Analysis of metal vessel wall ablation experiment with high temperature liquid by MPS method

Daisuke Masumura*, Yoshiaki Oka, Akifumi Yamaji, Masahiro Furuya

*この研究の対応する著者

研究成果: Conference contribution

1 被引用数 (Scopus)

抄録

In a severe accident of a light water reactor, ablation of the reactor pressure vessel (RPV) lower head by corium is a key phenomenon, which affects progression of the accident. The Moving Particle Semi- implicit (MPS) method is one of particle methods that calculate behavior of incompressible fluid by semi-implicit method. In preceding studies, MPS models have been developed to analyze phenomena such as heat conduction, phase change, natural convection, thermal stratification, and radiation heat transfer. These phenomena are expected to play key roles in the lower head ablation. This paper aims to investigate whether the MPS method is capable of analyzing the lower head ablation phenomenon, which involves complex interactions of the above mentioned phenomena. The small-scale experiment carried out at Central Research Institute of Electric Power Industry (CRIEPI) using Pb-Bi vessel and silicone oil was analyzed. The heat transfer model was modified for evaluation of heat transfer between the vessel and the oil. The results were compared both qualitatively and quantitatively with the experiment. The former is the comparison of the simulation and experiment regarding phenomena that the liquid ablates the metal vessel and discharges through the vessel wall, which showed good agreement. The latter are comparisons of the calculated liquid temperature, ablation start time and discharge start time with respect to the corresponding measurements. The analyses have shown that the MPS method is capable of analyzing ablation phenomenon qualitatively, but needs further development for quantitative prediction, including investigations on influence of the particle size used in the simulation.

本文言語English
ホスト出版物のタイトルInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
出版社American Nuclear Society
ページ7401-7413
ページ数13
9
ISBN(印刷版)9781510811843
出版ステータスPublished - 2015
イベント16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
継続期間: 2015 8 302015 9 4

Other

Other16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
国/地域United States
CityChicago
Period15/8/3015/9/4

ASJC Scopus subject areas

  • 器械工学
  • 原子力エネルギーおよび原子力工学

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