Rchr
J-GLOBAL ID：202401000622537775   Update date: Apr. 25, 2024

Chimi Yasuhiro

チミ ヤスヒロ | Chimi Yasuhiro
Affiliation and department：
Japan Atomic Energy Agency Ageing Management Research Group, Materials and Structural Integrity Research Division, Nuclear Safety Research Center, Sector of Nuclear Safety Research and Emergency Preparedness

About Japan Atomic Energy Agency Ageing Management Research Group, Materials and Structural Integrity Research Division, Nuclear Safety Research Center, Sector of Nuclear Safety Research and Emergency Preparedness


Job title： Group Leader
Research theme for competitive and other funds  (2)：
  • 2005 - 2007 高速重イオンによる電子励起ミキシングの機構解明と複合酸化物、珪素化物への応用
  • 2004 - 2006 高エネルギー粒子線を用いた磁性体薄膜局所改質の制御と評価法の開発
Papers (86)：
  • Kuniki Hata, Satoshi Hanawa, Yasuhiro Chimi, Shunsuke Uchida. Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis. Journal of Nuclear Science and Technology. 2024. 61. 4. 448-458
  • Kuniki Hata, Satoshi Hanawa, Yasuhiro Chimi, Shunsuke Uchida, Derk H. Lister. Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurised water reactor primary coolant under irradiation (2) evaluation of electrochemical corrosion potential. Journal of Nuclear Science and Technology. 2023. 60. 8. 867-880
  • Keiko Iwata, Kuniki Hata, Tohru Tobita, Takatoshi Hirota, Hisashi Takamizawa, Yasuhiro Chimi, Yutaka Nishiyama. Evaluation of brittle crack arrest toughness for highly-irradiated reactor pressure vessel steels. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP. 2021. 1
  • Shunsuke Uchida, Yasuhiro Chimi, Shigeki Kasahara, Satoshi Hanawa, Hidetoshi Okada, Masanori Naitoh, Masayoshi Kojima, Hiroshige Kikura, Derek H. Lister. Improvement of plant reliability based on combining of prediction and inspection of crack growth due to intergranular stress corrosion cracking. Nuclear Engineering and Design. 2019. 341. 112-123
  • Shigeki Kasahara, Yasuhiro Chimi, Kuniki Hata, Koji Fukuya, Katsuhiko Fujii. Empirical equations of crack growth rates based on data fitting of neutron irradiated stainless steel under high temperature water simulating boiling water reactor core conditions. 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019. 2019. 1345-1355
ｍore...
MISC (161)：
  • 内田俊介, 端邦樹, 塙悟史, 知見康弘, 佐藤智徳. The effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation: 9. Combind analysis of water radiolysis and ECP. 日本原子力学会春の年会予稿集(CD-ROM). 2023. 2023
  • 端邦樹, 内田俊介, 塙悟史, 知見康弘, 佐藤智徳. The effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation: 8. Evaluation of the effects of OH + H <=> H + H<sub>2</sub>O reaction and its back reaction on water radiolysis. 日本原子力学会春の年会予稿集(CD-ROM). 2023. 2023
  • 内田俊介, 端邦樹, 塙悟史, 知見康弘, 佐藤智徳. The effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation: 10. Effects of boiling on combind analysis of water radiolysis and ECP. 日本原子力学会秋の大会予稿集(CD-ROM). 2023. 2023
  • 内田俊介, 端邦樹, 塙悟史, 知見康弘. The effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation (5) Effects of boric acid and lithium hydroxide on radiolysis and ECP. 日本原子力学会春の年会予稿集(CD-ROM). 2022. 2022
  • 端邦樹, 内田俊介, 塙悟史, 知見康弘. The effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation (6) Application of water radiolysis analysis to PWR primary cooling system. 日本原子力学会秋の大会予稿集(CD-ROM). 2022. 2022
ｍore...
※ Researcher’s information displayed in J-GLOBAL is based on the information registered in researchmap. For details, see here.

Return to Previous Page

TOP

BOTTOM