POWER ESCALATION EXPERIMENTS FOR E FERMI PRESSURIZED WATER REACTOR PLANT

被引:0
|
作者
CAMPLANI, A
GIURIATO, A
机构
来源
ENERGIA NUCLEARE | 1967年 / 14卷 / 01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:18 / &
相关论文
共 50 条
  • [21] The Research on Seismic Margin Analysis for Piping in Pressurized Water Reactor Nuclear Power Plant
    Liu, Zhenshun
    Li, Qiang
    Zhen, HongDong
    Wu, Yingxi
    [J]. 2018 INTERNATIONAL CONFERENCE ON POWER SYSTEM TECHNOLOGY (POWERCON), 2018, : 4756 - 4759
  • [22] Research on Hydrogen Control Strategy in Advanced Pressurized Water Reactor Nuclear Power Plant
    先进压水堆核电厂氢气控制策略分析研究
    [J]. Chai, Guohan (chaiguohan@chinansc.cn), 1600, Atomic Energy Press (54): : 1221 - 1227
  • [23] SINGLE-LOOP NUCLEAR-POWER-PLANT WITH A PRESSURIZED-WATER REACTOR
    KOROVKIN, SV
    [J]. SOVIET ATOMIC ENERGY, 1991, 71 (05): : 940 - 942
  • [24] MODEL FOR STRATEGICALLY OPTIMIZING FUELLING OF A PRESSURIZED WATER REACTOR NUCLEAR-POWER PLANT
    LUTZOW, K
    [J]. KERNENERGIE, 1974, 17 (10): : 308 - 313
  • [25] Research on boron recycle system operation ability for pressurized water reactor power plant
    Wu, Jian
    Zhao, Wen-Hao
    Li, Jun
    [J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2012, 46 (SUPPL. 1): : 449 - 453
  • [26] Dynamic Characteristics Analyse of Pressurized Water Reactor Nuclear Power Plant Based on PSASP
    Xiong, Li
    Liu, Dichen
    Wang, Bo
    Wu, Ping
    Zhao, Jie
    Shi, Xi
    [J]. ICIEA: 2009 4TH IEEE CONFERENCE ON INDUSTRIAL ELECTRONICS AND APPLICATIONS, VOLS 1-6, 2009, : 3620 - 3625
  • [27] SELECTED PROBLEMS ON POWER-CONTROL OF NUCLEAR-POWER PLANT WITH PRESSURIZED WATER-REACTOR
    POLLAK, J
    KISIELEWICZ, S
    [J]. NUKLEONIKA, 1978, 23 (6-7) : 679 - 689
  • [28] Influence of cooling water temperature on the efficiency of a pressurized-water reactor nuclear-power plant
    Durmayaz, Ahmet
    Sogut, Oguz Salim
    [J]. INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2006, 30 (10) : 799 - 810
  • [29] PROBABILISTIC FRACTURE MECHANICS ANALYSIS FOR DEGRADED REACTOR PRESSURE VESSEL IN PRESSURIZED WATER REACTOR NUCLEAR POWER PLANT
    Huang, Kuan-Rong
    Huang, Chin-Cheng
    Chou, Hsoung-Wei
    [J]. PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2014, VOL 7, 2014,
  • [30] AUTOMATIC REACTOR POWER-CONTROL FOR A PRESSURIZED WATER-REACTOR
    CHOI, JI
    HAH, YJ
    LEE, UC
    [J]. NUCLEAR TECHNOLOGY, 1993, 102 (02) : 277 - 286