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。
reactor core radiation detector
反应堆堆芯辐射检测仪
core mechanical mockup
堆芯机械全尺寸模型
core spray recirculation system
堆芯喷淋再循环系统
seed and blanket core
点火区 再生区堆芯
traversing in core probe
可移动的堆芯内探测器
core spray heat exchanger booster pump
堆芯喷淋热交换讫压泵
reactor core isolation cooling system
反应堆堆芯隔离冷却系统
The Nuclear Core Design of 450MWt Pressurized Water Reactor
45万千瓦(热)压水堆堆芯核设计
Neutron flux distributions in the reactor core are measured.
测量了反应堆堆芯里的中子通量分布。
Heat Balance Test for Determined Reactor Core Power
计算核反应堆堆芯功率的热平衡试验
Core Stable Flowrate Distribution of High Flux Engineering Test Reactor(HFETR)
高通量工程试验堆堆芯流量分配计算
The Study on 80 Fuel Assemblies Core for HFETR
高通量工程试验堆80盒元件堆芯研究
Design of Core Vessel and Core Structure in China Advanced Research Reactor
中国先进研究堆堆芯容器及堆内构件设计研究
Safety Analysis for Xi’an Pulsed Reactor in Pulse Operation Mode with the Core in Steady Arrangement and Design Project for the New Core Arrangement
西安脉冲堆稳态堆芯脉冲运行安全性分析及新堆芯布置方案设计
Further, graphite cores may be safer than non-graphite cores under some accident scenarios.
再者，根据一些事故解说，石墨堆芯可比非石墨堆芯更安全一些。
it had a graphite core and no containment structure.
这些反应堆有一个石墨堆芯，没有外壳结构。
Measurements for monitoring adequate cooling within the core of pressurized light water reactors
GB/T13632-1992监督压水堆堆芯充分冷却的测量要求
In-core instrumentation for neutron fluence rate measurements in nuclear reactors
GB/T8995-1988核反应堆中子注量率测量堆芯仪表