Application of the GIF Safety Design Criteria and Safety Design Guidelines on Decay Heat Removal System to Next Generation Sodium-Cooled Fast Reactor in Japan

被引：0
|
作者：
Yamano, Hidemasa [1 ]
Futagami, Satoshi [1 ]
Higurashi, Koichi [2 ]
机构：
[1] Japan Atomic Energy Agency (JAEA), 4002 Narita, O-arai, Ibaraki, 311-1393, Japan
[2] Mitsubishi FBR Systems, Inc (MFBR), 2-34-17, Jingumae, Shibuya, Tokyo,150-0001, Japan
来源：
Proceedings of Advanced Reactor Safety, ARS 2024 | 2024年
关键词：
Compilation and indexing terms; Copyright 2025 Elsevier Inc;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Cooling systems - Dynamic response - Model structures - Nuclear reactor accidents - Railroad accidents - Reactor refueling - Structural dynamics - Thermoelectric equipment
引用
收藏
页码：121 / 130
相关论文
共 50 条
  • [1] Safety Design Features for Japan Sodium-cooled Fast Reactor - Passive Safety and CDA Mitigation
    Kotake, Shoji
    Uto, Nariaki
    Aoto, Kazumi
    Kubo, Shigenobu
    ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2010, 55 (06): : 386 - +
  • [2] Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor
    Yamano, H.
    Kubo, S.
    Shimakawa, Y.
    Fujita, K.
    Suzuki, T.
    Kurisaka, K.
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2012, 2012
  • [3] Fast reactor decay heat removal:: approach to the safety system design in Japan and Europe
    Farrar, B
    Lefèvre, JC
    Kubo, S
    Mitchell, CH
    Yoshinari, Y
    Itooka, S
    NUCLEAR ENGINEERING AND DESIGN, 1999, 193 (1-2) : 45 - 54
  • [4] DESIGN CRITERIA FOR SODIUM-COOLED FAST REACTOR COMPONENTS
    SLEMBER, R
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (01): : 116 - &
  • [5] ACTIVITIES OF THE GIF SAFETY AND OPERATION PROJECT OF SODIUM-COOLED FAST REACTOR SYSTEMS
    Yamano, Hidemasa
    Chenaud, Marie-Sophie
    Kang, Seok-Hun
    Sumner, Tyler
    Tsige-Tamirat, Haileyesus
    Wang, Jin
    Rozhikhin, Evgeny
    PROCEEDINGS OF 2021 28TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE28), VOL 1, 2021,
  • [6] Core and safety design for France-Japan common concept on sodium-cooled fast reactor
    Takano, Kazuya
    Ohki, Shigeo
    Ozawa, Takayuki
    Yamano, Hidemasa
    Kubo, Shigenobu
    Ogura, Masashi
    Yamada, Yumi
    Koyama, Kazuya
    Kurita, Koichi
    Costes, Laurent
    Venard, Christophe
    Carluec, Bernard
    Perrin, Benoit
    Verrier, Denis
    EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 2022, 8
  • [7] Design and Analysis of Passive Decay Heat Removal System for Sodium-cooled Small Modular Reactor
    Chen Z.
    Yang H.
    Yu H.
    Hou B.
    Zhu L.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (08): : 1417 - 1423
  • [8] A study on reliability assessment of a decay heat removal system for a sodium-cooled fast reactor
    Kim, Jintae
    Jae, Moosung
    ANNALS OF NUCLEAR ENERGY, 2018, 120 : 534 - 539
  • [9] SAFETY DESIGN APPROACH FOR A LARGE-SCALE JAPAN SODIUM-COOLED FAST REACTOR (JS']JSFR)
    Kotake, Shoji
    Yamano, Hidemasa
    Sagayama, Yutaka
    FUSION SCIENCE AND TECHNOLOGY, 2012, 61 (1T) : 137 - 143
  • [10] SAFETY ASPECTS OF INTERMEDIATE HEAT TRANSPORT AND DECAY HEAT REMOVAL SYSTEMS OF SODIUM-COOLED FAST REACTORS
    Chetal, Subhash Chander
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2015, 47 (03) : 260 - 266
12345