首页> 外文会议>ASME Pressure Vessels and Piping conference >LOADING CONDITION EVALUATION FOR STRUCTURAL INTEGRITY ASSESSMENT OF RPV DUE TO PTS EVENT BASED ON THREE-DIMENSIONAL THERMAL-HYDRAULICS AND STRUCTURAL ANALYSES
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LOADING CONDITION EVALUATION FOR STRUCTURAL INTEGRITY ASSESSMENT OF RPV DUE TO PTS EVENT BASED ON THREE-DIMENSIONAL THERMAL-HYDRAULICS AND STRUCTURAL ANALYSES

机译:基于三维热工水力和结构分析的PTS事件RPV结构完整性评估的荷载状态评估

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For structural integrity assessment on a reactor pressure vessel (RPV) of pressurized water reactor during the pressurized thermal shock (PTS) events, thermal histories of coolant water and heat transfer coefficient between coolant water and RPV are important influence factors. The former is determined on the basis of thermal-hydraulics (TH) analyses simulating PTS events and the latter is derived from Jackson-Fewster correlation using TH analysis results. Using these factors, subsequently, loading conditions for structural integrity of RPVs are evaluated by structural analyses. Nowadays, three-dimensional TH and structural analyses are recognized as precise methods for assessing structural integrity of RPVs. In this study, we performed the TH and structural analyses using a three-dimensional model including cold-leg, downcomer and beltline region of RPV in order to evaluate loading conditions during a PTS event more accurately. Distributions of temperature of coolant water and heat transfer coefficient on the surface of RPV were calculated by TH analysis. Loading condition evaluation was then performed by structural analysis using these values and taking the weld residual stress due to weld-overlay cladding and post-weld heat treatment into consideration. From these analyses, we obtained histories and distributions of loading conditions at the reactor beltline region of RPV. Based on the analysis results of loading conditions, we discussed the conservativeness of current structural integrity assessment method of RPV prescribed in the current codes through the comparison of the loading conditions due to a PTS event.
机译:为了在加压热冲击(PTS)事件期间对压水堆反应堆压力容器(RPV)进行结构完整性评估,冷却水的热历史以及冷却水与RPV之间的传热系数是重要的影响因素。前者是根据模拟PTS事件的热工液压(TH)分析确定的,而后者则是根据使用TH分析结果的Jackson-Fewster相关性得出的。使用这些因素,随后,通过结构分析评估RPV的结构完整性的加载条件。如今,三维TH和结构分析被认为是评估RPV的结构完整性的精确方法。在这项研究中,我们使用三维模型(包括RPV的冷腿,下导管和腰带区域)进行了TH和结构分析,以便更准确地评估PTS事件期间的载荷条件。通过TH分析计算了冷却水温度和RPV表面传热系数。然后,通过使用这些值进行结构分析,并考虑到由于堆焊覆层和焊后热处理引起的焊缝残余应力,进行了载荷条件评估。从这些分析中,我们获得了RPV反应堆腰线区域的载荷条件的历史和分布。基于荷载工况的分析结果,通过比较PTS事件引起的荷载工况,讨论了现行规范中规定的RPV现行结构完整性评估方法的保守性。

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