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首页> 外文会议>2002 ASME Pressure Vessels and Piping Conference, Aug 5-9, 2002, Vancouver, British Columbia, Canada >FINITE ELEMENT ANALYSIS FOR LOCAL CREEP OF A TUBE COOLANT PIPING SYSTEM IN LIGHT WATER REACTOR DUE TO LOCAL HEATING UNDER SEVERE ACCCIDENT CONDITION
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FINITE ELEMENT ANALYSIS FOR LOCAL CREEP OF A TUBE COOLANT PIPING SYSTEM IN LIGHT WATER REACTOR DUE TO LOCAL HEATING UNDER SEVERE ACCCIDENT CONDITION

机译：严重事故条件下局部加热下轻水反应器管冷管道系统局部蠕变的有限元分析。

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摘要

During severe accident of a light water reactor (LWR), reactor coolant piping would be damaged when the piping is subjected to high internal pressure and very high temperature due to heat transfer from high-temperature gas and decay heat from wall-deposited fission product (FP), both from degraded core. In such a case, high-temperature fast creep deformation could be the main cause for the pipe failure. For the evaluation of piping integrity during severe accidents, a method to predict such high-temperature fast creep deformation should be developed, using a creep constitutive equation considering tertiary creep behavior which has not been considered well in the pipe failure analyses. In this paper, a creep constitutive equation was developed, which is based on the Kachanov-Ravotnov isotropic damage rule considered the tertiary creep behavior. Japan Atomic Energy Research Institute (JAERI) creep tensile test data for nuclear-grade cold-drawn SUS316 material was used to determine coefficients of the developed constitutive equation. Using the developed constitutive equation, finite element analyses were performed for local creep deformation of coolant piping under two temperature conditions; uniform temperature and temperature gradient. The analyses results indicated the damage variable being integrated following the evolution of creep damage can indicate pipe wall internal damage condition quantitatively. The damage variable was confirmed further to be able to reproduce the observation in JAERI piping failure tests; pipe failure from the wall outside.
机译：在轻水反应堆（LWR）的严重事故中，由于高温气体的传热和沉积在壁上的裂变产物的热量衰减，当反应堆冷却剂管道承受较高的内部压力和极高的温度时，会损坏反应堆冷却剂管道（ FP），均来自降级的核心。在这种情况下，高温快速蠕变变形可能是造成管道故障的主要原因。为了评估严重事故下的管道完整性，应开发一种预测此类高温快速蠕变变形的方法，该方法应使用考虑了三次蠕变行为的蠕变本构方程，而在管道故障分析中并未很好地考虑到这种蠕变本构关系。本文基于Kachanov-Ravotnov各向同性破坏规则，考虑了三次蠕变行为，建立了蠕变本构方程。日本原子能研究院（JAERI）核级冷拉SUS316材料的蠕变拉伸试验数据用于确定已开发的本构方程的系数。使用开发的本构方程，对两种温度条件下冷却剂管道的局部蠕变变形进行了有限元分析。温度和温度梯度均匀。分析结果表明，随着蠕变损伤的发展，对损伤变量进行积分可以定量地指示管壁内部损伤情况。在JAERI管道故障测试中，进一步确认了损坏变量能够再现观察结果；管道故障从墙外开始。

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