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.
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，沸水型反应堆的燃料组件是和特殊的，因为在核心的地方已经沸腾了，那就需要一个保险措施，能让每一个，燃料组件都能冷却并且得到水。
Now BWR fuel assembly is unique in the sense that because we have boiling going on in the core there needs to be some assurance that every fuel assembly is getting coolant and getting water.
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。
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.
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.
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.
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.
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