nuclear power reactor 中文意思是什麼

nuclear power reactor 解釋
核動力反應堆
  • nuclear : adj 1 核的,成核的;有核的。2 【物理學】原子核的;原子能的;原子彈的;核動力的。3 〈比喻〉核心的...
  • power : n 1 力,力量;能力;體力,精力;(生理)機能;〈常 pl 〉才能。2 勢力,權力,權限;威力;政權;權...
  • reactor : n. 1. 反應者,被試驗者;【醫學】有(陽性)反應的人[動物]。2. 【電學】礙圈,扼流圈;電抗器;【化學】反應器;【物理學】反應堆。
  1. Nuclear power station with pressurised water reactor is basically divided into the " nuclear island " where steam is produced in the steam generator by nuclear power generated from a reactor, a " conventional island " where steam supplied from the nuclear island is used to drive the turbine - generator to produce electricity, and the balance of plant ( bop ) which consists of the station auxiliaries and ancillary plants, etc

    採用壓水式反應堆的核電站基本分為核島、常規島和核電站其他部分。由反應堆產生的核能會通過在核島內的蒸汽發生器產生蒸汽,而核島所供應的蒸汽會推動常規島內的渦輪發電機發電。核電站其他部分則包括站內的輔助設備及附屬設施等。
  2. Nuclear power station with pressurised water reactor is basically divided into the " nuclear island " where steam is produced in the steam generator by nuclear power generated from a reactor, a " conventional island " where steam supplied from the nuclear island is used to drive the turbine - generator to produce electricity, and the balance of plant which consists of the station auxiliaries and ancillary plants, etc

    採用壓水式反應堆的核電站基本分為核島常規島和核電站其他部分。由反應堆產生的核能會通過在核島內的蒸汽發生器產生蒸汽,而核島所供應的蒸汽會推動常規島內的渦輪發電機發電。核電站其他部分則包括站內的輔助設備及附屬設施等。
  3. Along with the development of nuclear power technology in china, it is necessary to develop the fast breeder reactor ( fast reactor ) through own efforts

    摘要隨著我國核電技術的發展,自主研製鈉冷快中子增殖堆十分必要。
  4. As a important part of the nuclear power plant simulation, reactor coolant system simulation research is of great significance

    作為核動力裝置培訓模擬器的重要組成部分,冷卻劑系統的模擬計算研究具有很重要的意義。
  5. The reactor coolant system is an important system of nuclear power plant, so simulation of reactor coolant system is an important part of nuclear power plant simulation

    主冷卻劑系統是核動力裝置的一個重要系統,對主冷卻劑系統的模擬研究是核動力裝置模擬研究的一個重要部分,具有非常重要的意義。
  6. The simulation of reactor physics and nuclear power plant system running using person - computer help for students studying the nuclear engineering course as well as the workers of nuclear power plant training

    用計算機對反應堆物理及核電站系統運行進行模擬,既有助於核工程專業的學生專業課的學習,也適合核電人員的初步培訓。
  7. Nuclear power station using pressurised water reactor

    採用壓水式反應堆的核電站
  8. The reactor at the nuclear power station went critical

    核電站反應堆處警戒狀態
  9. The aim of this research project is to supply the technical preparation for the nuclear power station domestalization and autonomous design, to improve the design quality and level, to ensure the reliability of the sealing system in the advanced pressurized water reactor vessel, to ensure the nuclear safety, and to raise the design software level of the nuclear vessel sealing system to the advanced world class

    本課題研究的目的是為核電站國產化及自主設計提供技術準備,提高設計質量和設計水平,確保先進壓水堆核容器密封系統設計的可靠性,確保核安全,使核容器密封設計軟體達到世界先進水平。
  10. This paper will discuss project feasibility study, investment estimating, operating costs estimating, selling income and tax, finical analysis of a high technical project - medical isotopic production reactor which was developed by nuclear power institute of china, using nuclear project feasibility study and economic analyses method

    本論文將利用現有的核工程項目可行性研究和經濟分析的方法對中國核動力研究設計院近期開發的高科技項目? ?醫用同位素生產堆的項目可行性報告編制、項目投資估算、項目生產成本費用估算、項目銷售收入及稅金估算、項目財務評價指標的計算、項目財務評價的結論等情況進行研究和探討。
  11. The reactor protection system reliability analysis of daya bay npp is an important branch of the probabilistic risk assessment project of daya bay nuclear power plant. the purpose of probabilistic risk assessment of reducing reactor trip is to discover all the signals and the components which can result in reactor trip potentially, to assess the safety and reliability of systematic design, to find the potential design drawbacks and take effective measures to reduce such events

