1.
The Nuclear Core Design of 450MWt Pressurized Water Reactor
45万千瓦(热)压水堆堆芯核设计
2.
External Reactor Vessel Cooling Measure in Severe Accident for Pressurized Water Reactor Nuclear Power Plant
压水堆核电厂严重事故下堆腔注水措施研究
3.
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。
4.
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
5.
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
6.
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
7.
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
8.
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
9.
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
10.
The hybrid breeders can provide plenty of fissile material for PWR or FBR.
聚变-裂变混合堆可以为压水堆或快堆提供充足的核燃料。
11.
Helium leak testing of nuclear fuel rod for PWR
GB/T11813-1996压水堆燃料棒氦质谱检漏
12.
Metallographic examination for weld seam of nuclear fuel rod used in PWR
GB/T11809-1998压水堆核燃料棒焊缝金相检验
13.
Guide to design of nuclear fuel rods for PWR
GB/T11925-1989压水堆核燃料棒设计导则
14.
Classification for the items of pressurized water reactor nuclear power plants
GB/T17569-1998压水堆核电厂物项分级
15.
Development of New Zirconium Alloys for PWR Fuel Rod Claddings
压水堆燃料包壳新锆合金的发展(英文)
16.
A Cold Stepping Driving Experiment for a Control Rod Drive Line of PWR
压水堆控制棒驱动线的冷态步跃试验
17.
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
18.
Trip analysis and online diagnosis regulation for loosing water level control of the PWR steam generator
压水堆蒸发器水位调节失控跳堆分析及在线诊断调整