... pressurized gas 压缩气体 pressurized water reactor 压水型堆 presswork 冲压制品 ...
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第三代大型压水堆核电技术 the third-generation pressurized-water reactor (PWR) nuclear power generation
先进型压水堆 APWR ; Advanced Pressure Water Reactor
大型压水堆 large pressurized water reactor
在先进型压水堆 Advanced Pressure Water Reactor ; APWR
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.
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.
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 model can be used to analyze thermal-hydraulic transient behaviour of inverted U-tube steam generators in PWR power plants.
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