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。
The departure from nucleate boiling (DNB) is important concerning about the safety of a PWR.
偏离泡核沸腾(DNB)对于压水堆安全具有重要意义。
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。
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。
A process for development of the Pilot Type HTHP Solenoid Valve used in a PWR power plant is described in this paper.
本文介绍了一种用于压水堆动力装置的间接操作式高温高压电磁阀的开发过程。
So the big difference between a PWR and BWR is that a BWR has a built in suppression pool for the steam that maybe released.
所以加压水反应堆和沸水反应堆的不同，就是沸水反应堆的在抑压池里有个装置，使得蒸汽能够释放出来。
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。
These pictures are hard to come by these days because of 9/11. Now pressurised water reactors are different and this is the schematic of a PWR.
这些图片现在很难得到,由于911事件，现在压水式反应堆,是不同的，这是它的原理图。
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。
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。
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。
This prensentation mainly analyzes the transient of uncontrolled RCCAwithdrawal from a subcritical or low power condition for PWR.
本文主要分析压水堆在次临界或低功率下发生的失控提捧事故的瞬态特性。
The key safety problem of a steam generation of PWR nuclear power plant is its instrumentation and control of water level, thus the reliability and safety is most important.
压水反应堆核电厂的蒸汽发生器的关键安全性问题就是其液位的仪表检测及控制问题，因此其可靠性与安全性就是极重要的因素。
Presented is a model for the multi region and variable node PWR core.
建立了多区变节点压水堆堆芯的数学物理模型。
Nuclear fuel elements containing dry process nuclear fuel pellets for the irradiation test in a reactor were remotely fabricated from spent PWR fuel materials in a hot cell.
包含用作反应堆中放射测试的干处理核燃料球体的核燃料元件，是由在热单元中的压水反应堆燃料远程制造的。
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。
The seismic response analysis and experimental study of a model PWR steam generator tube bundle has been completed.
完成了压水堆蒸汽发生器管束模拟体的地震响应水分析和试验研究。
As a dynamic equipment in the PWR units, the reliability of the pumps is key to the security of whole nuclear power station.
作为压水堆核电机组中的水力能动设备，泵类产品的可靠性对整个核电站的安全起着及其关键的作用。
Calculating source terms of pressure water reactor (PWR) that are time-related and of a lot of isotopes and their intensity.
计算压水堆与时间相关的、大量同位素的源项及其强度。
MR-100G and MR-1G, the power supply system for district heating and cooling, are a self-pressurized, nature circulated integral PWR.
MR-100G和MR-1G是专门为区域供热和冷却系统提供能源、一回路系统自加压的全自然循环一体化压水堆。
On the primary and secondary steam separator with a water defector in a steam generator for PWR;
本文对波形板汽水分离器进行了数值模拟和试验研究。
On the primary and secondary steam separator with a water defector in a steam generator for PWR;
本文对波形板汽水分离器进行了数值模拟和试验研究。
应用推荐