Calculation of a materials relocation experiment simulating a core disruptive accident condition in fast breeder reactors

被引：0
|
作者：
Tokyo Inst of Technology, Tokyo, Japan [1 ]
机构：
来源：
Nucl Eng Des | / 1-2卷 / 177-196期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
24
引用
收藏
相关论文
共 50 条
  • [31] INVESTIGATION OF MATERIAL RELOCATION PHENOMENA DURING SEVERE ACCIDENTS IN FAST BREEDER-REACTORS
    PEPPLER, W
    WILL, H
    MISU, S
    GROTZBACH, G
    NUCLEAR ENGINEERING AND DESIGN, 1987, 100 (03) : 409 - 425
  • [32] NUCLEAR PERFORMANCE OF LIQUID-METAL FAST BREEDER-REACTORS DESIGNED TO PRECLUDE ENERGETIC HYPOTHETICAL CORE DISRUPTIVE ACCIDENTS
    BAILEY, HS
    LU, YS
    NUCLEAR TECHNOLOGY, 1979, 44 (01) : 76 - 82
  • [33] HETEROGENEOUS CORE DESIGNS FOR LIQUID METAL FAST BREEDER REACTORS.
    Dickson, P.W.
    Doncals, R.A.
    Advances in Nuclear Science and Technology, 1980, 12 : 33 - 91
  • [34] RECENT EVOLUTION OF CORE DESIGN FOR LARGE FAST BREEDER-REACTORS
    OTAKE, I
    JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1981, 23 (12): : 877 - 885
  • [35] CORE MATERIALS STUDIES IMPROVE FAST BREEDER PERFORMANCE
    LAIDLER, JJ
    BENNETT, JW
    NUCLEAR ENGINEERING INTERNATIONAL, 1980, 25 (301): : 31 - 36
  • [36] Assessment of creep-fatigue damage at main vessel triple point of Prototype Fast Breeder Reactor after core disruptive accident
    Sati, Bhuwan Chandra
    Srinivasan, R.
    Selvaraj, P.
    Chellapandi, P.
    TRANSACTIONS OF THE INDIAN INSTITUTE OF METALS, 2010, 63 (2-3): : 657 - 660
  • [37] Assessment of creep-fatigue damage at main vessel triple point of Prototype Fast Breeder Reactor after core disruptive accident
    Bhuwan Chandra Sati
    R. Srinivasan
    P. Selvaraj
    P. Chellapandi
    Transactions of the Indian Institute of Metals, 2010, 63 : 657 - 660
  • [38] Numerical study of initiating phase of core disruptive accident in small sodium-cooled fast reactors with negative void reactivity
    Ishida, Shinya
    Fukano, Yoshitaka
    Tobita, Yoshiharu
    Okano, Yasushi
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2024, 61 (05) : 582 - 594
  • [39] A fundamental approach to specify thermal and pressure loadings on containment buildings of sodium cooled fast reactors during a core disruptive accident
    Velusamy, K.
    Chellapandi, P.
    Satpathy, K.
    Verma, Neeraj
    Raviprasan, G. R.
    Rajendrakumar, M.
    Chetal, S. C.
    ANNALS OF NUCLEAR ENERGY, 2011, 38 (11) : 2475 - 2487
  • [40] ABSORBER MATERIALS FOR CONTROL ROD SYSTEMS OF FAST BREEDER-REACTORS
    DUNNER, P
    HEUVEL, HJ
    HORLE, M
    JOURNAL OF NUCLEAR MATERIALS, 1984, 124 : 185 - 194
12345