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
  • [31] Seismic analysis of free-standing spent-fuel dry storage cask considering soil-concrete pad-cask interaction
    Kim, Seungpil
    Cho, Sang Soon
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (10) : 4446 - 4454
  • [32] Dynamic response of dry cask storage systems for spent nuclear fuel to near field blast loading
    Hanifehzadeh, Mohammad
    Gencturk, Bora
    ANNALS OF NUCLEAR ENERGY, 2021, 155
  • [33] Comparing Different Approaches to Calculating Decay Heat Power of a Spent Fuel Dry Storage Cask for Krsko NPP
    Merljak, Vid
    Kromar, Marjan
    30TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2021), 2021,
  • [34] Design and Structural Safety Evaluation of the High Burn-up PWR Spent Nuclear Fuel for Storage Cask
    Na, Taehyung
    Lee, Youngoh
    Kim, Yeji
    Lee, Donghee
    Kim, Taehyeon
    Kim, Kiyoung
    Kim, Yongdeog
    JOURNAL OF NUCLEAR FUEL CYCLE AND WASTE TECHNOLOGY, 2024, 22 (02): : 201 - 210
  • [35] An investigation of the seismic response of a free-standing dry storage cask for spent fuel using the finite element method
    Ko, YungYen
    Yang, Hsuanchih
    Huang, Chin-Cheng
    NUCLEAR ENGINEERING AND DESIGN, 2013, 261 : 33 - 43
  • [36] Numerical Modeling of Heat and Mass Transfer Processes in the Transfer of Spent Nuclear Fuel from "Wet" to "Dry" Cask Storage
    Karyakin Y.E.
    Pletnev A.A.
    Fedorovich E.D.
    Journal of Engineering Physics and Thermophysics, 2017, 90 (1) : 80 - 87
  • [37] Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas
    Yoo, Hee Sang
    Yoo, Seung Hun
    Kim, Eung Soo
    ANNALS OF NUCLEAR ENERGY, 2019, 132 : 108 - 118
  • [38] Dose rate distribution calculations with the Monte Carlo method for high burnup spent fuel loaded dry storage cask
    Pediz, Gokhan
    Acar, Banu Bulut
    NUCLEAR ENGINEERING AND DESIGN, 2024, 426
  • [39] Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition
    Durdu, Habibe Merve
    Acar, Banu Bulut
    KERNTECHNIK, 2023, 88 (04) : 424 - 436
  • [40] Validation of UNIST Monte Carlo code MCS for criticality safety analysis of PWR spent fuel pool and storage cask
    Jang, Jaerim
    Kim, Wonkyeong
    Jeong, Sanggeol
    Jeong, Eun
    Park, Jinsu
    Lemaire, Matthieu
    Lee, Hyunsuk
    Jo, Yongmin
    Zhang, Peng
    Lee, Deokjung
    ANNALS OF NUCLEAR ENERGY, 2018, 114 : 495 - 509