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首页> 外文期刊>Progress in Nuclear Energy >Lumped-parameter simulations of wall condensation and sump evaporation under typical thermal-hydraulic conditions of nuclear reactor containment severe accident
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Lumped-parameter simulations of wall condensation and sump evaporation under typical thermal-hydraulic conditions of nuclear reactor containment severe accident

机译：核反应堆安全壳严重事故的典型热工条件下壁面凝结和油底壳蒸发的集总参数模拟

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摘要

During the course of a severe accident in a Pressurized Water Reactor, pressurization of the containment occurs and hydrogen can be produced by the reactor core oxidation and distributed in the containment according to natural, mixed and forced convection flows induced by break flow, wall condensation and spray systems used in some reactors' containment to prevent overpressure. Because of these phenomena, water can be collected in the sump containment, inducing further heat and mass exchanges between the sump surface and the atmosphere. Considering the large volume of the reactor containment, LP (OD) codes are preferred to CFD calculations, which still remain a very challenging task to compute. The French IRSN has tested different tools for containment studies with lumped-parameter codes and the reference code is now ASTEC/CPA, so that mainly results of this code will be presented here. This paper focuses mainly on several IRSN tests especially developed for containment studies and the above mentioned thermal-hydraulical phenomena. The objective of this paper is to present the validations performed with LP codes on these different experimental tests. Experiments on the TOSQAN facility are considered.
机译：在压水反应堆发生严重事故的过程中，对安全壳进行加压，反应堆堆芯氧化会产生氢气，并根据断裂流，壁冷凝水和自然对流产生的自然对流，混合对流和强制对流将氢分配到安全壳内。一些反应堆安全壳中使用的喷雾系统，以防止过压。由于这些现象，水会被收集在集水池的围护中，从而在集水池的表面和大气之间引发更多的热量和质量交换。考虑到反应堆安全壳的体积较大，LP（OD）代码比CFD计算更可取，而CFD计算仍然是一项非常具有挑战性的任务。法国IRSN已使用集总参数代码测试了用于围堵研究的不同工具，现在的参考代码为ASTEC / CPA，因此这里将主要介绍此代码的结果。本文主要针对几种IRSN测试，这些测试是专门为密闭性研究和上述热工现象而开发的。本文的目的是介绍在这些不同的实验测试中使用LP代码进行的验证。考虑在TOSQAN设施上进行的实验。

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  • 来源
    《Progress in Nuclear Energy》 |2014年第11期|11-19|共9页
  • 作者

    J. Malet; T. Gelain;

  • 作者单位

    Institut de Radioprotection et de Surete Nucleaire (IRSN), PSN-RES, SCA, LEMAC, 91192 Gif-sur-Yvette, France;

    Institut de Radioprotection et de Surete Nucleaire (IRSN), PSN-RES, SCA, LEMAC, 91192 Gif-sur-Yvette, France;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Containment; Condensation; Evaporation; Sump; TOSQAN; ASTEC;

    机译：遏制;缩合;蒸发;污水坑;TOSQAN;科技;

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