PARAMETRIC STUDY OF DYNAMIC BEHAVIOUR AND STABILITY OF A STEAM-COOLED FAST REACTOR WITH AN INTEGRATED COOLING CYCLE

被引:0
|
作者
ERBACHER, F
FRISCH, W
HUBSCHMANN, W
MALANG, S
RITZ, L
WOITE, G
机构
来源
ATOMKERNENERGIE | 1968年 / 13卷 / 02期
关键词
D O I
暂无
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
引用
收藏
页码:85 / +
页数:1
相关论文
共 50 条
  • [31] DESAIN STUDY OF GAS COOLED FAST REACTOR WITH NATURAL URANIUM AS FUEL CYCLE INPUT USING RADIAL SHUFFLING STRATEGY
    Irka, Feriska Handayani
    Aryani, Menik
    Suud, Zaki
    Sekimoto, H.
    [J]. 3RD INTERNATIONAL CONFERENCE ON ADVANCES IN NUCLEAR SCIENCE AND ENGINEERING 2011 (ICANSE 2011), 2012, 1448 : 74 - 81
  • [32] Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors
    Song, Ping
    Zhang, Dalin
    Feng, Tangtao
    Wang, Shibao
    Chen, Jing
    Wang, Xin'an
    Xue, Xiuli
    Zhang, Yapei
    Wang, Mingjun
    Qiu, Suizheng
    Su, G. H.
    [J]. PROGRESS IN NUCLEAR ENERGY, 2019, 110 : 213 - 223
  • [33] Analysis and assessment of the integrated generation IV gas-cooled fast nuclear reactor and copper-chlorine cycle for hydrogen and electricity production
    Al-Zareer, Maan
    Dincer, Ibrahim
    Rosen, Marc A.
    [J]. ENERGY CONVERSION AND MANAGEMENT, 2020, 205
  • [34] Experimental study and kinetic analysis of sodium-water chemical reaction mechanism in steam generator of sodium-cooled fast reactor
    Kikuchi, Shin
    Seino, Hiroshi
    Kurihara, Akikazu
    Ohshima, Hiroyuki
    [J]. Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B, 2013, 79 (799): : 271 - 275
  • [35] CFD modeling methods applied to a lead-cooled fast reactor: A parametric study on conjugate heat transfer and thermal boundary conditions
    Umezu, Ivan K.
    Godino, Dario M.
    Ramajo, Damián E.
    Pereira, Claubia
    Costa, Antonella L.
    [J]. Nuclear Engineering and Design, 2024, 429
  • [36] Advanced MOX core design study of sodium-cooled reactors in current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan
    Mizuno, T
    Niwa, H
    [J]. NUCLEAR TECHNOLOGY, 2004, 146 (02) : 155 - 163
  • [37] Modeling and simulation of feedwater control system with multiple once-through steam generators in a sodium-cooled fast reactor (I): Dynamic model development
    Sun, Peiwei
    Zhang, Xianshan
    [J]. ANNALS OF NUCLEAR ENERGY, 2020, 138
  • [38] A STUDY ON DYNAMIC CHARACTERISTICS OF PLATE-FIN RECUPERATOR IN HIGH-TEMPERATURE GAS-COOLED REACTOR CLOSED CYCLE
    Ding, Ming
    Yang, Xiaoyong
    Wang, Jie
    [J]. NUCLEAR TECHNOLOGY, 2010, 169 (03) : 205 - 217
  • [39] Conceptual design of an indirect-cycle, supercritical steam cooled fast breeder reactor with negative coolant void reactivity characteristics (vol 20, pg 305, 1993).
    Jevremovic, T
    Oka, Y
    Koshizuka, S
    [J]. ANNALS OF NUCLEAR ENERGY, 1998, 25 (4-5) : 329 - 329
  • [40] Study on Control Strategy of Natural Circulation Lead-cooled Fast Reactor Coupled with S-CO2 Brayton Cycle
    Liu G.
    Yi J.
    Li G.
    Liang T.
    Fang H.
    Chen W.
    [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 (04): : 138 - 147