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堆压力容器
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  reactor pressure vessel
     Application of SA516-70 Plate Used in the 10MW High Temperature Gas-Cooled Reactor Pressure Vessel
     10MW高温气冷堆压力容器用SA516-70钢板
短句来源
     We have manufactured the 10MW High Temperature Gas- cooled Reactor pressure vessel with SA516- 70 plate.
     10MW高温气冷堆压力容器采用 SA516- 70钢板制造。
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
     The operating control principle and method for the water reactor pressure vessel, as an approach to prevent the brittle fracture of reactor coolant pressure boundary, has been described, based on the requirements of ANSI N18.2 and 10CFR 50App. A.
     本文根据ANSIN18.2和10CFR50·APPA的要求,对防止水堆冷却剂压力边界脆性断裂的工程方法之一——水堆压力容器运行控制的原理和方法进行了阐述。
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
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  “堆压力容器”译为未确定词的双语例句
     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
     Fast Neutron Flux Calculation of Welding Line in Pressure Vessel of High Flux Engineering Test Reactor
     高通量工程试验堆压力容器焊缝快中子注量计算
短句来源
     Analytical Design for Water Reactor Pressure Vessels
     水堆压力容器分析法设计
短句来源
     Contact Stress Analysis for the Flanges of HTR-10 Pressure Vessel
     10MW高温气冷堆压力容器主法兰结构的有限元接触分析
短句来源
     Progress in Design and Technology of PWR Pressure Vessels
     压水堆压力容器设计与技术进展
短句来源
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  相似匹配句对
     THE OPERATING LIMIT OF WATER REACTOR PRESSURE VESSEL
     水压力容器运行限制
短句来源
     Analytical Design for Water Reactor Pressure Vessels
     水压力容器分析法设计
短句来源
     Management of Pressure Vessels
     压力容器的管理
短句来源
     Manufacturing Technologies of PWR Vessels
     压水压力容器的制造工艺
短句来源
     The Leakage and Prevention of PWR Pressure Vessel Flange
     水压力容器法兰的泄漏与防止
短句来源
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  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.
      
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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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