Takuya Yamashita - My portal

Profile Information

Affiliation: Assistant Princupal Researcher, Japan Atomic Energy Agency
: Research Institute for Science and Engineering, Waseda University

researchmap Member ID: R000021799

Awards

Papers

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

Sato Ikken, Yoshikawa Shinji, Yamashita Takuya, Shimomura Kenta, Cibula M.*, Mizokami Shinya*

Nuclear Engineering and Design, 414 112574\_1-112574\_20, Dec, 2023 Peer-reviewed
Comprehensive analysis and evaluation of Fukushima Daiichi Nuclear Power Station Unit 3

Yamashita Takuya, Honda Takeshi*, Mizokami Masato*, Nozaki Kenichiro*, Suzuki Hiroyuki*, Pellegrini M.*, Sakai Takeshi*, Sato Ikken, Mizokami Shinya*

Nuclear Technology, 209(6) 902-927, Jun, 2023 Peer-reviewed
MAAP code analysis focusing on the fuel debris condition in the lower head of the pressure vessel in Fukushima-Daiichi Nuclear Power Station Unit 2

Sato Ikken, Yoshikawa Shinji, Yamashita Takuya, Cibula M.*, Mizokami Shinya*

Nuclear Engineering and Design, 404 112205\_1-112205\_21, Apr, 2023 Peer-reviewed
The Experimental and simulation results of LIVE-J2 test; Investigation on heat transfer in a solid-liquid mixture pool

Madokoro Hiroshi, Yamashita Takuya, Gaus-Liu X.*, Cron T.*, Fluhrer B.*, Sato Ikken, Mizokami Shinya*

Nuclear Technology, 209(2) 144-168, Feb, 2023 Peer-reviewed
BWR lower head penetration failure test focusing on eutectic melting

Yamashita Takuya, Sato Takumi, Madokoro Hiroshi, Nagae Yuji

Annals of Nuclear Energy, 173 109129\_1-109129\_15, Aug, 2022 Peer-reviewed
Post-test analyses of the CMMR-4 test

Yamashita Takuya, Madokoro Hiroshi, Sato Ikken

Journal of Nuclear Engineering and Radiation Science, 8(2) 021701\_1-021701\_13, Apr, 2022 Peer-reviewed
Ten years of Fukushima Dai-ichi post-accident research on the degradation phenomenology of the BWR core components

Pshenichnikov A., Shibata Hiroki, Yamashita Takuya, Nagae Yuji, Kurata Masaki

Journal of Nuclear Science and Technology, 59(3) 267-291, Mar, 2022 Peer-reviewed
LIVE-J1 experiment on debris melting behavior toward understanding late in-vessel accident progression of the Fukushima Daiichi Nuclear Power Station

Madokoro Hiroshi, Yamashita Takuya, Sato Ikken, Gaus-Liu X.*, Cron T.*, Fluhrer B.*, Stangle R.*, Wenz T.*, Vervoortz M.*, Mizokami Shinya

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16, Mar, 2022 Peer-reviewed
Comprehensive analysis and evaluation of Fukushima Daiichi Nuclear Power Station Unit 2

Yamashita Takuya, Sato Ikken, Honda Takeshi*, Nozaki Kenichiro*, Suzuki Hiroyuki*, Pellegrini M.*, Sakai Takeshi*, Mizokami Shinya*

Nuclear Technology, 206(10) 1517-1537, Oct, 2020 Peer-reviewed
Development of experimental technology for simulated fuel-assembly heating to address core-material-relocation behavior during severe accident

Abe Yuta, Yamashita Takuya, Sato Ikken, Nakagiri Toshio, Ishimi Akihiro

Journal of Nuclear Engineering and Radiation Science, 6(2) 021113\_1-021113\_9, Apr, 2020 Peer-reviewed
The CMMR program; BWR core degradation in the CMMR-4 test

