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Journal of Nuclear Science and Technology Volume 52, 2015 - Issue 2
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Original Articles

Prediction of temperature and water level in a spent fuel pit during loss of all AC power suppliesFootnote

Translation

Chihiro YanagiTechnical Support Project, Institute of Nuclear Technology, Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho, Mikata-gun, Fukui919-1205, JapanCorrespondence[email protected]
,
Michio MuraseTechnical Support Project, Institute of Nuclear Technology, Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho, Mikata-gun, Fukui919-1205, Japan
,
Yoshitaka YoshidaTechnical Support Project, Institute of Nuclear Technology, Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho, Mikata-gun, Fukui919-1205, Japan
&
Takayoshi KusunokiNuclear Power Division, The Kansai Electric Power, Co., Inc., 13-8 Goichi, Mihama-cho, Mikata-gun, Fukui919-1141, Japan
Pages 193-203 | Received 05 Jun 2014, Accepted 23 Jun 2014, Published online: 17 Jul 2014

Citations (6)

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Read on this site (1)

Mirza Mohammed Shah. (2018) Improved model for calculation of evaporation from water pools. Science and Technology for the Built Environment 24:10, pages 1064-1074.
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Articles from other publishers (5)

Mirza M Shah. (2021) Evaluation of methods for prediction of evaporation from water pools. Journal of Building Physics 45:5, pages 629-648.
Crossref
Mizra Mohammad Shah. 2021. Two‐Phase Heat Transfer. Two‐Phase Heat Transfer 279 310 .
Mirza M. Shah. (2019) Calculation of Evaporation From Fukushima Nuclear Power Plant Spent Fuel Pools. Journal of Nuclear Engineering and Radiation Science 5:4.
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Husaini Roslan, Nahrul Khair Alang Md Rashid & Muhammad Arif Sazali. (2019) Applicability of one-body model to predict thermal distribution in spent nuclear fuel pool. IOP Conference Series: Materials Science and Engineering 555:1, pages 012004.
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Chihiro Yanagi, Michio Murase & Yoichi Utanohara. (2016) Effects of Decay Heat Distribution on Water Temperature in a Spent Fuel Pit and Prediction Errors With a One-Region Model. Journal of Nuclear Engineering and Radiation Science 2:3.
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