Rchr
J-GLOBAL ID：202101001905089307
Update date: Mar. 31, 2024
Shimomura Kenta
シモムラ ケンタ | Shimomura Kenta
Affiliation and department：
Research field (1)：
Machine materials and mechanics
Papers (3)：
-
Sato Ikken, Yoshikawa Shinji, Yamashita Takuya, Shimomura Kenta, Cibula M.*, Mizokami Shinya*. MAAP code analysis for the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 1 and comparison of the results among Units 1 to 3. Nuclear Engineering and Design. 2024. 422. 113088\_1-113088\_24
-
Sato Ikken, Yoshikawa Shinji, Yamashita Takuya, Shimomura Kenta, Cibula M.*, Mizokami Shinya*. MAAP code analysis focusing on the fuel debris conditions in the lower head of the pressure vessel in Fukushima-Daiichi Nuclear Power Station Unit 3. Nuclear Engineering and Design. 2023. 414. 112574\_1-112574\_20
-
Shimomura Kenta, Kato Shoichi, Wakai Takashi, Ando Masanori, Hirose Yuichi*, Sato Kenichiro*. Creep-fatigue tests of double-end notched bar made of Mod.9Cr-1Mo steel. Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM). 2015. 9
MISC (3)：
-
Yamashita Takuya, Shimomura Kenta, Nagae Yuji, Yamaji Akifumi*, Mizokami Shinya, Mitsugi Takeshi, Koyama Shinichi. Summary results of subsidy program for the "Project of Decommissioning, Contaminated Water and Treated Water Management (Development of Analysis and Estimation Technologies for Characterization of Fuel Debris (Development of Estimation Technologies of RPV Damaged Condition, etc.) in 2022JFY. Hairo, Osensui, Shorisui Taisaku Jigyo Jimukyoku Homu Peji (Internet). 2023. 53
-
Shimomura Kenta, Yamashita Takuya, Nagae Yuji. Collection of strength characteristic data used for analysis evaluation in reactor pressure vessel and in-core structures in accident. JAEA-Data/Code 2022-012. 2023. 270
-
Okafuji Takashi*, Miura Kazuhiro*, Sago Hiromi*, Murakami Hisatomo*, Kubo Koji*, Sato Kenichiro*, Wakai Takashi, Shimomura Kenta. Study on the seismic buckling evaluation method for Mod. 9Cr-1Mo steel cylindrical vessel. Nihon Kikai Gakkai M\&M 2017 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet). 2017. 591-595
Lectures and oral presentations (18)：
-
Estimation of RPV damage and fuel debris relocation behavior in the PCV at Fukushima Daiichi Nuclear Power Station, 1; Development of 3D estimation diagrams and the debrisEye
(日本原子力学会2024年春の年会)
-
Clarification of debris formation conditions on the basis of the sampling data and experimental study using simulated fuel debris, 5; Damage behavior of lower plenum due to reaction with metallic debris
(日本原子力学会2024年春の年会)
-
Estimation of RPV damage and fuel debris relocation behavior in the PCV at Fukushima Daiichi Nuclear Power Station, 2; Fukushima Daiichi Nuclear Power Plant unit2 evaluation of containment behavior under the severe accident condition
(日本原子力学会2024年春の年会)
-
Estimation of RPV damage and fuel debris relocation behavior in the PCV at Fukushima Daiichi Nuclear Power Station, 5; Evaluation of temperature behavior of CRD Housing of Unit 2 during accident progress
(日本原子力学会2024年春の年会)
-
Estimation of RPV damage and fuel debris relocation behavior in the PCV at Fukushima Daiichi Nuclear Power Station, 4; RPV lower head penetration failure test due to eutectic reaction (ELSA-3)
(日本原子力学会2024年春の年会)
ｍore...
Return to Previous Page