    大亞灣核電站反應堆保護系統是大亞灣核電站pra項目的重要的一個分支,大亞灣核電站減少緊急停堆pra (概率安全分析)是要找出各種可能引起機組緊急停堆的信號和部件,評價系統設計的安全性和可靠性,找到可能存在的設計缺陷,採取有效的防範措施,減少此類事件。
  12. Acquisition and documentation of reference power reactor physics measurements for nuclear analysis verification, guide for

    核分析鑒定用參考動力反應堆物理測量的數據獲得及文件編制指南
  13. This method is used in a nuclear power station, diagnosis results is better ideality, and it has been shown that it is feasible for fault diagnosis of nuclear power station and fast reactor sodium pump

    本文將此方法應用於某核電廠主冷卻劑泵,診斷結果比較理想,證明此方法在核電廠的故障診斷中是可行的,對快堆鈉泵的診斷也是可取的。
  14. Based on adequate survey to faults of sodium pump for the china experiment fast reactor, in order that the advanced diagnosis methods are used in the sodium pump which is under fabrication, different methods of fault diagnosis system of sodium pump are designed and programmed ; and the principal component analysis ( pca ) is used to fault diagnosis system of main coolant pump in a nuclear power station. the feasibility of fault diagnosis systems developed have been proved by simulation results

    本課題對中國實驗快堆鈉泵的故障進行了研究,把先進的診斷方法應用到正在製造中的鈉泵上,設計和開發了不同方法的鈉泵的故障診斷系統;同時也應用主元分析方法,建立了某核電廠的主冷卻劑泵的故障診斷系統,模擬實驗證明了以上三個系統的可行性。
  15. The pressure container for the nuclear reactor pile which is introduced by this essay is designed and made by certain group company. it ' s a huge equipment used in the nuclear power station. the equipment is made up of two parts, a pressure container body and a lid. this paper is going to give the descriptions of the transport program design of the pressure container body. the body of the pressure container is 5. 165m wide, 4. 85m high and its net weight is 160t, because it is a large item for transporting in nature, the container needs a stern transporting condition. if we want to transport the container designedly and procedurely, to achieve no damage and no loss in the whole process, we must pay a careful investigation and find a feasible way to carry it

    該設備由壓力殼筒體和頂蓋兩部分組成,在此僅敘述核反應堆壓力殼筒體的運輸方案設計。核反應堆壓力殼筒體凈重160t ,寬5 . 165m ,高4 . 85m ,屬大件運輸。運輸技術條件要求極為嚴格,為使該大件運輸能有計劃、有步驟進行,確保整個運輸過程完整無損、萬無一失,必須進行深入細致的調查研究,尋找大件運輸的可行方案。
  16. In october 1997, china gave the united states assurances regarding its nuclear cooperation with iran. china agreed to end cooperation with iran on supplying a uranium conversion facility ( ucf ) and to end further cooperation after completing within a reasonable period of time two existing projects - - a zero - power reactor and a zirconium production plant

    方面的合作,並在合理的時間內完成兩個現有項目一個零功率核反應堆和一座生產鋯的工廠以後,終止與伊朗的進一步合作。我們將繼續對中國與伊朗有關實體今後的往來是否同中方做出的「不進行新的核合作」的保證相一致做出評估。
  17. The paper reports the model of the reactor core of the pwr nuclear power plant and established the suitable core physics - mathematics model for microcomputer simulation

    摘要闡述了pwr核電站堆芯的模型化問題,提出了適用於微機模擬的核電站堆芯的物理數學模型。
  18. Standard practice for evaluation of surveillance capsules from light - water moderated nuclear power reactor vessels

    評價輕水核電反應堆監視艙的標準實施規程
  19. Standard practice for design of surveillance programs for light - water moderated nuclear power reactor vessels

    輕水冷卻核反應堆容器的監督程序設計的標準操作規程
  20. In - core temperature or primary envelope temperature measurements in nuclear power reactor - characteristics and test methods

    核動力堆堆芯或堆主包殼內溫度測量特性和測試方法
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