Simplified Calculation of Saturated Steam Parameters in Sealed Premises of Nuclear Power Plants Following Loss of Coolant Accident.

被引：0
|
作者：
Gordon, B.G.
Ugoleva, I.R.
机构：
来源：
Teploenergetika | 1979年 / 07期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Equations for the calculation of the parameters of state of saturated steam in sealed rooms following loss of coolant accident are considered. It is proposed to use, for the calculation of the properties of saturated steam, the ideal gas equation which is satisfied with a precision adequate for engineering purposes, for temperatures up to 160 degree C, i. e. in the range in which saturated steam parameters in sealed rooms vary.
引用
收藏
页码：72 / 73
相关论文
共 8 条
  • [1] SIMPLIFIED CALCULATION OF THE PARAMETERS OF SATURATED STEAM IN THE REACTOR CONTAINMENTS OF A NUCLEAR-POWER STATION WITH ESCAPE OF COOLANT
    GORDON, BG
    UGOLEVA, IR
    THERMAL ENGINEERING, 1979, 26 (07) : 437 - 437
  • [2] An advanced method for determination of loss of coolant accident in nuclear power plants
    Mahmoodi, R.
    Shahriari, M.
    Zolfaghari, A.
    Minuchehr, A.
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (06) : 2013 - 2019
  • [3] Evaluation of chemical effects on fuel assembly blockage following a loss of coolant accident in nuclear power plants
    Wang, Da
    Chang, Baochen
    Zhang, Tianyi
    Tan, Sichao
    Niu, Fenglei
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2020, 44 (07) : 5488 - 5499
  • [4] Determination of Loss of Coolant Accident (LOCA) in Nuclear Power Plants Using Signal Processing Method
    Mahmoodi, R.
    Shahriari, M.
    Zolfaghari, A.
    ENGINEERING LETTERS, 2009, 17 (04)
  • [5] CALCULATION OF HYDRODYNAMICS OF PRIMARY COOLANT CIRCUIT IN NUCLEAR-POWER PLANTS EQUIPPED WITH WATER-COOLED WATER-MODERATED POWER-REACTORS FOR CASE OF LOSS OF COOLANT ACCIDENT
    DEMENTEV, BA
    KATKOVSKIJ, EA
    KERNENERGIE, 1975, 18 (05): : 145 - 147
  • [6] NONEQUILIBRIUM PROCESSES DURING THE SMALL BREAK LOSS-OF-COOLANT ACCIDENT IN NUCLEAR-POWER-PLANTS
    PARZER, I
    PETELIN, S
    MAVKO, B
    ZEITSCHRIFT FUR ANGEWANDTE MATHEMATIK UND MECHANIK, 1993, 73 (7-8): : T732 - T736
  • [7] Selection of Optimal Scheme of Model for Calculating Breakdowns in Loss of Coolant Accident at Nuclear Power Plants.
    Bukrinskii, A.M.
    Fuks, R.L.
    Teploenergetika, 1982, (01): : 13 - 16
  • [8] Integrating renewal process modeling with Probabilistic Physics-of-Failure: Application to Loss of Coolant Accident (LOCA) frequency estimations in nuclear power plants
    Sakurahara, Tatsuya
    O'Shea, Nicholas
    Cheng, Wen-Chi
    Zhang, Sai
    Reihani, Seyed
    Kee, Ernie
    Mohaghegh, Zahra
    RELIABILITY ENGINEERING & SYSTEM SAFETY, 2019, 190
1