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压力容器     
相关语句
  pressure vessel
    Quality Assurance on Manufacture Stage of Pressure Vessel for Water Reactor
    水堆压力容器制造阶段的质量保证
短句来源
    Irradiation Surveillance and Embrittlement Evaluation of LWR Pressure Vessel Materials
    水冷反应堆(LWR)压力容器材料辐照监督和脆化评定
短句来源
    Operating Limitary Pressure and Calculative Method of Water Reactor Pressure Vessel
    水堆压力容器运行限制压力的计算方法
短句来源
    TRIDIMENSIONAL FINITE ELEMENT ANALYSIS OF TRANSIENT STRESS FIELD OF PWR PRESSURE VESSEL NOZZLE BELT
    压水堆压力容器接管段瞬态应力场三维有限元分析
短句来源
    Reliability Analysis of the Reactor Pressure Vessel
    核反应堆压力容器可靠性分析
短句来源
更多       
  the pressure vessel
    Design of the Pressure Vessel for the Fuel Assembly Scouring Test
    燃料组件冲刷实验压力容器的设计
短句来源
    The program FEARPV is applied to analysis the sealing structure of the pressure vessel model during the total process, including bolt pretensioning process, heating and compression process, thermostated heating and constant pressure process, and the cooling and decompressing process.
    应用反应堆压力容器瞬态密封有限元分析程序对反应堆压力容器模拟体密封结构进行了螺栓预紧、升温升压、恒温恒压、降温降压等全过程分析。
短句来源
    The computational results are compared with the experimental data including stress, temperature, bolt force and separation, which are obtained from the pressure vessel module by the China Nuclear Power Operation Research Institute. Either under cooling or heating cycle, the computational results are in good concordance with the experimental data in both the qualitative regularity and the quantitative data.
    与中国核动力运行研究所在压力容器模拟体上测试所得的应力、温度、螺栓力、分离量等大量数据对比,在冷态和热态两种工况下,密封分析结果的定性规律和定量数据都与实验结果吻合良好。
短句来源
    This paperCheckes Qinshan Nuclear Power Plant's fast neutron flux maximum at the T/4position in the pressure vessel wall using neutron transport Green's functionmethord.
    本文应用中子输运格林函数法验算了秦山核电站压力容器1/4厚度处最大快中子通量。
短句来源
    These results show that the core safety isn't variation,and the fast neutron flux at the pressure vessel will be decreased greatly after replacemeat of the aluinum rod by the stainless steel rod as the outermost reflector of the core for HFETR.
    结果表明,用不锈钢代替铝棒作最外层反射层,堆芯安全性能不变,压力容器处快中子注量率被大幅度降低。
短句来源
更多       
  reactor pressure vessel
    Operating Limitary Pressure and Calculative Method of Water Reactor Pressure Vessel
    水堆压力容器运行限制压力的计算方法
短句来源
    Reliability Analysis of the Reactor Pressure Vessel
    核反应堆压力容器可靠性分析
短句来源
    The Analyses and Evaluation of Neutron Irradiation Damage for Reactor Pressure Vessel
    反应堆压力容器中子辐照损伤的分析和评价
短句来源
    Brittle Fracture of Water Reactor Pressure Vessel——Criteria,Standard and its Use
    水堆压力容器的脆性断裂——准则、标准及其应用
短句来源
    An Approach to the Reactor Pressure Vessel Design for AC-600
    AC-600反应堆压力容器设计探讨
短句来源
更多       
  pwr pressure vessel
    TRIDIMENSIONAL FINITE ELEMENT ANALYSIS OF TRANSIENT STRESS FIELD OF PWR PRESSURE VESSEL NOZZLE BELT
    压水堆压力容器接管段瞬态应力场三维有限元分析
短句来源
    The radiation embrittlement of two types of low copper reactor pressure vessel steels is studied. The relation between the material damage embrittlement extent and irradiation parameters such as fast neutron flux、 fluence and temperature is investigated, so with the test data of SA508 3 steel irradiated in the test reactor to be correlated to PWR pressure vessel surveillance test data.
    研究了快中子注量率、注量和辐照温度等辐照参数对低铜压力容器钢的辐照脆化程度的影响,从而将实验堆辐照试验数据与动力堆监督试验数据关联。
短句来源

 

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  pressure vessel
The depressurization of a high-pressure vessel initially filled with water heated to below the saturation point is investigated.
      
