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The Models Used in Predicting Steam Condensation Occurs during Nuclear Reactor Loss of Coolant Accident

机译：用于预测蒸汽冷凝的模型发生在核反应堆的冷却剂事故中

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Adel Ismail Mohammed;
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1. Development of Mathematical Models for Substantiating the Safety of Nuclear Power Stations and an Analysis of the Dynamics of Accidents Associated with Intercircuit Leaks in the Steam Generators of Reactor Installations with Lead-Bismuth Coolant [J] . A. V. Dedul, I. S. Krasko Thermal engineering . 2006,第1期

机译：证实核电站安全的数学模型的开发以及铅铋冷却剂反应堆装置的蒸汽发生器中与电路间泄漏有关的事故动态分析
2. THE ONCE-THROUGH MODE OF STEAM GENERATOR REFLUX CONDENSATION IN LOSS-OF-COOLANT ACCIDENT SCENARIOS [J] . Y. LIAO, S. GUENTAY, D. SUCKOW Nuclear Technology . 2011,第3期

机译：失水事故场景下蒸汽发生器回流冷凝的一次通过模式
3. Ab initio calculations and iodine kinetic modeling in the reactor coolant system of a pressurized water reactor in case of severe nuclear accident [J] . Xerri B., Canneaux S., Louis F., Computational & theoretical chemistry . 2012,第Null期

机译：发生严重核事故时压水堆反应堆冷却剂系统的从头算和碘动力学模型
4. Identification of a loss of coolant accident on a submaring nuclear steam raising plant using an intelligent knowledge based system [C] . Richard J. Carrick International conference on industrial and engineering applications of artificial intelligence and expert systems . 1997

机译：使用智能知识系统识别潜艇核蒸汽升高厂的冷却液事故丧失
5. Probabilistic risk assessment for a loss of coolant accident in McMaster Nuclear Reactor and application of reliability physics model for modeling human reliability. [D] . Ha, Taesung. 2007

机译：McMaster核反应堆中冷却剂损失事故的概率风险评估，以及用于建立人类可靠性模型的可靠性物理模型的应用。
6. Development of an automatedchemistry control system forsecondary coolant circuits inCANDU nuclear power reactors [O] . J. R. Dean, R. B. Stewart 1979

机译：开发自动化化学控制系统二次冷却液回路坎杜核电反应堆
7. LABORATORY SIMULATIONS OF CLADDING-STEAM REACTIONS FOLLOWING LOSS-OF- COOLANT ACCIDENTS IN WATER-COOLED POWER REACTORS. [O] . Hesson, J.C., Ivins, R.O., Wilson, R.E., 1970

机译：水冷功率反应器中冷却事故损失后的包覆蒸汽反应的实验室模拟。
8. Simulation of a loss of coolant accident without high pressure injection but with secondary side bleed and feed. Results of the fourth standard problem exercise on the simulation of loss of coolant accidents. Report of the IAEA technical co-operation project RER/9/004 on evaluation of safety aspects of WWER-440 Model 213 nuclear power plants [R] . 1995

机译：模拟在没有高压喷射但具有二次侧泄放和进给的情况下的冷却剂损失事故。关于模拟冷却剂事故的第四个标准问题的结果。关于评估WWER-440 213型核电厂安全方面的原子能机构技术合作项目RER / 9/004的报告

The Models Used in Predicting Steam Condensation Occurs during Nuclear Reactor Loss of Coolant Accident

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