSIS;
D O I
10.1016/j.net.2024.09.024
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
Eccentric fuel loading is one of the studies performed in a spent nuclear fuel criticality safety analysis. Several studies have been performed to investigate the effect of increasing reactivity on eccentric loading and random displacement in spent nuclear fuel pools; However, studies within spent nuclear fuel casks have not been performed. Therefore, this study investigates the effects of eccentric loading and random displacement of fuel assemblies on the reactivity in the spent nuclear fuel cask. The spent nuclear fuel cask and PLUS7 fuel are modeled using the MCNP code to investigate these effects. The result indicates that in eccentric cases, the k-effective values exceed those observed in the normal case. Also, several random displacement cases show k-effective values that exceed the normal case. These results differ from previous studies on eccentric loading in the spent fuel pool. It supports the necessity of considering both eccentric loading and random displacement in the criticality safety analysis in spent nuclear fuel cask. The increase in reactivity due to eccentric loading and random displacement of fuel assemblies within casks might be considered in criticality safety analysis and regarded as an uncertainty.
引用
收藏
页数:8
相关论文
共 50 条
  • [1] The effect of eccentric loading in spent fuel pool criticality safety analyses
    Metwally, Walid A.
    Alawad, Abdulrahman S.
    ANNALS OF NUCLEAR ENERGY, 2018, 114 : 407 - 412
  • [2] Radiation shielding analysis and criticality safety calculation for spent fuel transportation cask
    Chen, Xiaosong
    Yeoh, Eing Yee
    Zhen, Gang
    Luo, Zhen
    JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, SNA + MC 2024, 2024, 302
  • [3] Optimizing spent nuclear fuel cask loading for VVER-440 fuel
    Lovecky, M.
    Zavorka, J.
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (12) : 5048 - 5054
  • [4] Shielding calculation and criticality safety analysis of spent fuel transportation cask in research reactors
    Mohammadi, A.
    Hassanzadeh, M.
    Gharib, M.
    APPLIED RADIATION AND ISOTOPES, 2016, 108 : 129 - 132
  • [5] Sensitivity analysis of parameters important to nuclear criticality safety of Castor X/28F spent nuclear fuel cask
    Leotlela, Mosebetsi. J.
    Malgas, Isaac
    Taviv, Eugene
    KERNTECHNIK, 2015, 80 (05) : 485 - 493
  • [6] Basket criticality design of a dual purpose cask for VVER 1000 spent fuel assemblies
    Rezaeian, M.
    Kamali, J.
    KERNTECHNIK, 2016, 81 (06) : 640 - 646
  • [7] Dose rates for various loading patterns of spent fuel assemblies in a dry cask
    Jenquin, U
    PROCEEDINGS OF THE TOPICAL MEETING ON RADIATION PROTECTION FOR OUR NATIONAL PRIORITIES: MEDICINE, THE ENVIRONMENT, AND THE LEGACY, 2000, : 546 - 551
  • [8] Nuclear criticality safety analysis in dissolving process of spent fuel reprocessing
    Liu, Ying-Yu
    Luo, Zhi-Wen
    Liu, Zhen-Hua
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (08): : 1375 - 1379
  • [9] Analytical Sensitivity Analysis of a Spent Nuclear Fuel Cask
    Remedes, Tyler J.
    Ramsey, Scott D.
    Baciak, James E.
    JOURNAL OF VERIFICATION, VALIDATION AND UNCERTAINTY QUANTIFICATION, 2022, 7 (03):
  • [10] Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask
    Alrawash, Saed
    Boravy, Muth
    Yoo, Seung Uk
    Han, Hyuk
    Kim, Soon Young
    Park, Moon-ghu
    Park, Chang Je
    ANNALS OF NUCLEAR ENERGY, 2020, 144