首页> 外文会议>Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors >LA FATIGUE THERMIQUE DANS LES CENTRALES NUCLEAIRES: ENSEIGNEMENT DU RETOUR D'EXPERIENCE
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LA FATIGUE THERMIQUE DANS LES CENTRALES NUCLEAIRES: ENSEIGNEMENT DU RETOUR D'EXPERIENCE

机译:核电厂的热疲劳:反馈中的经验教训

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Thermal fatigue is a key degradation mechanism in nuclear power plants. Low cycle fatigue seems to be well managed, that is in accordance with field experience. For high cycle fatigue in connection with complex thermo-hydraulic loads, it seems that a large number of uncertainties remain in the different step of the methodology, that is also in accordance with field experience. 3 major situations are encountered: stratification, penetration of vortex and mixing tees for large ΔT. In this paper, after a quick overview of existing design codes, the last case encountered will be used as a generic example to treat globally the problem. In conclusion, a review of R&D actions and code modifications will be done. The paper confirms the multi-disciplinary actions with 2 important concerns: the metallurgical examinations and a need of international approaches of the subject. The paper is focused on piping systems (not to large components like reactor coolant pumps) and firstly pressurised water reactors.
机译:热疲劳是核电站中的关键退化机制。低周期疲劳似乎得到了很好的管理,这与现场经验相符。对于与复杂的热工液压负载相关的高周疲劳,似乎在该方法的不同步骤中仍然存在大量不确定性,这也与现场经验相一致。遇到3种主要情况:分层,涡旋穿透和大ΔT的混合三通。在本文中,快速浏览了现有的设计规范之后,最后遇到的情况将用作通用示例,以全局性地解决该问题。总之,将对R&D行动和代码修改进行审查。该论文确认了多学科行动,涉及两个重要方面:冶金学考试和该主题国际化方法的需求。本文的重点是管道系统(不适用于大型组件,如反应堆冷却剂泵),以及首先是压水堆。

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