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 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。
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。
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。
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。
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 UO2 fuel is normally enriched with 3-5% of U235. The uranium alloy has been enriched to contain up to 90% U235, but is normally used at between 45-75% U235 enrichment in PWR for ships propulsion.
UO 2一般内含3- 5%的U235，而铀合金经过浓缩则含有90%的U235，但是船用推进器一般使用U 235含量为45 - 75%的浓缩铀。
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。
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。
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 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。
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。
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。
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。
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 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。
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。
There are four types for PWR pressure-relieving devices: direct acting safety valve, pilot-operated pressure relief valve, power-operated pressure relief valve and safety valve with auxiliaries.
PWR的压力释放装置主要有四种类型：直接作用式安全阀、先导操作压力释放阀、动力作用式压力释放阀和具有辅助装置的安全阀。
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。
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。
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。
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。
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。
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。
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 results show that heaving has less effect upon the primary Loop's coolant flow rate and PWR output power in case of forced circulation but strongly influences natural circulation ability.
结果表明：起伏对强制循环下一回路冷却剂的流量和反应堆输出功率的影响较小，而对自然循环能力的影响很大。
In order to carry out power transient tests for PWR fuel element in China Advanced research Reactor (carr), the research and conceptual design of 3he pressure control loop were completed.
为使中国先进研究堆(CARR)具备开展压水堆燃料瞬态试验的能力，本工作对氦- 3回路进行研究与初步设计。
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。
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；
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