Changes in sulfur metabolism in mouse brains following radon inhalation

Kanzaki, Norie; Sakoda, Akihiro; Kataoka, Takahiro*; Sun, L.*; Tanaka, Hiroshi; Otsu, Iwao*; Yamaoka, Kiyonori*

International Journal of Environmental Research and Public Health, 19(17), p.10750_1 - 10750_14, 2022/09

https://doi.org/10.3390/ijerph191710750

Reactive sulfur species (RSS) involve oxidative stress deeply and contribute anti-inflammatory effect, but no studied have focused on RSS changes after irradiation. In this study, we comprehensively analyzed the metabolites, focusing on RSS in mouse brain following radon inhalation. The ratio of oxidized glutathione to reduced glutathione and proportion of RSS in GSH or cysteine increased by radon inhalation. The sulfur ion might bind to GSH or cysteine chemically under conditions of oxidative stress, even at very low-dose exposure. We performed the overall assessment of high-dimensional data by applying machine learning and showed the specific characteristics of the effects by the exposure conditions. Our results suggested that RSS could produce a biological defense against oxidative stress following radon inhalation.

Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs

Takeda, Takeshi; Otsu, Iwao

Nuclear Engineering and Technology, 50(6), p.829 - 841, 2018/08

https://doi.org/10.1016/j.net.2018.05.005

RELAP5 uncertainty evaluation using ROSA/LSTF test data on PWR 17% cold leg intermediate-break LOCA with single-failure ECCS

Takeda, Takeshi; Otsu, Iwao

Annals of Nuclear Energy, 109, p.9 - 21, 2017/11

https://doi.org/10.1016/j.anucene.2017.05.007

ROSA/LSTF test on nitrogen gas behavior during reflux cooling in PWR and RELAP5 post-test analysis

Takeda, Takeshi; Otsu, Iwao

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 11 Pages, 2017/07

ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses

Takeda, Takeshi; Otsu, Iwao

Mechanical Engineering Journal (Internet), 2(5), p.15-00132_1 - 15-00132_15, 2015/10

http://doi.org/10.1299/mej.15-00132

ROSA/LSTF experiment on AM measures during a PWR station blackout transient with pump seal leakage and RELAP5 POST-TEST analysis

Takeda, Takeshi; Otsu, Iwao

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 10 Pages, 2015/05

OECD/NEA ROSA project experiment on steam condensation in PWR horizontal legs during large-break LOCA

Takeda, Takeshi; Otsu, Iwao; Nakamura, Hideo

Journal of Energy and Power Engineering, 7(6), p.1009 - 1022, 2013/06

http://www.davidpublishing.com/show.html?13295

OECD/NEA ROSA Project experiment on steam condensation in PWR horizontal legs during large-break LOCA

Takeda, Takeshi; Otsu, Iwao; Nakamura, Hideo

Proceedings of 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference (ICONE-20 & POWER 2012) (DVD-ROM), 11 Pages, 2012/07

Thermal-hydraulic research on future reactor systems in the ROSA program at JAERI

Yonomoto, Taisuke; Otsu, Iwao; Svetlov, S.*

Proceedings of 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-3), p.521 - 528, 2002/00

A research project is being conducted at the Japan Atomic Energy Research Institute on thermal hydraulics for the future reactor systems. The present paper provides the belief description of the project, followed by two recent topics: the natural circulation in the PWR loop and the condensation heat transfer for a passive cooling system. For the first topic, we discuss the importance of the modeling of the nonuniform flow behavior among SG U-tubes for the assessment of the long-term decay heat removal systems relying on the SG secondary side cooling. Such a system is planned to be used in APWR+, a Japanese next-generation PWR. The condensation heat transfer was investigated using the data obtained at the SPOT test facility in Russia. The results have shown that the measured heat transfer rates on the inner surface of the tube consisting of several bends and short straight sections can be predicted using the existing correlations with the accuracy of several percentage, although the correlations are based typically on the data taken using relatively long straight tube.

ROSA/LSTF experiments on low-pressure natural circulation heat removal for next-generation PWRs

Yonomoto, Taisuke; Otsu, Iwao

Proceedings of 12th Pacific Basin Nuclear Conference (PBNC 2000), Vol.1, p.317 - 329, 2000/00

no abstracts in English