SELECTING A SUBITABLE TYPE OF MAIN CIRCULATION PUMP IN NUCLEAR POWER STATION WITH REACTOR COOLED BY WATER UNDER PRESSURE

被引：0
|
作者：
TURETSKI.LI
GRYZLOV, AG
PUGACHEV.TF
PUZYREV, LK
机构：
来源：
THERMAL ENGINEERING | 1970年 / 17卷 / 12期
关键词：
D O I：
暂无
中图分类号：
O414.1 [热力学];
学科分类号：
摘要：
引用
收藏
页码：4 / &
相关论文
共 50 条
  • [31] RESULTS OF TESTING AN ELECTROMAGNETIC FILTER IN THE SECONDARY LOOP OF A NUCLEAR POWER STATION WITH A WATER-MODERATED WATER-COOLED VVER-440 POWER REACTOR.
    Tsyrul'nikov, D.L.
    Yurchevskii, E.B.
    Belan, F.I.
    Mamet, A.P.
    Yarichin, A.D.
    Labaznikov, S.V.
    Tsybul'nik, L.P.
    Novikov, M.V.
    Berezkin, N.N.
    [J]. Thermal Engineering (English translation of Teploenergetika), 1987, 34 (04): : 188 - 191
  • [32] Study on pressure fluctuation in main pump of 300 MW nuclear power plants
    Chen, Xiang-Yang
    Yuan, Dan-Qing
    Yang, Min-Guan
    Yuan, Shou-Qi
    [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2010, 31 (03): : 78 - 82
  • [33] Experience with the Operation of Water-cooled Generators at Biblis Nuclear Power Station.
    Doerr, A.
    Paffrath, G.
    [J]. VGB-Kraftwerkstechnik, 1982, 62 (03): : 220 - 223
  • [34] CALCULATION OF THE QUANTITY OF CORROSION PRODUCT DEPOSITS ON FUEL-ELEMENTS AND OF THEIR RADIONUCLIDES IN THE REACTOR LOOP OF A NUCLEAR-POWER STATION WITH A WATER-MODERATED WATER-COOLED REACTOR
    TEVLIN, SA
    [J]. THERMAL ENGINEERING, 1991, 38 (01) : 12 - 15
  • [35] Simulation of thermal breakdown of a reactor vessel as a result of a heavy accident in a nuclear power plant with reactors of VVER (water-moderated water-cooled power reactor) type
    Dolgov, VV
    Kashcheev, MV
    Muranov, YV
    [J]. HIGH TEMPERATURE, 1996, 34 (05) : 759 - 769
  • [36] Simulation of Thermal Breakdown of a Reactor Vessel as a Result of Heavy Accident in a Nuclear Power Plant with Reactors of VVER (Water-moderated Water-cooled Power Reactor) Type
    Dolgov, V. V.
    Kashcheev, M. V.
    Muranov, Y. V.
    [J]. High Temperature (English translation of Teplofizika Vysokikh Temperatur), 1996, 34 (05):
  • [37] 900 MW NUCLEAR POWER STATION PHILIPPSBURG WITH AN AEG BOILING WATER REACTOR
    HUTTL, A
    MOLL, W
    [J]. ATOMWIRTSCHAFT, 1970, 15 (07): : 320 - &
  • [38] Development and implementation of nuclear power station with advanced boiling water reactor (ABWR)
    Tomono, K
    Miyamoto, T
    Hayashi, T
    Hucik, SA
    [J]. JSME INTERNATIONAL JOURNAL SERIES C-MECHANICAL SYSTEMS MACHINE ELEMENTS AND MANUFACTURING, 1997, 40 (02): : A13 - A14
  • [39] Design Method of Some Results of Investigation of the Model of an Axial Main Circulation Pump for High Capacity Reactor Blocks of Nuclear Power Plants.
    Val'chuk, V.S.
    Golikov, V.A.
    Kuzina, A.I.
    Papir, A.N.
    Shkarbul', S.N.
    [J]. Trudy LPI, 1981, (374): : 16 - 20
  • [40] On the Shape of Stress Corrosion Cracks in Water-Cooled Nuclear Power Reactor Piping
    Lee, Sang-Kwon
    Kramer, Daniel
    Macdonald, Digby D.
    [J]. MATERIALS DEGRADATION IN ENERGY SYSTEMS: CORROSION AND HYDROGEN-MATERIAL INTERACTIONS, 2013, 50 (30): : 27 - 39
12345