Yamashita Takuya, Sato Ikken

Proceedings of 9th Conference on Severe Accident Research (ERMSAR 2019) (Internet), 13, Mar, 2019 Peer-reviewed
Mechanical investigation on interface failure mechanisms of dissimilar welded joints

Yamashita Takuya, Yamashita Hayato, Nagae Yuji

Tetsu To Hagane, 105(1) 96-104, Jan, 2019 Peer-reviewed
Development of experimental technology for simulated fuel-assembly heating to address core-material-relocation behavior during severe accident

Abe Yuta, Yamashita Takuya, Sato Ikken, Nakagiri Toshio, Ishimi Akihiro, Nagae Yuji

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 9, Jul, 2018 Peer-reviewed
The CMMR program; BWR core degradation in the CMMR-1 and the CMMR-2 tests

Yamashita Takuya, Sato Ikken, Abe Yuta, Nakagiri Toshio, Ishimi Akihiro, Nagae Yuji

Proceedings of 12th International Conference of the Croatian Nuclear Society; Nuclear Option for CO$_{2}$ Free Energy Generation (USB Flash Drive), 109\_1-109\_15, Jun, 2018 Peer-reviewed
Metallurgical investigations on creep rupture mechanisms of dissimilar welded joints between Gr.91 and 304SS

Yamashita Takuya, Nagae Yuji, Kikuchi Koichi*, Yamamoto Kenji*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 8, Apr, 2017 Peer-reviewed
The Welded joint strength reduction factors of modified 9Cr-1Mo Steel for the advanced loop-type sodium cooled fast reactor

Yamashita Takuya, Wakai Takashi, Onizawa Takashi, Sato Kenichiro*, Yamamoto Kenji*

Journal of Pressure Vessel Technology, 138(6) 061407\_1-061407\_6, Dec, 2016 Peer-reviewed
Strength of 316FR joints welded by Type 316FR/16-8-2 filler metals

Yamashita Takuya, Nagae Yuji, Sato Kenichiro*, Yamamoto Kenji*

Journal of Pressure Vessel Technology, 138(2) 024501\_1-024501\_7, Apr, 2016 Peer-reviewed
Material strength evaluation for 60 years design in Japanese sodium fast reactor

Nagae Yuji, Onizawa Takashi, Takaya Shigeru, Yamashita Takuya

Proceedings of 2014 ASME Pressure Vessels and Piping Conference (PVP 2014) (DVD-ROM), 9, Jul, 2014 Peer-reviewed

Misc.

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

Yamashita Takuya, Shimomura Kenta, Nagae Yuji, Yamaji Akifumi*, Mizokami Shinya, Mitsugi Takeshi, Koyama Shinichi

Hairo, Osensui, Shorisui Taisaku Jigyo Jimukyoku Homu Peji (Internet), 53, Oct, 2023
Collection of strength characteristic data used for analysis evaluation in reactor pressure vessel and in-core structures in accident

Shimomura Kenta, Yamashita Takuya, Nagae Yuji

JAEA-Data/Code 2022-012, 270, Mar, 2023
How far do we know about the Accident at the Fukushima Daiichi Nuclear Power Station?; In the case of Unit 2

Yamashita Takuya

Enerugi Rebyu, 41(4) 14-16, Mar, 2021
The CMMR program; BWR core degradation in the CMMR-3 test

Yamashita Takuya, Sato Ikken, Abe Yuta, Nakagiri Toshio, Ishimi Akihiro, Nagae Yuji

Proceedings of International Conference on Dismantling Challenges; Industrial Reality, Prospects and Feedback Experience (DEM 2018) (Internet), 11, Oct, 2018

Presentations

Thermal-structural coupled analysis for estimating RPV damage in FDNPS Unit 2

Yamashita Takuya, Shimomura Kenta, Sakae Kazuaki*, Hashimoto Akihiko*, Nagae Yuji

International Conference on Environmental Remediation and Radioactive Waste Management (ICEM2023)
Development of high temperature material property equation for base metal and welded joints of reactor pressure vessel steels

