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Watanabe, Nao; Yamashita, Susumu; Uesawa, Shinichiro; Nishihara, Kenji; Yoshida, Hiroyuki
Proceedings of 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) (Internet), p.3522 - 3534, 2023/08
Accelerator-driven system (ADS), the coolant of which is lead-bismuth eutectic (LBE), has been designed by Japan Atomic Energy Agency. Estimating corrosion rate at the wall surface of LBE channel is an important issue in considering safety and the life of the entire structure. The corrosion rate depends on state of oxygen layers forming at the material surface. Therefore, this study aims to develop a method to evaluate the corrosion rate in ADS for the design study by estimation of the oxide layer growth and dissolution (OLGD) rates by means of numerical analysis. The OLGD rates, mass transfer rates of oxygen and iron between the material and LBE and advection-diffusion rates of them in LBE depend on each other. Therefore, in order to estimate OLGD rates, the three numerical analysis models should be coupled. For the advection-diffusion calculation, to use CFD code should be reasonable approach to analyze complex flow in ADS, while for the OLGD and the mass transfer calculation, to use some correlation equations should be reasonable because their scales are much smaller than the advection-diffusion. The present work has developed the analysis method of OLGD rates by using JUPITER code, which is CFD code developed in JAEA. In terms of the correlation equations of OLGD and mass transfer rates, existing models used in a previous study were used with modified.
Tanaka, Shingo*; Yokota, Hideharu; Ono, Hirokazu; Nakayama, Masashi; Fujita, Tomoo; Takiya, Hiroaki*; Watanabe, Naoko*; Kozaki, Tamotsu*
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05
Yabe, Takashi*; Utsumi, Takayuki*
Computational Fluid Dynamics Journal, 9(3), p.185 - 193, 2000/10
no abstracts in English
Takeda, Seiji; Kimura, Hideo; Moltyaner, G. L.*; Klukas, M. H.*
Proceedings of 7th International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '99) (CD-ROM), 7 Pages, 1999/00
no abstracts in English
Klukas, M. H.*; Moltyaner, G. L.*; Takeda, Seiji; Yamazaki, L. S.*; Kozter, T. G.*
AECL-RC-2132, p.1 - 42, 1998/08
no abstracts in English
Yamazawa, Hiromi
Journal of Nuclear Science and Technology, 33(1), p.69 - 77, 1996/01
Times Cited Count：5 Percentile：44.69(Nuclear Science & Technology)no abstracts in English
Kimura, Hideo; Takahashi, Tomoyuki; ; Matsuzuru, Hideo
Journal of Nuclear Science and Technology, 32(3), p.206 - 217, 1995/03
Times Cited Count：4 Percentile：42.75(Nuclear Science & Technology)no abstracts in English
Kimura, Hideo
JAERI-M 92-115, 48 Pages, 1992/08
no abstracts in English
Iijima, Kazuki; Fujiwara, Kenso; Matoba, Daisuke*; Sasaki, Takayuki*
no journal, ,
Depth profiles of radionuclides discharged to the environment of Fukushima was obtained in the forest soil just nearby the Fukushima Daiichi Nuclear Power Station (FDNPS). According to characteristics of the depth profile, Pu-238 was originated from the FDNPS accident, while Pu-239+240 was mainly originated from global fallout. Comparing depth profiles attributed by the accident and global fallout can give understanding on the migration behavior of Pu in subsurface soil during decades. In this study, advection-dispersion model was applied to evaluate the depth profiles of Pu isotopes. The Kd values for global fallout Pu-239+240 agreed with those of Fukushima Pu-238 within around factor 3. Therefore, migration behavior of Pu could be understood by the advection-dispersion model.
