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锅炉及压力容器规范
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  boiler and pressure vessel code
    This paper specifically analyzes the philosophy of requirements of permissible out-of-roundness for shells, of shape tolerance for heads, and of alignment tolerance for sections at edges to be welded which are specified by ASME Boiler and Pressure Vessel Code.
    本文对ASME锅炉及压力容器规范中壳体许用不圆度规定、封头形状误差规定、待焊对接截面对准误差规定等逐一进行分析。
短句来源
    A method to establish the finite element model and assess the stress of expansion joints on power plant air cooling system were presented based on the rules of JB 4723—1995"Steel Pressure Vessels—Design by Analysis" and "ASME Boiler and Pressure Vessel Code,Section Ⅷ,Div 2,Alternative Rules for Construction of High Pressure Vessels",and to explain the method,calculation of a gimbal expansion joints was put forward.
    参照JB 4723—1995《钢制压力容器——分析设计标准》和《ASME锅炉及压力容器规范Ⅷ第二册.压力容器建造另一规则》,对某热电厂空冷系统的波纹管膨胀节建立了有限元计算模型,并对其进行应力评定,然后以双铰链膨胀节为例加以说明。
短句来源
    A finite element method for expansion joints design is presented based on the rules of ASME BOILER AND PRESSURE VESSEL CODE, Section Ⅷ, Div 3, Alternative Rules for Construction of High Pressure Vessels, with a detailed discussion on the related problems such as the analysis of pipeline, the establishment of loading and the assessment of stresses. At last a simple problem is given to illustrate the procedures of the method.
    本文参照JB 4723-95《钢制压力容器——分析设计标准》和《ASME锅炉及压力容器规范Ⅷ第二册·压力容器建造另一规则》,提出一套采用有限元设计膨胀节的方法,对所涉及到的管线分析计算、外载荷设定、应力评定等方面问题作了细致讨论,并通过简例加以说明。
  “锅炉及压力容器规范”译为未确定词的双语例句
    Brief introduction of “ASME boilers & pressure vessels code”
    《ASME锅炉及压力容器规范》简介
短句来源
    Significant changes to the Rules in the ASME Section Ⅷ Code
    ASME锅炉及压力容器规范(1998版)第Ⅷ卷的重要修订
短句来源
    Resolution of General Stresses Resulted from Methods of Stress Classification or Finite Element Analysis
    对美国“锅炉及压力容器规范Ⅷ-2”的分析与理解之四——应力分类及对有限元所求总应力的分解
短句来源
    The Philosophy of Requirements of Permissible Shape Tolerance for ASME Boiler and Pressure Vessel Code
    ASME锅炉及压力容器规范对壳体和封头形状允差规定的依据
短句来源
    The New ASME Section Ⅷ Division 3 High Pressure Vessel Code
    ASME锅炉及压力容器规范第八卷新增第三册高压容器规范简介
短句来源
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  boiler and pressure vessel code
These observations are consistent with limitations (2000 Addendum to ASME Boiler and Pressure Vessel Code) on the use of cold worked austenitic stainless steels for elevated temperature service.
      


The steam generator in PWR primary coolant system is one of the equipment made by our own country in Qinshan Nuclear Power Plant of China. It is a crucial unit belonging to the category of nuclear pressure vessel. The purpose of this research work is to make an examination of the weld quality of the steam generator under fatigue loading and to assess its reliability by using the experimental results of fatigue test of material of nuclear pressure vessel steel S-271 (Chinese Standard) and of qualified tests of...

The steam generator in PWR primary coolant system is one of the equipment made by our own country in Qinshan Nuclear Power Plant of China. It is a crucial unit belonging to the category of nuclear pressure vessel. The purpose of this research work is to make an examination of the weld quality of the steam generator under fatigue loading and to assess its reliability by using the experimental results of fatigue test of material of nuclear pressure vessel steel S-271 (Chinese Standard) and of qualified tests of welded seams of a simulated prototype of bottom closure head of the steam generator. A guarantee of weld quality is proposed as a subsequent verification for China National Nuclear Safety Supervision Bureau. The results of reliability analysis reported in this work can be taken as a supplementary material of Probabilistic Safety Assessment (PSA) of Quinshan Nuclear Power Plant. According to the requirement of Provision Ⅱ-1500 cyclic testing, ASME Boiler and Pressure Vessel Code, Section Ⅲ, Rules for Construction of Nuclear Power Plant Components, a simulated prototype of the bottom closure head of the steam generator was made in this work for qualified tests. To find the quantified results of reliaability assessment by using the testing data, two proposals are presented in this paper.

秦山30万千瓦核电设备中的蒸汽发生器,是国产关键设备之一。对该蒸汽发生器焊接质量进行疲劳可靠性评估的试验研究,旨在根据国产核容器用钢S-271的疲劳性能测试结果,通过对该容器底封头模拟装置试验数据分析,为国家核安全局进行质量审评提供参考依据,并作为秦山核电工程概率安全评价的补充。按照美国机械工程师学会《锅炉及压力容器规范》第三分篇有关条款的要求进行了模拟试验,提出了两种方法进行可靠性定量求解。

This paper specifically analyzes the philosophy of requirements of permissible out-of-roundness for shells, of shape tolerance for heads, and of alignment tolerance for sections at edges to be welded which are specified by ASME Boiler and Pressure Vessel Code.

本文对ASME锅炉及压力容器规范中壳体许用不圆度规定、封头形状误差规定、待焊对接截面对准误差规定等逐一进行分析。

This paper specifically analyzes the philosophy of requirements of permissible out-of-roundness for shells, of shape tolerance for heads, and of alignment tolerance for sections at edges to be welded which are specified by ASME Boiler and Pressure Vessel Code.

本文对ASME锅炉及压力容器规范中壳体许用不圆度规定、封头形状误差规定、待焊对接截面对准误差规定等逐一进行分析。

 
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