著者

富田 康弘 芳賀 和夫 Tomita Yasuhiro Haga Kazuo

出版者

筑波大学菅平高原実験センター

雑誌

菅平高原実験センター研究報告 (ISSN:09136800)

巻号頁・発行日

no.12, pp.35-54, 1992-03-10

著者

HAGA Kazuo Itoh Tomomichi ENDO Hiroshi SHINDO Yoshihisa BAGLIETTO Emilio SASAKI Yasutomo IRIKURA Motoki

出版者

一般社団法人 日本機械学会

雑誌

Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE

巻号頁・発行日

vol.2011, pp._ICONE1943, 2011

被引用文献数

1

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When heat-transfer tube failure occurred in SG of LMFBR and the steam leak rate is medium (some 10s g/s-some kg/s), overheating tube rupture would be caused due to the accelerated high-temperature creep in the heat transfer tubes surrounded by the high temperature products of sodium-water reaction (SWR). However, the detailed analysis code to analyze this phenomenon is not established. Adopting a Computational Fluid Dynamics (CFD) code would be a promising candidate for that perpose. At first in developing the analysis tool using a CFD code, STAR-CCM+ and LHM (Locally Homogeneous Multi-phase) model was adapted considering the appropriateness to SWR and the merits of homogeneous model, that is, the light load of computing resources and the minimum usage of models whose applicability is remained in argument. In the second step, a concept of interfacial area density was introduced to the submerged jet analysis. Furthermore, a sodium-water reaction model was added as an external function of the CDF code. A trial calculation was made to the basic SWR experimental data obtained by Hobbes et al. The analysis of the temperature profile formed in the jet region showed a good agreement with the experiment by properly choosing parameters such as Lewis number and the heat transfer coefficient on the sodium droplet. No marked difference was seen between the two-dimensional analysis and the three-dimensional analysis.