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Characterization of PWR vessel steel tearing under severe accident condition temperatures

机译:严重事故工况温度下压水堆容器钢撕裂的表征

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摘要

In the event of a severe core meltdown accident in a pressurised water reactor (PWR), core material can relocate into the lower head of the vessel resulting in significant thermal and pressure loads being imposed on the vessel. In the event of reactor pressure vessel (RPV) failure there is the possibility of core material being released towards the containment. On the basis of the loading conditions and the temperature distribution, the determination of the mode, timing, and size of lower head failure is of prime importance in the assessment of core melt accidents. This is because they define the initial conditions for ex-vessel events such as core/basemat interactions, fuel/coolant interactions, and direct containment heating. When lower head failure occurs (i) the understanding of the mechanism of lower head creep deformation; (ii) breach stability and its kinetic of propagation leading to the failure; (iii) and developing predictive modelling capabilities to better assess the consequences of ex-vessel processes, are of equal importance. The objective of this paper is to present an original characterization programme of vessel steel tearing properties by carrying out high temperature tearing tests on Compact Tension (CT) specimens. The influence of metallurgical composition on the kinetics of tearing is investigated as previous work on different RPV steels has shown a possible loss of ductility at high temperatures depending on the initial chemical composition of the vessel material. Small changes in the composition can lead to different types of rupture behaviour at high temperatures. The experimental programme has been conducted on various French RPV 16MND5 steels for temperatures ranging from 900℃ to 1100℃. Comparisons between the tests performed on these various 16MND5 steels show that this approach is appropriate to characterize the difference in ductility observed at high temperatures. The aim of this experimental study is also to contribute to the definition of a tearing criterion by identifying, on the basis of CT results, the related material parameters at temperatures representative of the real severe accident conditions. This experimental campaign has been carried out in partnership with IRSN in the framework of a research programme whose purpose is to complete the mechanical properties database of 16MND5 steel and to model tearing failure in French RPV lower head vessels under severe conditions (Koundy et al., 2008).
机译:万一压水反应堆(PWR)中发生严重的堆芯熔化事故,堆芯材料可能会重新定位到容器的下部封头中,从而导致在容器上施加大量的热负荷和压力负荷。如果反应堆压力容器(RPV)发生故障,则有可能将堆芯材料释放到安全壳内。根据加载条件和温度分布,确定下熔头故障的方式,时间和大小对于评估堆芯熔体事故至关重要。这是因为它们定义了船外事件的初始条件,例如堆芯/底垫相互作用,燃料/冷却剂相互作用以及直接密闭加热。当发生下部头部破坏时(i)了解下部头部蠕变变形的机理; (ii)破坏稳定性及其导致失败的传播动力学; (iii)同样重要的是,发展预测模型功能以更好地评估前船过程的后果。本文的目的是通过对紧凑张力(CT)试样进行高温撕裂测试,提出一种容器钢撕裂性能的原始表征程序。研究了冶金成分对撕裂动力学的影响,因为先前对不同RPV钢的研究表明,取决于容器材料的初始化学成分,高温下可能会失去延展性。成分的微小变化会导致高温下的不同类型的断裂行为。该实验程序已在900℃至1100℃的各种法国RPV 16MND5钢上进行。对各种16MND5钢进行的测试之间的比较表明,这种方法适合表征高温下观察到的延展性差异。该实验研究的目的还在于通过基于CT结果识别代表实际严重事故工况的温度下的相关材料参数,从而有助于确定撕裂标准。这项实验活动是与IRSN合作开展的一项研究计划,其目的是完善16MND5钢的力学性能数据库,并模拟法国RPV下水头容器在严酷条件下的撕裂失效(Koundy等, 2008)。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2012年第1期|p.124-133|共10页
  • 作者单位

    CEA, DEN, DM2S, SEMT, F-91191 Gif-sur-Yvette, France;

    CEA, DEN, DM2S, SEMT, F-91191 Gif-sur-Yvette, France;

    CEA, DEN, DM2S, SEMT, F-91191 Cif-sur-Yvette, trance Laboratoire de Mécanique des Structures Industrielles Durables, UNIR CNRS-EDF2832, 1 avenue du Generai de Gaulle, F-92141 Clamare France;

    IRSN-DSR, Service devaluation des Accidents Graves et des Rejets radioactifs B.P. 17,92262 Fontenay-aux-Roses Cedex, France;

    IRSN-DSR, Service devaluation 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
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