Experimental studies on safety of dry cask storage technology of spent fuel - Allowable temperature of cladding and integrity of cask under accidents

被引:3
|
作者
Saegusa, T [1 ]
Mayuzumi, M [1 ]
Ito, C [1 ]
Shirai, K [1 ]
机构
[1] CENT RES INST ELECT POWER IND, KOMAE RES LAB, KOMAE, TOKYO 201, JAPAN
关键词
spent fuel; spent fuel casks; material testing; cask storage; cladding creep; cask drop; drop accident; cask toppling; earthquake;
D O I
10.3327/jnst.33.250
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
The purpose of this report is to publish results on a comprehensive review of research subjects on safety of the dry cask storage and to publish a part of the research results. (1) A method to calculate the maximum allowable temperature of fuel cladding tvas proposed, based on experiments using irradiated and non-irradiated Zircaloy tube specimens, in order to prevent excessive creep deformation of fuel cladding in dry cask. (2) Under an accidental test of ''Cask drop onto concrete floor'', the cask integrity was demonstrated using full-scale casks (100-t class). (3) Under an accidental test of ''Building collapse and drop of heavy objects onto cask'', the cask integrity was demonstrated using a full-scale cask (100-t class). (4) As to possibility of cask toppling by earthquake, analytical and experimental results using a scale model cask shan ed that the cask will not be toppled by earthquake.
引用
收藏
页码:250 / 258
页数:9
相关论文
共 50 条
  • [41] A METHOD TO EVALUATE THE MAXIMUM ALLOWABLE TEMPERATURE OF SPENT FUEL IN DRY STORAGE DURING A POSTULATED ACCIDENT
    MAYUZUMI, M
    ONCHI, T
    NUCLEAR TECHNOLOGY, 1991, 93 (03) : 382 - 388
  • [42] Maximum allowable temperatures of WWER-1000 spent fuel under dry storage conditions
    Kadarmetov, IM
    Bibilashvili, YK
    Medvedev, AV
    Sokolov, FF
    INTERNATIONAL CONFERENCE ON STORAGE IN NUCLEAR FUEL CYCLE, 1996, 1996 (07): : 227 - 233
  • [43] Numerical simulation of coupling heat transfer and thermal stress for spent fuel dry storage cask with different power distribution and tilt angles
    Ji, Wei-Hao
    Cheng, Jian-Jie
    Tao, Han-Zhong
    Li, Wei
    NUCLEAR SCIENCE AND TECHNIQUES, 2023, 34 (02)
  • [44] A risk-informed assessment tool to support review of license amendment requests for spent nuclear fuel dry cask storage systems
    Eidelpes, Elmar
    Biersdorf, John M.
    NUCLEAR ENGINEERING AND DESIGN, 2022, 394
  • [45] Numerical simulation of coupling heat transfer and thermal stress for spent fuel dry storage cask with different power distribution and tilt angles
    Wei-Hao Ji
    Jian-Jie Cheng
    Han-Zhong Tao
    Wei Li
    Nuclear Science and Techniques, 2023, 34
  • [46] Numerical simulation of coupling heat transfer and thermal stress for spent fuel dry storage cask with different power distribution and tilt angles
    Wei-Hao Ji
    Jian-Jie Cheng
    Han-Zhong Tao
    Wei Li
    Nuclear Science and Techniques, 2023, 34 (02) : 111 - 129
  • [47] Neutron Measurements and Monte Carlo Simulations of Spent Nuclear Fuel in Dry Cask Storage Using a New Remote Monitoring System Prototype
    King, Jeremy W. W.
    Marianno, Craig M. M.
    Chirayath, Sunil S. S.
    NUCLEAR SCIENCE AND ENGINEERING, 2023, 197 (12) : 3125 - 3137
  • [48] Vibrational modes for the internal characterization of a full-scale Transnuclear-32 dry storage cask for spent nuclear fuel assemblies
    Lin, Kevin Yi-Wei
    Mobley, Joel
    Prather, Wayne E.
    Lu, Zhiqu
    Priyadarshan, Gautam
    Gladden, Joseph R.
    JOURNAL OF SOUND AND VIBRATION, 2019, 460
  • [49] A risk-informed assessment tool to support review of license amendment requests for spent nuclear fuel dry cask storage systems
    Eidelpes, Elmar
    Biersdorf, John M.
    Nuclear Engineering and Design, 2022, 394
  • [50] Ventilation pattern and heat dissipation characteristics of a vertical dry storage cask for spent nuclear fuel: Wind tunnel experiments and CFD simulations
    Wang, Yao-Hung
    Lin, Yi-Pin
    Chang, Heui-Yung
    Lai, Chi-Ming
    ANNALS OF NUCLEAR ENERGY, 2021, 160