水水堆 的英文怎麼說
中文拼音 [shuǐshuǐduī]
水水堆
英文
water-water reactor-
The geode - essentially a rock cavity which has become lined with crystalline deposits - is eight meters in length, 1. 8 metres wide and 1. 7 metres high ( 26 feet by six by six )
這個晶洞-原本是巖石洞演變成線狀水晶堆積物-是長8米，寬1 . 8米和高1 . 7米（ 26英尺x六英尺x六英尺） 。Matrix for light water reactor fuel reprocessing
輕水堆燃料回收用容器Presents the steady - state programming with constant coolant average temperature and constant live steam pressure, an ideal programming for marine nuclear power plant ( npp ), under which, both the coolant average temperature and the live steam pressure of nuclear steam supply system ( nsss ) are constant when the steady state operating condition is varied, and points out that in comparison with the steadysate programming with constant coolant average temperature, the ideal programming can improve the overall operating performance of npp effectively, especially in low - load range, for instance, raise the heat efficiency of npp, decrease the operating noise of main coolant pump, and improve the conditions of design, operation and control of the secondary loop system
雙恆定運行方案是船用壓水堆核動力裝置的理想運行方案.在這種運行方案下，當裝置穩態功率變化時，冷卻劑平均溫度與蒸汽壓都保持不變，與通常採用的冷卻劑平均溫度恆定運行方案相比，有效地改善了核動力裝置的總體運行性能，特別是在低負荷運行時，可以提高裝置經濟性、降低主泵運行噪聲、改善二迴路系統的設計、運行和控制條件，這對于提高船用核動力裝置的運行可靠性和安全性具有實際意義Helium leak testing of nuclear fuel rod for pwr
壓水堆燃料棒氦質譜檢漏Metallographic examination for weld seam of nuclear fuel rod used in pwr
壓水堆核燃料棒焊縫金相檢驗Radiographic inspection of welds for pwr fuel rods
壓水堆燃料棒焊縫x射線照相檢驗方法Design rules for mechanical components of pwr nuclear islemds
壓水堆核電廠核島機械設備設計規范Design rules for mechanical components of pwr nuclear islands
壓水堆核電廠核島機械設備設計規范Radioactive source term of pwr nuclear power plant for operational states
壓水堆核電廠運行狀況下的放射性源項Fuzzy controller design method for pwr steam generator level control
壓水堆蒸汽發生器水位模糊控制器的設計方法Mathematical model for coil - coding control rod position detector in pwrs
壓水堆線圈編碼控制棒位置探測器的數學模型Design and construction rules for nuclear island systems of 2 600mw pwr nuclear power plants
壓水堆核電廠核島系統設計建造規范Zircaloy - 4 is generally used as fuel tubes in pressurized water reactors because of it " s low neutron absorption cross - section, excellent corrosion resistance, good strength and ductility
由於鋯4合金具有低的中子吸收截面，良好的抗腐蝕能力、高強度以及延展性好的特點，被廣泛用於壓水堆作為核燃料棒的包殼材料。Ln power system full dynandc simulation, the electric - mechanical transient processes of dynamic elements of power system should be simulated in detail, and the detailed dynandc models of mid - term and long - term processes are necessary based on the research and analysis for the ndd - term and long - term models, the dynandc models, such as thermal power plant, hydraulic power plant, nuclear power plant and the automatic generation control ( agc ), which are necessary to power syst
電力系統全過程動態模擬除了需要詳細模擬電力系統動態元件的機電暫態過程外，還要有詳細的中長期過程的模型。本文在綜合調查和分析的基礎上，研究了電力系統全過程動態模擬所需要的火電廠動力系統的數學模型、水電廠動態模型、壓水堆核電站模型以及自動發電控制（ agc ）模型及其演算法，並在電力系統全過程動態模擬軟體中得到了實現。Reload startup physics tests for pressurized water reactors
壓水堆重新裝料起動的物理試驗Because of deposit the ground form, wide soft soil and large thickness, we should use the methods to set up the standard design., such as to change and fill out a stone, lump block of stone of the strong rammer and split off the thick liquid of note and so on
摘要深圳市港灣大道沿線屬前海灣沿岸海漫灘沉積地貌，軟土層分佈范圍廣、厚度大、性狀極差，闡述該路採用的換填塊石、劈裂注漿、插板排水堆載預壓、強夯塊石墩等地基處理方法，進行了標準設計。95zr is one of the fission products and main radioactivity liquid drainages of nuclear reactor
~ （ 95 ） zr是核電站反應堆的主要裂變產物之一，是壓水堆核電站的主要放射性液態排放物。Matrix for lwr spent fuel receiving and storage
輕水堆廢燃料接收和貯存用容器Program for testing radiation shields in light waterreactors
輕水堆核電廠輻射屏蔽檢測大綱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。分享友人