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Uchibori, Akihiro; Yanagisawa, Hideki*; Takata, Takashi; Li, J.*; Jang, S.*
Mechanical Engineering Journal (Internet), 7(3), p.19-00548_1 - 19-00548_11, 2020/06
Evaluation of occurrence possibility of tube failure propagation under sodium-water reaction accident is an important issue. In this study, a numerical analysis method to predict occurrence of failure propagation by overheating rupture was constructed to expand application range of an existing computer code. Applicability of the method was constructed through the numerical analysis of the experiment on water vapor discharging in liquid sodium. To improve the evaluation accuracy for the temperature distribution, a Lagrangian particle model for simulating reacting jet was also developed as an alternative method and its basic function was confirmed.
Uchibori, Akihiro; Yanagisawa, Hideki*; Takata, Takashi; Ohshima, Hiroyuki
Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 6 Pages, 2018/11
Evaluation of occurrence possibility of tube failure propagation under sodium-water reaction accident is an important issue. In this study, a numerical analysis method to predict occurrence of failure propagation by overheating rupture was constructed to expand application range of an existing computer code. Applicability of the method was constructed through the numerical analysis of the experiment on water vapor discharging in liquid sodium.
Uchibori, Akihiro; Takata, Takashi; Yanagisawa, Hideki*; Li, J.*; Jang, S.*
Proceedings of 2018 ANS Winter Meeting and Nuclear Technology Expo; Embedded Topical International Topical Meeting on Advances in Thermal Hydraulics (ATH 2018) (USB Flash Drive), p.1289 - 1294, 2018/11
Evaluation of occurrence possibility of tube failure propagation under sodium-water reaction accident is an important issue. In this study, a numerical analysis method to predict occurrence of failure propagation by overheating rupture was constructed to expand application range of an existing computer code. Applicability of the method was constructed through the numerical analysis of the experiment on water vapor discharging in liquid sodium. To improve the evaluation accuracy for the temperature distribution, a Lagrangian particle model for simulating reacting jet was also developed as an alternative method and its basic function was confirmed.
Kojima, Saori*; Uchibori, Akihiro; Takata, Takashi; Ohno, Shuji; Fukuda, Takeshi*; Yamaguchi, Akira*
Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 8 Pages, 2016/11
Analytical evaluation on a self-wastage phenomenon at heat transfer tubes in the steam generator of sodium cooled fast reactors has been performed by using the sodium-water reaction analysis code SERAPHIM. In this study, a fluid-structure thermal coupling model was developed and incorporated in the SERAPHIM code to evaluate heat transfer between the sodium-side reacting flow and the outer surface of the heat transfer tube. The effect of the fluid-structure thermal coupling model on the temperature field was demonstrated through the numerical analyses.
Uchibori, Akihiro; Watanabe, Akira*; Takata, Takashi; Ohno, Shuji; Ohshima, Hiroyuki
Proceedings of OECD/NEA & IAEA Workshop on Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation (CFD4NRS-6) (Internet), 11 Pages, 2016/09
For assessment of the wastage environment under tube failure accident in a steam generator of sodium-cooled fast reactors, a mechanistic computer code called SERAPHIM calculating compressible multicomponent multiphase flow with sodium-water chemical reaction has been developed. The original SERAPHIM code is based on the finite difference method. In this study, unstructured mesh-based numerical method was developed and introduced into the SERAPHIM code to advance a numerical accuracy for the complex-shaped domain including multiple heat transfer tubes. Validity of the unstructured mesh-based SERAPHIM code was investigated through the analysis of an under expanded jet experiment. The calculated pressure profile showed good agreement with the experimental data. Numerical analysis of water vapor discharging into liquid sodium was also performed. It was demonstrated that the proposed numerical method could be applicable to evaluation of the sodium-water reaction phenomenon.
