堆芯熔化

现有概率安全评价指出，常规轻水堆的堆芯熔化频率及安全壳失效，放射性大量释放的频率都是很低的。

The available probabilistic safety analysis study shows that both the occurrence of core meltdown and the frequency of occurrence of outer containment failure are low .

轻水堆核电站堆芯熔化分析

LWR Nuclear Power Plant Core Meltdown Analysis

最后根据对支配性事故序列和各题头事件重要度的分析，提出了降低SGTR事故导致堆芯熔化发生概率应采取的相应措施。

At last , according to the analysis of dominant accident sequences and events ' importance , the measures of reducing the Core Melting Frequency are advised .

三个反应堆堆芯熔化了装它们的容器。

Three reactor cores melted though their containment vessels .

用分子动力学方法研究反应堆堆芯熔化机理

A Mechanism Investigation of Core Melting in Nuclear Reactor Using Molecular Dynamics Method

文章比较了正常冷却剂释放、间隙释放和堆芯熔化状况下不同核素对安全壳内辐射监测仪表示值的相对贡献。

Importance of individual nuclides were compared during normal coolant release , gap release and core melt .

虽然他们都安然无恙，但是却面临着新的恐怖&离他们30英里外的福岛第一核电站可能会发生灾难性的核反应堆堆芯熔化事故。

My relatives are unharmed , but there are new fears of a catastrophic meltdown at the Fukushima Daiichi nuclear power plant , just 30 miles away .

由于反应堆在常压下运行，不会发生堆芯熔化事故，安全性好，可靠性高，技术上可立足国内。

This type of reactor is operated at normal pressure , and will be no accident of in-core melting . It has high reliability and good performance of safety and can be constructed by using domestic technology .

快堆局部堵流所致堆芯局部熔化事故的预测模型快装锅炉对流管束熔化事故原因分析及预防措施

Predictive model for local core melting accident caused by subassembly blockage in a fast reactor Analysis and Prevention to the Melt Down of Convection Bank in a Package Boiler

核电厂运行经验反馈和概率安全分析表明，核电厂在停堆状态下具有相当大的堆芯熔化的潜在风险。

Nuclear Power Plant ( NPP ) operation experiment feedback and probabilistic safety analysis show clearly that NPPs in the shutdown conditions have great potential risk of coremeltdown .

非能动余热排出系统是非能动安全设计思想的一个成功应用，担负着反应堆停堆后安全可靠地排出堆芯余热，防止出现堆芯熔化事故的重任。

The passive residual heat removal system ( PRHR ) is a successful application of the passive safety design theory . Its function is to remove core decay heat for any postulated non-LOCA event , prevent the occurrence of reactor meltdown accident .