ROSA/LSTF test on nitrogen gas behavior during reflux condensation in PWR and RELAP5 code analyses
Author:
Affiliation:
1. Nuclear Regulation Authority, Japan
2. Japan Atomic Energy Agency
Publisher
Japan Society of Mechanical Engineers
Subject
General Medicine
Link
https://www.jstage.jst.go.jp/article/mej/5/4/5_18-00077/_pdf
Reference22 articles.
1. Hirano, M., Yonomoto, T. and Ishigaki, M., et al., Insights from review and analysis of the Fukushima Dai-ichi accident, Journal of Nuclear Science and Technology, Vol. 49, No. 1 (2012), pp. 1-17.
2. JAERI, Effect of exhausted gases on heat removal during a reactor accident, Persistent Quest-Research Activities, Japan Atomic Energy Research Institute (1995).
3. Kukita, Y., Nakamura, H., Tasaka, K. and Chauliac, C., Nonuniform steam generator U-tube flow distribution during natural circulation tests in ROSA-IV large scale test facility, Nuclear Science and Engineering, Vol. 99, No. 4 (1988), pp. 289-298.
4. Liu, T.-J., Reflux condensation behavior in a U-tube steam generator with or without noncondensables, Nuclear Engineering and Design, Vol. 204, No. 1-3 (2001), pp. 221-232.
5. Loomis, G. G. and Soda, K., Results of the Semiscale Mod-2A natural circulation experiments, NUREG/CR-2335 (1982).
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