Kido, Kentaro; Hata, Kuniki; Maruyama, Yu; Nishiyama, Yutaka; Hoshi, Harutaka*
NEA/CSNI/R(2016)5 (Internet), p.204 - 212, 2016/05
Uchibori, Akihiro; Kurihara, Akikazu; Ohshima, Hiroyuki
AIP Conference Proceedings 1702, p.040010_1 - 040010_4, 2015/12
Times Cited Count：0 Percentile：0.00(Physics, Applied)A Multiphysics analysis system was newly developed to evaluate possibility of failure propagation occurrence in a steam generator of sodium-cooled fast reactors. The system consists of the computer codes, SERAPHIM, TACT, and RELAP5. The SERAPHIM code calculates the multicomponent multiphase flow involving sodium-water chemical reaction. Applicability of the SERAPHIM code was confirmed through the analyses of the basic experiment and the experiment on water vapor discharging in liquid sodium. The TACT code was developed to calculate heat transfer from the reacting jet to the adjacent tube and to predict the tube failure occurrence. The numerical models of the TACT code were verified through some related experiments. The RELAP5 code evaluates thermal hydraulic behavior of water inside the tube. The original heat transfer correlations were corrected for the rapidly heated tube. The developed system enabled us to evaluate the wastage environment and possibility of failure propagation.
Yamauchi, Michinori*; Hori, Junichi*; Ochiai, Kentaro; Sato, Satoshi; Nishitani, Takeo; Kawasaki, Hiromitsu*
Fusion Engineering and Design, 81(8-14), p.1577 - 1582, 2006/02
Times Cited Count：1 Percentile：9.69(Nuclear Science & Technology)no abstracts in English
Nagase, Fumihisa; Otomo, Takashi; Uetsuka, Hiroshi
JAERI-Research 2001-009, 21 Pages, 2001/03
JAERI-Research-2001-009.pdf:2.93MB
no abstracts in English
Nagaya, Yasunobu; Nakagawa, Masayuki; Mori, Takamasa
Journal of Nuclear Science and Technology, 35(1), p.6 - 19, 1998/01
Times Cited Count：3 Percentile：31.90(Nuclear Science & Technology)no abstracts in English
Uetsuka, Hiroshi; Nagase, Fumihisa;
Journal of Nuclear Materials, 246(2-3), p.180 - 188, 1997/00
Times Cited Count：14 Percentile：71.78(Materials Science, Multidisciplinary)no abstracts in English
Nagase, Fumihisa; Uetsuka, Hiroshi;
JAERI-Research 95-085, 48 Pages, 1995/11
JAERI-Research-95-085.pdf:2.67MB
no abstracts in English
Sugimoto, Masaki; ; Okamura, K.*; Seguchi, Tadao
Journal of the American Ceramic Society, 78(4), p.1013 - 1017, 1995/00
Times Cited Count：78 Percentile：94.04(Materials Science, Ceramics)no abstracts in English
Okoshi, Minoru; Yoshimori, Michiro
Proc. of 3rd Japan-Russia Joint Symp. on Radiation Safety, 0, p.75 - 85, 1995/00
no abstracts in English
; ; Saido, Masahiro; Ogiwara, Norio;
Japanese Journal of Applied Physics, 32(9A), p.3968 - 3974, 1993/09
Times Cited Count：15 Percentile：62.54(Physics, Applied)no abstracts in English
; ; ; ; ; ; Kimura, Hideo; Munakata, Masahiro
Nihon Genshiryoku Gakkai-Shi, 34(4), p.342 - 364, 1992/04
Times Cited Count：2 Percentile：27.22(Nuclear Science & Technology)no abstracts in English
Sagara, Akio*; ; Sasaki, Teikichi; Baba, Yuji
Nuclear Instruments and Methods in Physics Research B, 44, p.373 - 376, 1990/00
Times Cited Count：4 Percentile：53.84(Instruments & Instrumentation)no abstracts in English
; ; ; ; ;
JAERI-M 86-016, 51 Pages, 1986/02
no abstracts in English
; ; ;
JAERI-M 9912, 21 Pages, 1982/01
no abstracts in English
; ; ; ; ; ; ;
JAERI-M 9901, 14 Pages, 1982/01
no abstracts in English
