堆芯冷却

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 .

基于LOFTL2-5试验的一维与三维计算结果比较，初步分析了有关三维效应及其对ECC旁通等应急堆芯冷却过程以及燃料包壳峰值温度（PCT）的影响。

By comparing the 1-D and 3-D calculation results of LOFT L2-5 test progress , related 3-D effects and its influence on such emergency core cooling progress as ECC bypass etc and that on the fuel peaking cladding temperature ( PCT ) is preliminarily investigated .

CARR应急堆芯冷却系统停堆冷却措施分析

Analysis of Cooling Measures for ECCS at CARR Shutdown

本文以核安全法规和导则为前提，以满足系统功能为基础，首先介绍了CARR应急堆芯冷却系统的功能、主要参数和流程。

This paper first introduced the function , main parameters and flow chart of the CARR ECCS , consider - ing the nuclear safety code and guide .

根据CARR的实际情况，对应急堆芯冷却系统的停堆冷却措施和典型事故进行了分析，论证了该系统是如何在正常停堆和事故停堆状态下实现非能动堆芯冷却的。

Based on the real condition of CARR , this paper also analyzed the typical accidents and the shutdown cooling of the ECCS , and demonstrated how the ECCS carded out the passive cooling at normal and accidental shutdown .

应急堆芯冷却系统是核电站工程安全设施的一个组成部分。

The emergency core cooling system is a component part of engineered safety feature of a nuclear power plant .

分析结果表明，低压安注系统在冷段注入再循环和在冷、热段同时注入再循环时能保证堆芯冷却，并防止硼酸结晶。

The results show that the reactor core can be cooled and boron precipitation can be prevented during the cold leg recirculation or both of cold and hot leg recirculation using low head injection system ( LHIS ) .

安全壳再循环地坑滤网是核电厂安全系统的重要设备，再循环工况下它的工作状况直接影响到安全注射系统（应急堆芯冷却系统）、安全壳喷淋系统的正常运行。

The recirculating pit filter in containment is an important equipment of safety system in nuclear power plant . In the recirculating condition , it influences the operation of emergency reactor core cooling system and spray system in containment .

本文应用阶段任务分析法建立了应急堆芯冷却系统的综合故障树，求得应急堆芯冷却系统无效度的精确解。

In this paper , we construct the synthetic fault tree of emergency core cooling system by using phased mission analysis method , calculate the exact so - lution of the unavailability of emergency core cooling system , and present two approximate calculating techniques .

反应堆堆芯隔离冷却系统

Reactor core isolation cooling system

为确保堆芯的充分冷却和防止汽轮机叶片的损坏，将SG水位控制在合理的位置是十分重要的。

Properly controlling the water level of SG is very important in order to secure the sufficient cooling source of nuclear reactor and prevent the damage of turbine blades .

GB/T13632-1992监督压水堆堆芯充分冷却的测量要求

Measurements for monitoring adequate cooling within the core of pressurized light water reactors

当发生冷却剂丧失事故时，它向堆芯注入应急冷却水，以确保核电站的安全。

When a loss-of-coolant accident occurs , it injects emergency cooling water into the core to ensure the safety of a nuclear power plant .

其中DPR-1堆芯是自然循环冷却，而DPR-3是强迫循环冷却。

The core of DPR-1 is cooled by natural circulation and DPR-3 is cooled by forced circulation .

简要描述了实验过程及实验结果，为先进堆非能动堆芯应急冷却系统的设计提供了实验依据。

The experiment process and experiment results were described in this paper .

分析结果表明：堆芯从4560s开始破坏。由于堆芯的冷却条件很差，使得整个的堆芯早期失效过程相对较快。

The calculation results show that the core starts damage from 4 560s and the whole process of early core degradation is relatively fast due to poor core cooling conditions .

停堆冷却过程中运行时间最长、问题最复杂的是应急堆芯冷却系统投入冷却阶段，是整个冷却过程中最关键的阶段。

The second phase is the most important one in total cooling process for that it is operated on the most complicated condition and at the longest period .

当核反应堆处于失水事故时，利用堆芯补水箱（CMT）内含硼水的重力特性对堆芯进行非能动注水，实现应急堆芯冷却。

When the nuclear reactor is in the state of leaking , the boric water 's gravity characteristics can be used to supply water to core passively , which can cool the core urgently .