reactor core pressure drop

Analysis of Heat Transfer Characteristics in Core of Supercritical Water Cooled Reactor;

超临界水冷堆堆芯传热特性分析

Analyzed are the concept and significance of real time simulation for the safety analysis code of the PWR core using a microcomputer.

在微机的运行环境下，明确了实时仿真在堆芯安全分析背景下的概念与意义，通过对目前实时仿真工作现状和基本途径的分析，选择并组合成熟安全分析程序中所用过的数学模型，编制了一套操作简便的压水堆堆芯安全分析程序，具体实施了单区堆芯的高精度实时仿真，研究了３ 区６ 节点堆芯的高精度实时仿真过程的实现问题，指出了堆芯实时仿真的特点、方式及未来前景。

Presented is a model for the multi region and variable node PWR core.

建立了多区变节点压水堆堆芯的数学物理模型 。

Dynamic engineering model of the HTR-10 reactor core;

HTR-10堆芯的工程化动态模型

According to the current design and relative procedures in QNPP,the main feed-water system can not be restored after its isolating under accident conditions,and thus there will be a larger contribution to the total core damage frequency of QNPP.

按照现有的设计和遵循的相关规程,秦山核电厂事故工况下主给水系统隔离后不能恢复运行,对核电厂总的堆芯损伤频率的贡献较大。

The accident sequences and mathematical model of core melt (CM) was established, then quantitative analysis is performed.

并以陆奥号核动力商船为例,运用事件树分析技术,对SGTR事故进行了安全分析,得出了事故后可能导致堆芯熔化的事故序列,确定了堆芯熔化数学模型,并进行了定量化分析。