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Semi-analytical modeling of a PWR lower head failure under severe accident conditions using an axisymetrical shell theory

机译:使用轴对称壳理论在严重事故情况下压水堆下压头故障的半分析建模

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摘要

The USNRC/SNL OLHF program was carried out within the framework of an OECD project. This program consisted of four one-fifth scale experiments of a reactor pressure vessel (RPV) lower head failure (LHF) under well controlled internal pressure and large throughwall temperature differentials; the objectives were to characterize the mode, timing and size of a possible PWR lower head failure in the event of a core meltdown accident. These experiments should also lead to a better understanding of the mechanical behavior of the reactor vessel lower head, which is of importance both in severe accident assessment and the definition of accident mitigation strategies. A well-characterized failure of the lower head is of prime importance for the evaluation of the quantity of core material that can escape into the containment, since this defines the initial conditions for all ex-vessel events. A large quantity of escaping corium may lead to direct heating of the containment or ex-vessel steam explosion. These are important issues due to their potential to cause early containment failure. The experiments also provide data for model development and validation. For our part, as one of the program partners, a 2D semi-analytical model has been developed and used to simulate these experiments. The aim of this effort is to develop a simplified but well predicting code that can be then implemented in European integral severe accident computer codes (ASTEC, ICARE/CATHARE). This paper presents the detailed mathematical formulation of this simplified method which is used to interpret the experimental results. The axi-symmetric shell theory under internal pressure proposed by Timoshenko has been utilised. The solution to the equilibrium equations is presented, with particular attention to the Rabotnov analytical formula. The radius and the polar angle of the deformed structure have been written as analytical expressions in order to take the large displacements and large strains into account using our mathematical formulation. The Norton type creep law and the Kachanov damage law have been used. Several failure criteria were used in the calculations and their effect on the numerical results is discussed. This 2D semi-analytical model gives very satisfactory results when compared, with the experimental and numerical results that were presented recently in the Benchmark calculations based on the first test of the OLHF program. The performance of this model is also illustrated by its capacity to accurately simulate the deformation of the lower head, including the variation of wall thickness.
机译:USNRC / SNL OLHF计划是在OECD项目框架内实施的。该程序包括四个反应堆压力容器(RPV),在良好的内部压力和较大的贯穿壁温差下的低水头故障(LHF)的五分之一规模实验;目的是确定发生堆芯熔化事故时可能发生的压水堆下压头故障的方式,时间和大小。这些实验还应该使人们更好地了解反应堆容器下扬程的机械性能,这在严重事故评估和事故缓解策略的定义中都具有重要意义。对于评估可以逃逸到安全壳中的核心材​​料的数量而言,充分确定下端头的故障至关重要,因为这定义了所有前船事件的初始条件。大量逸出的皮质可能导致容器的直接加热或前蒸汽爆炸。这些都是重要问题,因为它们有可能导致早期收容失效。实验还提供了用于模型开发和验证的数据。作为程序合作伙伴之一,我们已经开发了2D半分析模型并将其用于模拟这些实验。这项工作的目的是开发一种简化但预测良好的代码,然后可以在欧洲整体严重事故计算机代码(ASTEC,ICARE / CATHARE)中实现。本文介绍了此简化方法的详细数学公式,用于解释实验结果。利用了蒂莫申科提出的内压轴对称壳理论。提出了平衡方程的解,并特别注意了Rabotnov分析公式。为了使用我们的数学公式考虑大位移和大应变,已将变形结构的半径和极角表示为解析表达式。使用了诺顿型蠕变定律和卡尚诺夫损伤定律。计算中使用了几种失效准则,并讨论了它们对数值结果的影响。当与基于OLHF程序的第一次测试的基准计算中最近提供的实验和数值结果进行比较时,该二维半分析模型给出了非常令人满意的结果。该模型的性能还可以通过其准确模拟下缸盖变形(包括壁厚变化)的能力来说明。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2005年第8期|p.845-853|共9页
  • 作者

    V. Koundy; I. Cormeau;

  • 作者单位

    IRSN-DSR, Service d'evaluation des accidents graves et des rejets radioactifs, B.P. 17, 92262 Fontenay-Aux-Roses Cedex, France;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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