power reactor
美 
英
- n.动力反应炉
- 网络动力堆；动力反应堆；原子动力反应堆
英汉解释
例句
It is pressing for U. S. permission to recycle plutonium from spent power-reactor fuel, originally supplied by the United States.
它迫切要求美国同意，可以从动力反应堆乏燃料中回收钚——这些乏燃料起初是由美国供应的。
At present, the pressurized water reactor and boiling water nuclear power reactor in the largest proportion.
在目前，核电站中以压水堆和沸水堆所占的比例最大。
Hence the fears over Iran, which claims to need an industrial-scale enrichment plant without having a single working power reactor.
因此，当伊朗宣称需要一套工业规模的浓缩装置，而不只是简单运转的电力级核反应堆之时，对该国的诸多担忧应运而生。
Because of increasing burnup of power reactor, more advanced technologies should be applied in the reprocessing of spent nuclear fuel.
由于核电站动力堆乏燃料的燃耗深，对乏燃料后处理工艺技术提出了更高要求。
Its initials, in Russian, stand for "water-water-power-reactor. "
VVER是俄语“水-水-电-反应堆”的首字母缩写。
Iran's Press TV quoted Salehi as saying that the Bushehr nuclear power reactor will be May 5 to 10 to enter between the critical state.
伊朗新闻电视台援引萨利希的话说，布什尔核电站核反应堆将在5月5日至10日之间进入临界状态。
The 3 million people of landlocked Armenia are unique in their energy dependence on one aging nuclear power reactor.
拥有300万人口的这个内陆国，唯一的能源依靠就是一座正在老化的核电站。
In addition, the No. 2 nuclear power reactor cooling system has stopped working, the Government is taking the way into the water to cool.
此外，核电站的2号反应堆冷却系统也已停止工作，政府正在采取注入海水的方式进行冷却。
Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification, Guide for
核分析鉴定用参考动力反应堆物理测量的数据获得及文献工作指南
In-core temperature or primary envelope temperature measurements in nuclear power reactor - Characteristics and test methods
核动力堆堆芯或堆主包壳内温度测量特性和测试方法
standard practice for evaluation of surveillance capsules from light - water moderated nuclear power reactor vessels
评价轻水核电反应堆监视舱的标准实施规程
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
为轻水冷却核反应堆容器的实施监视试验
Measurements of Neutron Spectra and Doses Inside and Outside the Containment of a Power Reactor
核动力堆安全壳内外中子能谱和剂量测量
Status and development of instrumented fuel rod testing simulating the power reactor operating conditions in the research reactor MIR
中模拟动力堆运行工况下受测燃料棒考验的现状和发展
Natural and External Man-Made Hazards at Power Reactor Sites, Guidelines for Combining
核动力反应堆现场内在的与外部人为危险综合考虑导则
Determining Design Basis Flooding at Power Reactor Sites
核反应堆场所的溢流设计基础的测定
PRISM (Power Reactor Inherently Safe Module)
动力[反应]堆固有安全模件
Economic Risks of Nuclear Power Reactor Accidents
核动力反应堆事故的经济风险分析
saline water conversion power reactor plant
海水淡化核动力厂
The Current Status and Future Development of Small Nuclear Power Reactor
小型核电反应堆的现状及未来发展
Development of low-strain resistant fuel for power reactor fuel rods
动力堆燃料棒抗低应变燃料的研制
