首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >LIVE EXPERIMENTS ON THE IN-VESSEL MELT POOL BEHAVIOUR WITH EXTERNAL COOLING CONDITIONS AND THE SIMULATION RESULTS WITH A COUPLED MELCOR-PECM APPROACH
【24h】

LIVE EXPERIMENTS ON THE IN-VESSEL MELT POOL BEHAVIOUR WITH EXTERNAL COOLING CONDITIONS AND THE SIMULATION RESULTS WITH A COUPLED MELCOR-PECM APPROACH

机译:在容器内熔池行为的实时实验,外部冷却条件和耦合熔体 - PECM方法的仿真结果

获取原文

摘要

The LIVE program investigates late in-vessel melt pool behaviour in case of a severe accident under large scale 3D conditions and different relocation modes. The melt retention by flooding the reactor vessel externally is regarded as an effective severe accident management strategy. One question is how the melt pool heat transfer to the vessel walls depends on different external cooling conditions. In this paper, the melt's thermal behaviour, such as melt temperature, heat flux and crust profiles, of two LIVE tests with different external coolant temperatures are compared: one with nucleate boiling condition, the other with sub-cooling condition. Other test conditions, such as simulant material, heating power and the upper boundary condition were similar in the two experiments. The experimental results are simulated with coupled MELCOR and PECM codes. The program DINAMO, which was developed at KIT, was used to realize this coupling exchange. Using DINAMO it is possible to add new or enhanced models to the nuclear safety code MELCOR without the necessity of changing the MELCOR source code. Thus, it is possible to combine the advantages of the CFD-based Phase-Change Effective Convectivity Model (PECM) and MELCOR as an integral code. Implementing the advantages of the PECM code to MELCOR, such as the temperature distribution in the molten pool, heat flux distribution on the curved vessel wall and treatment of non-eutectic solidification, the prediction accuracy of MELCOR can be considerably improved concerning the analysis of core melt behaviour in the lower plenum during a core melt accident.
机译:直播计划在大规模3D条件和不同的重定位模式下发生严重事故的情况下调查船舶融合池行为。通过淹没反应器容器的熔体保留被视为有效的严重事故管理策略。一个问题是熔融池热传递对血管壁的热传递取决于不同的外部冷却条件。在本文中,比较了熔体的热行为,例如熔体温度,热通量和地壳轮廓,两个实时测试具有不同的外部冷却气体温度:一个具有核心沸腾条件,另一个具有副冷却条件。在两个实验中,其他测试条件,例如模拟材料,加热功率和上边界条件相似。用耦合的熔体和PECM码模拟实验结果。在KIT开发的DINAMO计划,用于实现这种耦合交换。使用DINAMO可以为核安全码熔体添加新的或增强型号,而无需改变熔体源代码。因此,可以将基于CFD的相位变化有效的对流模型(PECM)和熔体的优点组合为整体代码。实现PECM代码的优点,例如熔池中的温度分布,弯曲血管壁上的热通量分布和非共晶凝固的处理,熔体的预测精度有关核心的分析可以显着提高在核心熔体事故期间,下层增长的熔体行为。

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