1.
Feasibility Research on Advanced PWR for Steam-Water Flow Injector
增压换热器在先进压水堆应用的可行性研究
2.
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
3.
Out-of-Pile Hydraulic Stability Test of China Advanced Research Reactor Standard Fuel Assembly
中国先进研究堆标准燃料组件堆外水力稳定性试验
4.
Research and Design on Fuel Bundle of Advanced Heavy Water Reactor;
先进重水反应堆燃料棒束物理研究与设计
5.
Nuclear Power Plant Simulation System and Its Improvement Based on PCTRAN;
基于PCTRAN的压水堆核电站模拟仿真系统及其改进
6.
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
7.
burnable poison pressurized water reactor
可燃毒物压水反应堆
8.
natural circulation pressurized water reactor
自然循环压水反应堆
9.
The Nuclear Core Design of 450MWt Pressurized Water Reactor
45万千瓦(热)压水堆堆芯核设计
10.
Study on Krylov Subspace Method and the Flux Mapping for Advanced Candu Reactor
Krylov子空间方法及先进重水堆在线通量拟构方法初步研究
11.
Nozzle Loads Optimizing of Inlet Primary Loop Piping in China Advanced Research Reactor
中国先进研究堆主回路进堆管系接管载荷优化
12.
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
13.
Measures and Characteristics of Cooling at Shutdown Mode for China Advanced Research Reactor
中国先进研究堆停堆冷却措施及其主要特点
14.
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。
15.
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
16.
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
17.
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
18.
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