Rchr
J-GLOBAL ID：202001008237890490
Update date: Apr. 16, 2024
Miyoshi Koji
ミヨシ コウジ | Miyoshi Koji
Affiliation and department：
Job title：
副主任研究員
Homepage URL (1)：
http://www.inss.co.jp/institute/nuclear_research/plant_aging/thermal.html
Research field (3)：
Machine materials and mechanics
, Fluid engineering
, Nuclear engineering
Research keywords (4)：
Thermal fatigue
, Thermal hydraulics
, 構造評価
, Nuclear engineering
Papers (40)：
-
Koji Miyoshi. Heat transfer process for penetration flow into a branch pipe causing thermal fatigue at a T-junction. Nuclear Engineering and Design. 2024
-
Koji Miyoshi. Temperature characteristics of penetration flow into a branch pipe causing thermal fatigue at a T-junction. Nuclear Engineering and Design. 2023. 403. 112157-112157
-
Tatsuya Tsuneyoshi, Yoichi Utanohara, Koji Miyoshi, Yoshiyuki Tsuji. Numerical calculation of heat transport process in complex flow field and comparison with experimental measurement. The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS 13). 2022. N13P134
-
Miyoshi, K., Kamaya, M. Fatigue Life Assessment for Variable Strain in a Mixing Tee by Use of Effective Strain Range. Journal of Pressure Vessel Technology, Transactions of the ASME. 2022. 144. 1
-
Koji Miyoshi, Masayuki Kamaya. Effects of a Single Overload on Fatigue Crack Growth of Type 316 Stainless Steel. Proceedings of ASME 2021 Pressure Vessels & Piping Conference. 2021. Volume 2
ｍore...
MISC (59)：
-
Koji MIYOSHI, Masayuki KAMAYA. Thermal Fatigue Assessment for Penetration Flow into a Branch Pipe of Mixing Tee. The Proceedings of the National Symposium on Power and Energy Systems. 2022. 2022.26. E222-E222
-
Numerical simulation of impinged penetration into T-junction branch lines. INSS journal : Journal of the Institute of Nuclear Safety System. 2021. 28. 75-82
-
Yoichi UTANOHARA, Koji MIYOSHI, Masayuki KAMAYA. Thermal Fatigue Assessment for Penetration Flow into a Branch Pipe of Mixing Tee. The Proceedings of the National Symposium on Power and Energy Systems. 2021. 2021.25. D212-D212
-
Koji MIYOSHI, Yoichi UTANOHARA, Masayuki KAMAYA. Thermal Fatigue Assessment for Penetration Flow into a Branch Pipe of Mixing Tee. The Proceedings of the National Symposium on Power and Energy Systems. 2021. 2021.25. D211-D211
-
Heat transfer coefficient suitable for thermal fatigue assessment at a T-junction. INSS journal : Journal of the Institute of Nuclear Safety System. 2021. 28. 83-94
ｍore...
Lectures and oral presentations (5)：
-
配管合流・分岐部 に生じる熱疲労防止のための評価に関する研究
(日本伝熱学会東海支部 第 30 回伝熱コロキウム 2024)
-
Assessment of fatigue damage at the pipe inner surface in a mixing tee
(Workshop on material service safety of high temperature equipment in power plants 2019)
-
流体温度ゆらぎによる熱疲労評価手法の検討
(日本伝熱学会関西支部 第 25 期 第 1 回講演討論会 2018)
-
Thermal stress investigation by wall temperature measurements for mixing flow at T-Junction
(Fourth International Conference on Fatigue of Nuclear Reactor Components 2015)
-
T字合流管での熱疲労評価法を改善するための熱応力特性
(数値流体力学の原子炉熱流動への応用に関する国際シンポジウム 2015)
Education (2)：
- 2013 - 2015 神戸大学大学院 工学研究科機械工学専攻
- 1997 - 1999 神戸大学大学院 自然科学研究科機械工学専攻
Professional career (1)：
Work history (2)：
- 2009/08 - 現在 株式会社 原子力安全システム研究所
- 1999/04 - 現在 関西電力株式会社
Committee career (4)：
- 2020/11 - 現在 日本機械学会 原子力専門委員会 疲労評価分科会 疲労評価手法作業会
- 2019/07 - 2021/03 関西原子力懇談会 原子力関係科学技術の基礎的研究の動向調査委員会
- 2015/04 - 2019/03 日本溶接協会 原子力研究委員会 疲労ナレッジQ&A小委員会
- 2015/04 - 2017/03 日本機械学会 熱疲労評価技術の高度化と知識基盤構築に関する研究分科会
Association Membership(s) (3)：
日本材料学会
, 日本原子力学会
, 日本機械学会
