loss of coolant accident

Experimental investigation on 1% small break loss of coolant accident of pressurized water reactor cold leg

PWR冷管段1%小破口失水事故实验研究

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

The simultaneous injection into cold leg and hot leg for more reactor core safety during large break loss of coolant accident

大破口失水事故时冷热段同时安注反应堆堆芯会更安全

The momentum integral method is applied in the frame of safety analysis of pressure water reactors under hypothetical loss of coolant accident ( LOCA) conditions to simulate numerically film condensation, rewetting and vaporization on the inner surface of a pressure water reactor containment.

采用动量积分方法分析压水堆发生失水事故时在安全壳的内表面上的液膜凝结、再浸润和蒸发过程。

A Small Break Loss of Coolant Accident ( SBLOCA) experiment NSB 6 was carried out at the High Pressure Integral Test Facility ( HPITF). The break was oriented at the bottom of the horizontal cold leg with its area of 2%.

在高压综合实验装置（HPITF）上进行了压水堆冷管段2%小破口失水事故实验（NSB－6），破口方向为冷管段底部，破口面积为2%。

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

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。

Liquid collapse level monitoring for nuclear reactors during loss of coolant accident

核反应堆压力容器小破口事故中坍塌液位的测量