学術誌/Scientific Journal

1.Sunghyon Jang, Takashi Takata and Akira Yamguchi, Numerical Analysis of Self-wastage Phenomena Caused by Sodium-Water Reaction in Sodium-Cooled Fast Reactor through Simulant Experiment, 【PDF】
Journal of Energy and Power Engineering, Vol.9, No. 6, pp. 539-547, 2015. doi: 10.17265/1934-8975/2015.06.004.

2.Sunghyon, Jang, Takashi Takata, Akira Yamaguchi, Akihiro Uchibori, Akikazu Kurihara and Hiroyuki Ohshima, Numerical approach for quantification of selfwastage phenomena in sodium-cooled fast reactor, 【PDF】
Nuclear Engineering and Technology, Volume 47, No. 6, pp. 700-711. doi:10.1016/j.net.2015.06.008.

3.Sunghyon Jang, Takashi Takata and Akira Yamguchi, Numerical Design Study of Self-wastage Experiment Using Simulant Material in Sodium Fast Reactor,
Nuclear Engineering and Technology, doi:10.1016/ j.net.2015.12.006. (In press)

Xiaoyu Zheng, et al., "Quantitative common cause failure modeling for auxiliary feedwater system involving the seismicinduced degradation of flood barriers" 【PDF】
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.51, No.3, pp.332-342, 2014

Xiaoyu Zheng, et al., "Probabilistic common cause failure modeling for auxiliary feedwater system after the introduction of flood barriers" 【PDF】
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.50, No.8, pp.828-836, 2013

Xiaoyu Zheng, et al., "α-Decomposition for estimating parameters in common cause failure modeling based on causal inference" 【PDF】
Reliability Engineering and System Safety 116, 2013, 20-27

Makoto SHIBAHARA, et al., "Numerical study on thermal stratification phenomena in upper plenum of LMFBR “MONJU”" 【PDF】
Nuclear Engineering and Design 258, 2013 226.234

Toshinori MATSUMOTO, et al., "Investigation of correlation diagram between heat transfer coefficient and void fraction under sodium-water reaction" 【PDF】
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.49, No.6, pp.610-617, 2012

Akira YAMAGUCHI, et al., "Gas entrainment allowance level at free surface and gas dynamic behavior of sodium-cooled fast reactor" 【PDF】
Nuclear Engineering and Design 241, 2011 1627.1635

Toshinori MATSUMOTO, et al., "Estimation of Heat Transfer Coefficient and Flow Characteristics on Heat Transfer Tube in Sodium-Water Reaction" 【PDF】
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 48, No. 3, p.315-321, 2011

Takashi TAKATA, et al., "Development of Sub-Channel Analysis Tool for TRU Fuel Fabrication" 【PDF】
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 47, No. 9, p.839-848, 2010

Takashi TAKATA, et al., "Computational Methodology of Sodium-Water Reaction Phenomenon in Steam Generator of Sodium-Cooled Fast Reactor" 【PDF】
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.46, No.6, pp.613-623, 2009

Akira YAMAGUCHI, et al., "Numerical Prediction and Optimization of Depressurized Sodium-Water Reaction Experiment With Counterflow Diffusion Flame" 【PDF】
Journal of Engineering for Gas Turbines and Power, Vol.131, Issue 2, 022907(7pages), March 2009

Takashi TAKATA, et al., "Computational Sensitivity Study on Sodium-Water Reaction Phenomenon" 【PDF】
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.43, No.5, pp.514-525, 2006