An Experimental study on local fuel-coolant interactions by delivering water into a simulated molten fuel pool
Cheng, S.; 松場 賢一; 磯崎 三喜男; 神山 健司; 鈴木 徹; 飛田 吉春
Cheng, S.; Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Suzuki, Toru; Tobita, Yoshiharu
Analyses of severe accidents for SFRs have indicated that the accident might proceed into a transition phase where a large whole-core-scale pool containing sufficient fuel to exceed prompt criticality by fuel compaction might be formed. Local fuel-coolant interaction (FCI) in the pool is regarded as one of the probable initiators that could lead to such compactive fluid motions. To clarify the mechanisms underlying this interaction, in this study a series of experiments was conducted by delivering a given quantity of water into a simulated molten fuel pool. Based on the experimental data obtained from a variety of conditions, interaction characteristics including the pressure-buildup as well as resultant mechanical energy release and its conversion efficiency, is checked and compared. It is found that under our experimental conditions the water volume, melt temperature and water release position have remarkable impact on the interaction, while the role of water subcooling seems to be less prominent. The analyses also suggest that the pressurization and resultant mechanical energy release during local FCIs should be intrinsically limited, due to an observed suppressing role caused by the increasing of coolant volume entrapped within the pool as well as the transition of boiling mode. Evidence and data from this work will be utilized for verifications of advanced fast reactor safety analysis codes.
使用言語 : English
掲載資料名 : Nuclear Engineering and Design
: 275
ページ数 : p.133 - 141
発行年月 : 2014/08
出版社名 : Elsevier
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論文URL :
キーワード : no keyword
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受委託・共同研究相手機関 :
登録番号 : AA20130846
抄録集掲載番号 : 42000902
論文投稿番号 : 14560
Accesses  (From Jun. 2, 2014)
- Accesses
分野:Nuclear Science & Technology
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