Experimental studies are performed into the variation of the shape of a jet of boiling liquid flowing out of a high-pressure vessel under conditions of high superheating.
      
The possibility of preparing diethyl terephthalate without a catalyst in a rocking cylindrical pressure vessel with the rocking axis passing through the geometric center was examined.
      
This provides a basis for characterizing the dose dependence of the hardening of reactor pressure vessel steel and for comparing the effects of primary radiation damage for fission and fusion reactors.
      
We have studied dynamics of pulsation that develop during the explosion boil-up of overheated water jets emitted via a nozzle from a high-pressure vessel.
      
更多          
  the pressure vessel
A suitable weight was assigned to each stratified sample according to the actual working states of the pressure vessel, so that the estimation of fatigue crack growth rate equation was more accurate for practice.
      
Based on the vessel temperature histories measured at the distance of 50?mm from the inner surface and at the outside surface the transient temperature distribution in the pressure vessel was obtained.
      
The engineering situation considered here has practical importance in the pressure vessel and pipe industry.
      
At arbitrary intervals, the pressure vessel was quenched to room temperature and both solids and solutions were separated by filtration.
      
The seismic detectors (vertical geophone or hydrophone and two orthogonally mounted horizontal geophones) are located outside of the pressure vessel on the main frame.
      
更多          
  reactor pressure vessel
This provides a basis for characterizing the dose dependence of the hardening of reactor pressure vessel steel and for comparing the effects of primary radiation damage for fission and fusion reactors.
      
This configuration can occur, when in the progress of a hypothetical accident the core melt relocates to the lower plenum of a nuclear reactor pressure vessel and gets partially fragmented.
      
The bed was placed in a glass container with an inclined bottom to represent a section of the lower plenum of a reactor pressure vessel.
      
Microstructural investigations on Russian reactor pressure vessel steels by small-angle neutron scattering
      
The effect of radiation embrittlement has a high safety significance for Russian VVER reactor pressure vessel steels.
      
更多          
  其他


According to the ASME B & PVC Sec.Ⅲ subsection NB and designexperiences on the manufactory of water reactor pressure vessels in USA,Netherland,Italy and Japan et al.,this paper analyses and describes the chara-cteristics,contents,steps and experiences of analytical design.

本文根据ASME规范第Ⅱ卷NB篇的内容,结合美国、荷兰、意大利、日本等国有关厂家关于水堆压力容器的设计经验,分析并叙述了分析法设计的特点、内容、步骤及经验。

This paper summarizes the theoretical and experimental stress analysis results of pressure vessel of 300 MWe PWR Nuclear Power Station. Stress assessment is given with reference to relevant strength criteria. The results show that the vessel is strong enough under normal steady pressure and tempesature. Various methods were used in the stress analysis in order to cnsure reliability of the results, and to establish a practical analytical method and a program system. A comment on the stress analysis concerned...

This paper summarizes the theoretical and experimental stress analysis results of pressure vessel of 300 MWe PWR Nuclear Power Station. Stress assessment is given with reference to relevant strength criteria. The results show that the vessel is strong enough under normal steady pressure and tempesature. Various methods were used in the stress analysis in order to cnsure reliability of the results, and to establish a practical analytical method and a program system. A comment on the stress analysis concerned is given on the basis of the comparison between the analytical and experimental resulls.

本文綜述了核电站重要設备——压水堆压力容器的应力分析和試驗结果,并参照有关国家规范拟定的强度准則,进行了应力評价。结果表明,該容器对于稳态压力和温度具有足够的强度。采用多种方法对容器所进行的对比分析,其目的不仪在于确保数据可靠,还在于試图得到一种定型的实用分析方法,以建立必要的程序系統。通过計算和試驗結果的分析比較,提出了一些看法。

In the paper,the allowable leakage values of reactor pressure boundary isabstracted.The causes of leakage for PWR pressure vessel flange are analysed.Measurements possibly taken for preventing the leakage of PWR pressure vesselflange are proposed.

本文摘录了水堆冷却剂压力边界允许的泄漏值,分析了水堆压力容器法兰泄漏的原因,提出了防止水堆压力容器法兰泄漏可能采用的措施.

 
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