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- Two phase countercurrent flow in reactor hot leg at loss of coolant accident is studied by experiment and analysis. 对反应堆失水事故条件下热管段内的两相流逆向流动过程进行了实验研究和理论分析。
- Loss of coolant accident is considered as design basis accident in the design of nuclear power plant. 失水事故是核电站设计的基准事故之一,是压水堆事故分析关注的重点。
- The analysis of large break loss of coolant accident (LBLOCA) which occured at nominal power of nuclear power plant is given. 摘要针对核电站额定运行工况下发生冷段大破口失水事故进行了分析。
- Small break loss of coolant accident (SBLOCA) of a nuclear power plant reactor primary system is simulated at the high pressure integral test facility (HPITF). The break is loca ted at the bottom of the horizontal cold leg and its area is 1% (NSB 7 case). 在高压综合实验装置(HPITF)上进行核电厂反应堆一次系统冷管段小破口失水事故(SBLO-CA)模拟实验,破口方向为冷管段底部,破口面积为1%25(NSB-7工况)。
- The general-purpose CFD code FLUENT is used to calculate the transient process of China helium-cooled solid breeder test blanket module (TBM) under loss of coolant accident (LOCA) scenario. 摘要用通用计算流体力学程序FLUENT计算了中国氦冷固体增殖实验包层模块(TBM)冷却剂丧失事故中的冷却剂排放瞬态过程。
- very small break loss of coolant accident 小小破口冷却剂丧失事故
- large break loss of coolant accident 大破口失水事故
- Analysis of Loss of Coolant Accident for Pulsed Reactor 脉冲反应堆失水事故分析
- radiological consequences break loss of coolant accident 设计基准事故
- Study on Severe Accident Induced by Large Break Loss of Coolant Accident for Pressurized Water Reactor 压水堆大破口失水事故引发的严重事故研究
- Research on Two-phase Countercurrent Flow in Reactor Hot Leg at the Loss of Coolant Accident 反应堆失水事故条件下热管段内的两相流逆向流动研究
- Keywords LOCA(loss of coolant accident);nuclear heating reactors;inherent safety; 失水事故;核供热堆;固有安全性;
- Analysis of Heat Removal and Boron Precipitation Prevention Using Low Head Injection System Following Large Break Loss of Coolant Accident 大破口失水事故低压安注排热和防止硼结晶分析
- Three Dimensional Monte-Carlo Simulation Method for LMFBR Fuel Bundle Heat Transfer Under Loss of Coolant Accident Conditions 冷却剂丧失条件下钠冷快堆棒束传热的三维蒙特卡罗模拟方法
- Loss of coolant accident (LOCA) 冷却剂丧失事故(LOCA)
- loss of coolant accident 冷却剂璃事故
- Abstract Based on GO-FLOW methodology, the reliability of emergency core cooling system (ECCS) in lose of coolant accident (LOCA) was analyzed. 摘要 应用GO-FLOW法分析在失水事故过程中紧急堆芯冷却系统的可靠性。
- Based on GO-FLOW methodology, the reliability of emergency core cooling system (ECCS) in lose of coolant accident (LOCA) was analyzed. 摘要应用GO-FLOW法分析在失水事故过程中紧急堆芯冷却系统的可靠性。
- In this thesis, a new concept with passive moderator system for TACR isdesigned, and is assessed through analyzing a loss of coolant flow accident(LOFA)by CATHENA Mod3.5c/Rev1, a thermalhydraulic computer codedeveloped by AECL for CANDU. 本论文为钍基先进坎杜堆(TACR)满足非能动安全要求的慢化剂系统进行概念设计;并用热工水力分析程序 CATHENA Mod3.;5c/Rev1 分析反应堆在全厂断电情况下的失流事故;以评价所设计的系统。
- I commiserate with you on the loss of your mother. 你母亲逝世,我特向你慰问。
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- 深远海浮式风电平台 - deep-sea floating wind power platform
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- 京雄高速公路 - Beijing-Xiongan expressway
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- 农业及相关产业增加值 - the added value of agriculture and related industries