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
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