1.
A Matrix Analytic Method for the Second Loop Thermodynamic System of a Pressurized Water Reactor-based Nuclear Power Plant
压水堆核电机组二回路热力系统矩阵分析法
2.
Research on unified models of heat-economic analysis for PWR nuclear power plants
压水堆核电机组二回路热力系统热经济性分析统一模型的研究
3.
Research on the Unified Physical Model and the Mathematic Model of Heat-economic Analysis for PWR Nuclear Power Plant
压水堆核电机组二回路热力系统热经济性分析统一物理模型和数学模型
4.
Furthermore, this article introduces the techniques to ensure the water vapor quality in secondary circuit of PWR.
还介绍了保证压水堆核电站二回路水汽质量的措施。
5.
Optimization of Leakage Calculation in RCP System of PWR
压水堆核电厂一回路冷却剂泄漏率计算的优化
6.
Effect of Natural Circulation on RCS Depressurization Strategy in PWR NPP
压水堆核电厂自然循环对一回路卸压策略的影响
7.
Design rules for mechanical components of pwr nuclear islemds
GB/T16702-1996压水堆核电厂核岛机械设备设计规范
8.
STUDY ON COMPUTATIONAL MODELS OF SECONDARY SOURCE TERMS FOR NORMAL OPERATION OF CPR1000 NUCLEAR POWER PLANTS
CPR1000核电机组二回路系统稳态运行期间的放射性源项计算
9.
The Study of Secondary Water Chemistry Problem for Qinshan Ⅱ NPP;
秦山第二核电厂二回路水质问题及对策研究
10.
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
11.
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
12.
The Application of Ethanolamine in Secondary Water Chemistry for Steam Generator in Nuclear Power Plants;
缓蚀剂ETA在核电站二回路水处理中应用研究
13.
Classification for the items of pressurized water reactor nuclear power plants
GB/T17569-1998压水堆核电厂物项分级
14.
This comprises two 985MW pressurised water reactors which went into commercial operation in February and May 1994, respectively.
大亚湾核电站设有两座985兆瓦压水式反应堆，这两座反应堆分别于一九九四年二月及五月投产。
15.
Research on Two-dimensional Inertial Piezoelectric Actuator Driven by Piezoelectric Stack
叠堆驱动二维惯性压电驱动机构研究
16.
The Effect of Primary Water Chemistry on the Integrity of Nuclear Fuel Cladding Tube;
压水堆一回路水化学对燃料包壳完整性的影响
17.
Vibratory examination testing on anti-looseness performance of PWR internal fasteners
压水堆核电厂堆内构件联接件防松性能振动考核试验
18.
Design of Reactor Pressure Vessel for Qinshan Phase II NPP Project
秦山核电二期工程反应堆压力容器设计