power reactor
美
英 
- n.動(dòng)力反應(yīng)爐
- 網(wǎng)絡(luò)動(dòng)力堆;動(dòng)力反應(yīng)堆;原子動(dòng)力反應(yīng)堆
英漢解釋
例句
It is pressing for U. S. permission to recycle plutonium from spent power-reactor fuel, originally supplied by the United States.
它迫切要求美國(guó)同意,可以從動(dòng)力反應(yīng)堆乏燃料中回收钚——這些乏燃料起初是由美國(guó)供應(yīng)的。
At present, the pressurized water reactor and boiling water nuclear power reactor in the largest proportion.
在目前,核電站中以壓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,當(dāng)伊朗宣稱需要一套工業(yè)規(guī)模的濃縮裝置,而不只是簡(jiǎn)單運(yùn)轉(zhuǎn)的電力級(jí)核反應(yīng)堆之時(shí),對(duì)該國(guó)的諸多擔(dān)憂應(yīng)運(yùn)而生。
Because of increasing burnup of power reactor, more advanced technologies should be applied in the reprocessing of spent nuclear fuel.
由于核電站動(dòng)力堆乏燃料的燃耗深,對(duì)乏燃料后處理工藝技術(shù)提出了更高要求。
Its initials, in Russian, stand for "water-water-power-reactor. "
VVER是俄語“水-水-電-反應(yīng)堆”的首字母縮寫。
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.
伊朗新聞電視臺(tái)援引薩利希的話說,布什爾核電站核反應(yīng)堆將在5月5日至10日之間進(jìn)入臨界狀態(tài)。
The 3 million people of landlocked Armenia are unique in their energy dependence on one aging nuclear power reactor.
擁有300萬人口的這個(gè)內(nèi)陸國(guó),唯一的能源依靠就是一座正在老化的核電站。
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,核電站的2號(hào)反應(yīng)堆冷卻系統(tǒng)也已停止工作,政府正在采取注入海水的方式進(jìn)行冷卻。
Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification, Guide for
核分析鑒定用參考動(dòng)力反應(yīng)堆物理測(cè)量的數(shù)據(jù)獲得及文獻(xiàn)工作指南
In-core temperature or primary envelope temperature measurements in nuclear power reactor - Characteristics and test methods
核動(dòng)力堆堆芯或堆主包殼內(nèi)溫度測(cè)量特性和測(cè)試方法
standard practice for evaluation of surveillance capsules from light - water moderated nuclear power reactor vessels
評(píng)價(jià)輕水核電反應(yīng)堆監(jiān)視艙的標(biāo)準(zhǔn)實(shí)施規(guī)程
Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
為輕水冷卻核反應(yīng)堆容器的實(shí)施監(jiān)視試驗(yàn)
Measurements of Neutron Spectra and Doses Inside and Outside the Containment of a Power Reactor
核動(dòng)力堆安全殼內(nèi)外中子能譜和劑量測(cè)量
Status and development of instrumented fuel rod testing simulating the power reactor operating conditions in the research reactor MIR
中模擬動(dòng)力堆運(yùn)行工況下受測(cè)燃料棒考驗(yàn)的現(xiàn)狀和發(fā)展
Natural and External Man-Made Hazards at Power Reactor Sites, Guidelines for Combining
核動(dòng)力反應(yīng)堆現(xiàn)場(chǎng)內(nèi)在的與外部人為危險(xiǎn)綜合考慮導(dǎo)則
Determining Design Basis Flooding at Power Reactor Sites
核反應(yīng)堆場(chǎng)所的溢流設(shè)計(jì)基礎(chǔ)的測(cè)定
PRISM (Power Reactor Inherently Safe Module)
動(dòng)力[反應(yīng)]堆固有安全模件
Economic Risks of Nuclear Power Reactor Accidents
核動(dòng)力反應(yīng)堆事故的經(jīng)濟(jì)風(fēng)險(xiǎn)分析
saline water conversion power reactor plant
海水淡化核動(dòng)力廠
The Current Status and Future Development of Small Nuclear Power Reactor
小型核電反應(yīng)堆的現(xiàn)狀及未來發(fā)展
Development of low-strain resistant fuel for power reactor fuel rods
動(dòng)力堆燃料棒抗低應(yīng)變燃料的研制