PWR:压水堆
压水反应堆(Pressurized Water Reactor,简称PWR)是核能领域常用的反应堆类型之一,因其结构安全、技术成熟而被广泛应用于核电站。为便于书写和交流,“PWR”成为其常见缩写形式,多见于核电工程、学术文献及综合技术资料中。
Pressure Water Reactor具体释义
Pressure Water Reactor的英文发音
例句
- The utility model relates to the field of nuclear fuel components, in particular to an upper tube seat of a pressure water reactor fuel element.
- 本实用新型涉及核燃料元件领域,具体涉及一种压水堆(PWR)燃料组件上管座。
- Through research and test, the self-reliance manufacturing for the core barrel of pressure water reactor internals has been realized.
- 通过攻关试验,实现了压水堆(PWR)吊篮筒体国产化。
- Meanwhile, the four corners are respectively and symmetrically provided with positioning pin holes, so that the assembly of the pressure water reactor fuel element can be more flexible and convenient.
- 同时,在四角位置分别对称布置定位销孔,从而使压水堆(PWR)燃料组件的安装更加灵活方便。
- The momentum integral method is applied in the frame of safety analysis of pressure water reactors under hypothetical loss of coolant accident ( LOCA ) conditions to simulate numerically film condensation, rewetting and vaporization on the inner surface of a pressure water reactor containment.
- 采用动量积分方法分析压水堆(PWR)发生失水事故时在安全壳的内表面上的液膜凝结、再浸润和蒸发过程。
- Conceptual study of passive residual heat removal system of a pressure tube water reactor
- 压力管式反应堆非能动余热排出系统方案研究
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