首页> 外文会议>Proceedings of International Conference on Structural Mechanics in Reactor Technology >SIMPLIFIED MODEL OF PWR VESSEL TEARING UNDER SEVEREACCIDENT CONDITIONS.APPLICATION TO LHF TESTS AND REACTOR SITUATIONS
【24h】

SIMPLIFIED MODEL OF PWR VESSEL TEARING UNDER SEVEREACCIDENT CONDITIONS.APPLICATION TO LHF TESTS AND REACTOR SITUATIONS

机译:在强事故条件下压水堆容器的简化模型.LHF试验和反应条件的应用

获取原文

摘要

Between 1999 and 2003, CEA conducted a R&D program on high temperature ductile tearing ofFrench PWR vessel steel 16MND5. The main goal was to develop simplified high temperature tearingmodels, validated on experimental data, and allowing parametrical studies of various severe accidentsituations of vessel failure. These models are to give estimations of the final breach section (andtherefore assess the risks of complete unzipping of the vessel), which are major safety concerns withregard to molten corium ejection and ex-vessel initial conditions.The model presented in this paper concerns circumferential tearing and applies to fast openingsituations, for which breach propagation is coupled to vessel depressurisation. Following anexperimental program of high-temperature tearing tests on Compact Tensile specimens and CentreCrack Panels, a perfect plastic behaviour with a strain rupture criterion have been chosen, and simpleassumptions were made on stress and strain distribution. The equations of the model are based on theenergetic differential balance between the kinetic energy, the external work of the pressure load andthe energy dissipated in the tearing process, coupled to an isothermal depressurisation model. Thissystem is numerically solved to obtain the breach length and section versus time during thedepressurisation process.The application of this model to the LHF tests 3, 5 and 8 shown a very good agreement with theexperimental results concerning the final breach size and the dynamic stability or instability of thestructure. Dimensionless key parameters were identified, allowing simple assessments on the risks ofcatastrophic failure in experimental or reactor situations. Moreover, the importance of pressure historybefore failure was explained : lower and constant pressure values (implying creep failures) lead todynamically stable situations and smaller breach sections, whereas fast plastic failures during pressureramps lead to dynamically unstable situations and catastrophic failures may occur.Finally, a PWR severe accident situation with corium relocation in the vessel bottom head has beenmodelled. The main result is that catastrophic failure (complete unzipping of the vessel bottom head,like in the LHF 5 test) can occur in situations of late vessel reflooding, leading to a re-pressurisation ofthe primary circuit at high vessel temperature. These situations are of low probability, but these resultsmight have important consequences on accident management and safety assessments.
机译:在1999年至2003年之间,CEA进行了一项针对高温韧性撕裂的R&D计划。 法国PWR船用钢16MND5。主要目标是开发简化的高温撕裂 模型,通过实验数据进行验证,并可以对各种严重事故进行参数研究 船只故障的情况。这些模型用于估算最终违规部分(以及 因此,请评估容器完全拉开拉链的风险),这是安全隐患 关于熔化的皮质醇排出和前容器的初始条件。 本文介绍的模型涉及周向撕裂,适用于快速打开 在这种情况下,违规传播与船舶减压有关。跟随 致密拉伸试样和中心的高温撕裂试验的实验程序 选择了裂纹面板,具有应变断裂准则的理想塑性行为,并且简单 对应力和应变分布进行了假设。该模型的方程式基于 动能,压力负荷的外部功和 撕裂过程中耗散的能量,再加上等温降压模型。这 对系统进行数值求解,以得出断裂期间的缺口长度和截面与时间的关系 减压过程。 该模型在LHF测试3、5和8中的应用表明与LHF测试非常吻合。 有关最终违规尺寸和动态稳定性或不稳定性的实验结果 结构体。确定了无量纲的关键参数,从而可以对风险的简单评估 在实验或反应堆情况下发生灾难性故障。而且,压力史的重要性 在解释故障之前:较低和恒定的压力值(暗示蠕变故障)会导致 动态稳定的情况和较小的缺口区域,而在压力作用下快速发生塑性破坏 斜坡会导致动态不稳定的情况,并可能发生灾难性故障。 最终,发生了压水堆严重事故,船底盖内发生了钙迁移。 建模。主要结果是发生灾难性故障(船只底盖完全拉开拉链, 例如在LHF 5测试中)可能会在后期血管回注的情况下发生,从而导致重新加压 容器高温时的主回路。这些情况的可能性很小,但是这些结果 可能会对事故管理和安全评估产生重要影响。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号