IS SODIUM REHEAT JUSTIFIED IN A SODIUM-COOLED FAST BREEDER REACTOR POWER PLANT CYCLE

被引：0
|
作者：
GUNSON, WE
KEYFITZ, IM
MITCHELL, SW
机构：
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1968年 / 11卷 / 02期
关键词：
D O I：
暂无
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：
引用
收藏
页码：639 / &
相关论文
共 50 条
  • [41] Lubrication Characteristics of Hybrid Bearing in Sodium-cooled Fast Reactor
    Pei S.
    Niu H.
    Hong J.
    Jixie Gongcheng Xuebao/Journal of Mechanical Engineering, 2020, 56 (21): : 29 - 37
  • [42] Severe accident source terms for a sodium-cooled fast reactor
    Brunett, Acacia
    Denning, Richard
    Umbel, Marissa
    Wutzler, Whitney
    ANNALS OF NUCLEAR ENERGY, 2014, 64 : 220 - 229
  • [43] Reflector and Protections in a Sodium-cooled Fast Reactor: Modelling and Optimization
    Blanchet, David
    Fontaine, Bruno
    ICRS-13 & RPSD-2016, 13TH INTERNATIONAL CONFERENCE ON RADIATION SHIELDING & 19TH TOPICAL MEETING OF THE RADIATION PROTECTION AND SHIELDING DIVISION OF THE AMERICAN NUCLEAR SOCIETY - 2016, 2017, 153
  • [44] Materials R & D for sodium-cooled fast reactor in China
    XIE Chuchunn
    Baosteel Technical Research, 2010, 4(S1) (S1) : 73 - 73
  • [45] Multiphysics and multiscale simulation for an experimental sodium-cooled fast reactor
    Lopez-Solis, Roberto
    Espinosa-Paredes, Gilberto
    Perez-Valseca, Alejandria D.
    Cruz-Lopez, Carlos- Antonio
    NUCLEAR ENGINEERING AND DESIGN, 2024, 422
  • [46] METHODOLOGY FOR DESIGNING A SODIUM-COOLED FAST REACTOR WITH INHERENT SAFETY
    Stauff, N. E.
    Buiron, L.
    Fontaine, B.
    Rimpault, G.
    NUCLEAR TECHNOLOGY, 2013, 181 (02) : 241 - 250
  • [47] VELOCITY DISTRIBUTIONS IN SODIUM-COOLED FAST REACTOR FUEL CHANNELS
    COOK, KW
    MECHANICAL ENGINEERING, 1970, 92 (05) : 68 - &
  • [48] ECONOMICAL RESEARCH ON HYDROGEN PRODUCTION OF SODIUM-COOLED FAST REACTOR
    Dai, Zhiwen
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 1, ICONE31 2024, 2024,
  • [49] Impact of nuclear data on sodium-cooled fast reactor calculations
    Aures, Alexander
    Bostelmann, Friederike
    Zwermann, Winfried
    Velkov, Kiril
    WONDER-2015 - 4TH INTERNATIONAL WORKSHOP ON NUCLEAR DATA EVALUATION FOR REACTOR APPLICATIONS, 2016, 111
  • [50] DEVELOPMENT OF A FUEL ELEMENT FOR A SODIUM COOLED FAST BREEDER REACTOR
    MORGENSTERN, F
    KERNTECHNIK ISOTOPENTECHNIK UND CHEMIE, 1967, 9 (3-4): : 122 - +
12345