标准化核电站系统(简称SNUPPS)是西屋电气公司建造的众多压水反应堆之一。
SNUPPS, or Standardized Nuclear Unit Power Plant System, is one of a series of pressurized-water reactors built by Westinghouse.
潜艇推进系统据信是核、涡-电布置，包括一台压水反应堆（PWR）组成，采用单驱动轴。
The submarine's propulsion system is believed to be nuclear, turbo-electric arrangement, consisting of one pressurised water reactor (PWR), with one shaft.
按照最优控制理论，把压水反应堆的负荷跟踪控制问题描述为一个非线性二次型最优控制问题。
According to the optimal control theory, the problem of load following operation in a pressurized water reactor is formulated as a nonlinear quadratic optimal control problem.
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。
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.
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。
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.
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。
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.
本文叙述了应用于控制压水反应堆反应性的中子吸收法测量硼浓度原理，介绍了硼浓度的测量方法，并对硼浓度与计数率的关系曲线进行了测量。
This paper discusses the neutron absorption principle of measuring the boron concentration, which is to control the reactivity of the pressurized-water reactor.
压水反应堆堆内温度测量装置是监测反应堆热功率输出及堆内功率分布情况、保证反应堆安全运行的手段之一。该装置以热电偶作为测量元件，用不锈钢作保护外套。
The PWR in-core temperature detection device, which is one of measures to ensure reactor safety operation, is to monitor and diagnose reactor thermal power output and in-core power distribution.
这两个俄制VVER-91压水核反应堆能够发电1060兆瓦。
The two Russian-built VVER-91 pressurised water reactors each has outputs of 1, 060MW.
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 one is the familiar one, inadvertent opening of a pressurised safety or relief valve in a PWR or a safety valve in a BWR.
在压水式反应堆里，热水在高压下通过钢管循环，金属离子不断从管壁上溶解到水中。
In a pressurised-water reactor, hot water circulates at high pressure through steel piping, dissolving metal ions from the walls of the pipes.
现在，我们回顾一下沸水式反应堆，我们会做一个压水式反应堆。
Now let me go over boiling water reactors and then we'll do pressurised water reactors.
在一个压水式反应堆里，我们用硼来控制反应率。
Now in a PWR we have essentially boron to control reactivity.
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。
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.
现在，两种在美国很普遍的类型，是压水式反应堆和沸水式反应堆。
Now the two types that are common in the United States are the pressurised water and the boiling water.
在反应堆安全中，他们观察可能产生问题的，事件，初始的事件在压水式反应堆的领域里。
In reactor safety they look events that can create problems, initiating events in PRA world.
我想要着重在沸水反应堆，也压水式反应堆。
And I wanna focus in on the boiling water reactor and the pressurised water reactor.
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 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.
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。
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.
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。
In a PWR the pressure of the water is about two thousand pounds which prevents boiling in the core.
当1969年开始建设时，Metsamor用的是VVER440型230反应堆，最早的压水堆核电站的设计样板之一，是由苏联在1956年- 1970年间开发的。
When construction began in 1969, Metsamor was a VVER 440, Model 230, an example of one of the earliest pressurized-water nuclear plant designs, developed by the Soviets between 1956 and 1970.
压水堆核电站反应堆功率的控制是通过调节控制棒和硼浓度来实现的。
The control of the pressurized-water reactor's power is transited by accommodate -ting the control rod and boron concentration.
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。
The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant).
核主泵是压水型反应堆核电站中的核心设备之一。
The nuclear reactor coolant pump (RCP) is one of the core equipments in PWR nuclear Power Plant.
压水堆核电站依靠控制棒实现反应堆功率的快速调节和特殊情况下的紧急停堆。
The control rods are used to implement quick regulation of the reactor power and emergent shutdown of the reactor in pressurized water nuclear power station.
高温气冷堆主氦风机与压水堆主泵一样，均为反应堆一回路的关键设备。
Both the primary helium circulator for high-temperature gas-cooled reactor (HTR) and the primary pump for the pressurized-water reactor are the key components in the reactor primary loop.
高温气冷堆主氦风机与压水堆主泵一样，均为反应堆一回路的关键设备。
Both the primary helium circulator for high-temperature gas-cooled reactor (HTR) and the primary pump for the pressurized-water reactor are the key components in the reactor primary loop.
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