英英释义
noun
- a nuclear reactor that uses water as a coolant and moderator
Synonym: pressurized water reactor
- And you'll also note in a PWR we have three different cooling systems; the primary, the secondary and the third system which is the system that actually goes into the environment.
你们也会注意到在压水式反应堆里有，3个不同的冷却系统，主要的，第二个，还有第三个系统，那是系统，会真的进入到环境中去。 - PWR nuclear power plant; the secondary circuit; economy; diagnosis;
压水堆；二回路；经济性；诊断； - The main factor of localization of nuclear island major equipment of PWR nuclear power plant& Large forgings
压水堆核电厂核岛主设备国产化关注点&大型锻件 - Control rods are used in a PWR typically to change the power level and also to shut down the reactor.
控制棒是在一个加压水冷却反应堆里使用的，用来改变能量的级别，也可以用来停止反应堆。 - Radioactive source term of PWR nuclear power plant for operational states
GB/T13976-1992压水堆核电厂运行工况下的放射性源项 - Now typically in a PWR this is typically a configuration for a PWR.
现在在压水式反应堆里，这是个典型的，结构，对一个压水式反应堆来说。 - 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 - Simulation of Dynamic Characteristics of Power Regulation System of PWR
压水堆功率调节系统动态特性仿真研究 - Preliminary study on thorium-uranium fuel cycle in the equilibrium core of PWR
零功率反应堆响应函数压水堆平衡堆芯钍铀燃料循环初步研究 - Calculation of PWR Neutron Pulse Count Rate and Analysis Method for Weak Source Area
压水堆中子脉冲计数率计算与弱源启动分析方法 - 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。 - In addition, due to temperature and poisoning negative feedbacks, PWR NPP can withstand certain disturbances including step power.
此外，由于压水堆的负温度效应，核电机组可承受一定的外部干扰和功率阶跃。 - And clearly, many different types of fuel assemblies, as you will see a BWR and PWR fuel assemblies are different and all heat that is generated in that one fuel pin needs to be removed.
还有很清楚地，许多不同种的燃料组件，如你们会在一个沸水型，和加压水式反应堆看到的，燃料组件是不同的，所有产生在一个燃料针的，热量都需要除去。 - Common Cause Failures Analysis of PWR Purification System Based on GO Methodology
基于GO法的压水堆净化系统共因失效分析 - Neutron Physical Characteristics of Light Water Cooled Blanket of Fusion-Fission Hybrid Reactor The hybrid breeders can provide plenty of fissile material for PWR or FBR.
聚变-裂变混合堆水冷包层中子物理性能研究聚变-裂变混合堆可以为压水堆或快堆提供充足的核燃料。 - They did some research, they did some preliminary analysis and they basically had the BWR people fix certain things but they concluded that it was kind of okay for PWRs back at that time.
他们做了些研究，他们做了一些前期的，分析，他们让BWR的人修理，某些东西，但是他们总结出来，它对PWR当时没问题的，在当时。 - In this paper we deduce a series of formulae for the specific activity of the corrosion products in PWR coolant, conducting calculation and analysis, and proving foreign related data.
本文推导了一套反应堆冷却剂腐蚀产物比活性的计算公式，进行了计算分析，验证了国外有关参考数据； - In a PWR the pressure of the water is about two thousand pounds which prevents boiling in the core.
在压水式反应堆中，水的压力则是，2000磅，这避免了水在核心处沸腾。 - Now in a PWR we have essentially boron to control reactivity.
在一个压水式反应堆里，我们用硼来控制反应率。 - There exists probability of fuel assembly damage in PWR during refueling period.
在压水堆核电站换料的过程中存在燃料棒破损的可能。 - This one is the familiar one, inadvertent opening of a pressurised safety or relief valve in a PWR or a safety valve in a BWR.
这一个是很熟悉的，增压安全阀的疏忽打开，或者是在压水式反应堆的减压阀，或者是在沸水式反应堆的安全阀。 - Simulation Model of Natural Circulation in PWR Coolant System under Ocean Conditions
海洋条件下冷却剂系统自然循环仿真模型 - Design and Test of Westinghouse PWR Steam Generators
西屋公司压水堆核电站蒸汽发生器的设计与试验 - This is a very important design difference between a BWR and a PWR. So, BWR fuel assemblies are essentially canned to make sure we have an adequate supply of cooling water.
这是个沸水式反应堆和压水式反应堆的，设计上的重要区别，沸水型反应堆的燃料组件，是罐装起来确保我们得到，的冷水的供应足够。 - Application of GO-FLOW Methodology to RHS Reliability Analysis in PWR
GO-FLOW法在压水堆余热排出系统可靠性分析中的应用 - Investigation on Basic Equations and Scaling Criteria of PWR Natural Circulation
压水堆自然循环比例模化基本方程及相似准则数的研究 - 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。 - The design and construction rules applicable to mechanical components of PWR Nuclear Islands ( RCC-M) are a part of the collection of design and construction rules for nuclear power plants.
压水堆核岛机械设备的设计和建造规则（RCC-M）是核电厂设计和建造规则系列规范之一。 - Controlled recirculation boiling water reactor Study on Scaling Law of PWR Natural Circulation with Motion Condition
可控再循环沸水反应堆运动状态下压水堆自然循环比例模拟方法研究 - The high-pressure core melt accidents in PWR nuclear power plant which cover most of the severe accidents, have large potential risk.
压水堆核电厂的高压熔堆事故覆盖了大部分的严重事故序列，且具有很大的潜在威胁。