1.
The Nuclear Core Design of 450MWt Pressurized Water Reactor
45万千瓦(热)压水堆堆芯核设计
2.
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
3.
Modeling and Simulation of the PWR Core and Its Control Systems;
压水堆堆芯系统建模及其控制系统仿真研究
4.
Preliminary study on thorium-uranium fuel cycle in the equilibrium core of PWR
压水堆平衡堆芯钍铀燃料循环初步研究
5.
Optimization of BurnablePoison Assignment for PWRLow Leakage Reload Core
压水堆低泄漏换料堆芯可燃毒物的优化配置
6.
Radiant Deformation of PWR AFA17×17 Fuel Assembly and Core Loading of Deformed Fuel Assembly;
压水堆AFA17×17燃料组件辐照变形及其堆芯装料
7.
Simulation of Dynamic Mathematical Modeling for PWR Nuclear Power Plant Core Based on PSASP
基于PSASP的压水堆核电站堆芯建模及仿真研究
8.
The comparison of the computational results for reactor core of PWR and BWR are also presented.
文中还给出了压水堆和沸水堆堆芯计算实例的比较。
9.
Study of Boron Poisoning Experiments on Advanced PWR Zero-Power Core with Steel-Water Reflector Assembly
先进压水堆铁水反射层组件零功率堆芯硼中毒实验研究
10.
core spray heat exchanger booster pump
堆芯喷淋热交换讫压泵
11.
The Principle and methodology of pressurized water reactor nuclear power plant core power capability verification for reload are introduced.
介绍了压水堆核电厂换料堆芯功率能力验证分析的原理和方法。
12.
The Person-Computer Simulation And Demonstrate platform Research on PWR Nuclear Power Plant Physics-Running;
压水堆核电站运行堆芯物理过程的PC仿真和演示平台研制
13.
Manufacturing of Nuclear Fuel Assembly for PWR and Study for the Fuel Pellets with Central Hole;
压水堆核燃料制造及中孔环形燃料芯块的研制
14.
A THERMAL-HYDRAULIC MODEL FOR BWR SIMULATORS
沸水堆堆芯模拟程序中的热工-水力模型
15.
Single Assembly Preliminary Analysis for Horizontal Seismic Analysis on Fast Breeder Reactor Core
快堆堆芯水平抗震分析的单组件初步分析
16.
A REWETTING MODEL DURING CORE BOTTOM UP REFLOOD PROCESS AFTER PWR LOCA;
失水事故中反应堆堆芯再淹没数学模型
17.
Coupled Thermal-Hydraulics and Neutron-Physics Analysis of Supercritical Water Cooled Reactor With Mixed Spectrum Core
混合能谱超临界水堆堆芯热工-物理性能分析
18.
reactor core radiation detector
反应堆堆芯辐射检测仪