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 paper presents the developing tendency of PWR NPP briefly.

文中简要介绍了国外压水堆核电站的发展趋势。

The application of MOX fuel in China's PWR is discussed in the end.

探讨了MOX燃料在国内压水堆核电站中的应用问题。

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。

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。

The effect of condensation reflux model in PWR LOCA analyses was investigated.

研究了冷凝回流在压水堆中破口失水事故中的作用。

This paper described benchmark test noise signal analysis of PWR and gets some useful results.

本文介绍了压水堆噪声基准试验信号分析，并从中得出一些有用的结果。

The nuclear reactor coolant pump (RCP) is one of the core equipments in PWR nuclear Power Plant.

核主泵是压水型反应堆核电站中的核心设备之一。

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。

This Paper Presents analysis of the stationary and transient behaviours of natural circulation PWR.

本文对完全自然循环压水堆装置的稳态和动态特性进行了分析。

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。

The experimental results are useful for rational selecting parameters of containment spray system of PWR.

实验结果可用于合理选择压水堆安全壳喷淋系统参数。

This paper briefly describes the siting of Qingshan Nuclear Power Plant, the first 300MW PWR unit of China.

本文简要介绍了我国第一座300MW压水堆型核电站——秦山核电厂的厂址选定情况。

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。

The three dimensional potential flow theory is applied to the analysis of the steady flow field of PWR upper Plenum.

本文将三维势流理论应用于压水堆上腔室稳态流扬分析。

Considering fuel assembly for PWR, it is possessed of dense lattice, complex geometry and strong absorption of neutron.

对于压水堆燃料组件而言，栅格稠密、几何形状复杂，对中子的吸收较强。

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。

This paper presents an one-dimensional homogeneous flow model for thermal-hydraulic transient behaviour of PWR steam generators.

本文介绍了压水堆核电厂蒸汽发生器的一维均相流瞬态分析模型。

This model can be used to analyze thermal-hydraulic transient behaviour of inverted U-tube steam generators in PWR power plants.

该模型可用于分析压水堆核电厂U型管自然循环式蒸汽发生器的热工水力瞬态过程。

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 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。

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。

The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant).

压水堆核电厂反应堆冷却剂系统自然循环能力是这种类型核电厂固有的安全性之一。

After having completed the model analysis of the pressurized water reactor (PWR) core barrel in an 1:10 model, the dynamic characteristics are obtained.

在反应堆1：10模型上进行了堆芯吊篮结构的空气和静水中模态分析试验，获得动态特性。

After having completed the model analysis of the pressurized water reactor (PWR) core barrel in anl: 10 model, the dynamic characteristics are obtained.

在反应堆1：10模型上进行了堆芯吊篮结构的空气和静水中模态分析试验，获得动态特性。

The paper presents status of failure incidents of PWR steam generator heat transfer tubes in Japan as well as causes of failure and measures used for protection.

本文介绍日本压水堆核电站蒸汽发生器传热管破损情况，破损原因和防止传热管破损的措施。

From the point of view of design, this article briefly introduces construction, tube material and water-treatment system for PWR steam generators in the Soviet Union.

本文仅从设计角度出发，摘要介绍苏联压水堆蒸汽发生器的结构、选材和水化学制度等方面的问题。

The loss of efficient head of circulation pump in the primary loop of PWR will increase with the increase of resistance coefficient of JetPump under forced circulation.

强迫循环条件下，压水堆一回路主循环泵有效压头的损失随喷射泵阻力系数的增加而增加；