Shimomura Kenta, Yamashita Takuya, Nagae Yuji

日本原子力学会2023年秋の大会
Analysis of fuel debris discharge behavior from the 1F Unit-2 RPV lower head region with MPS method

Bando Yamato*, Yamaji Akifumi*, Yamashita Takuya

令和5年度日本原子力学会関東・甲越支部「第16回学生研究発表会」
Failure of BWR lower head due to reaction between molten metal and structural materials

Sato Takumi, Yamashita Takuya, Shimomura Kenta, Nagae Yuji

令和4年度福島研究開発部門成果報告会
Failure behavior of BWR lower head due to reaction with molten metallic materials

Sato Takumi, Yamashita Takuya, Shimomura Kenta, Nagae Yuji

International Topical Workshop on Fukushima Decommissioning Research (FDR2022)
Preliminary evaluation of the fuel debris behavior below the RPV lower head boundary of 1F Unit-2

Bando Yamato*, Sasaki Ryotaro*, Fukuda Takanari*, Yamaji Akifumi*, Yamashita Takuya

International Topical Workshop on Fukushima Decommissioning Research (FDR2022)
In-vessel phase MAAP analysis based on the latest findings on Fukushima Daiichi Nuclear Power Station in JFY2021, 2; Unit 3 Analysis results and use for future studies

Yamashita Takuya, Sato Ikken, Yoshikawa Shinji, Cibula M.*, Mizokami Shinya*

日本原子力学会2022年秋の大会
In-vessel phase MAAP analysis based on the latest findings on Fukushima Daiichi Nuclear Power Station in JFY2021, 1; Overview and Unit 2 analysis results

Sato Ikken, Yamashita Takuya, Yoshikawa Shinji, Cibula M.*, Mizokami Shinya*

日本原子力学会2022年秋の大会
Development of the decommissioning research infrastructure database (debrisWiki)

Yamashita Takuya

令和3年度福島研究開発部門成果報告会
Reaction behavior of BWR lower head structure and molten metals

Sato Takumi, Yamashita Takuya, Madokoro Hiroshi, Nagae Yuji

日本原子力学会2021年秋の大会
LIVE experiment on thermal behavior of solid-liquid mixture pool in RPV lower head

Madokoro Hiroshi, Gaus-Liu X.*, Cron T.*, Fluhrer B.*, Stangle R.*, Wenz T.*, Vervoortz M.*, Yamashita Takuya, Sato Ikken, Mizokami Shinya

日本原子力学会2021年秋の大会
Post-test analysis of the CMMR-4 test bundle

Madokoro Hiroshi, Yamashita Takuya, Sato Ikken

25th International QUENCH Workshop
Examination of application to material hardness evaluation method by simultaneous multi-spectrum measurement of Laser Induced Breakdown Spectroscopy (LIBS), 1; Evaluation of specimen for hardness measurement using LIBS

Abe Yuta, Yamashita Takuya, Kawakami Tomohiko*

日本分析化学会関東支部第15回茨城地区分析技術交流会
Assessment of core status of TEPCO's Fukushima Daiichi Nuclear Power Plants, 114; Integrated evaluation of fuel debris remaining inside the RPV and the PCV; Unit1

Sakai Takeshi*, Mizokami Shinya*, Honda Takeshi*, Nozaki Kenichiro*, Yamashita Takuya, Pellegrini M.*, Suzuki Hiroyuki*

日本原子力学会2018年秋の大会
Assessment of core status of TEPCO's Fukushima Daiichi Nuclear Power Plants, 113; Integrated evaluation of fuel debris remaining inside the RPV and the PCV; Unit3

Mizokami Shinya*, Honda Takeshi*, Nozaki Kenichiro*, Sakai Takeshi*, Yamashita Takuya, Pellegrini M.*, Suzuki Hiroyuki*

日本原子力学会2018年秋の大会
Assessment of core status of TEPCO's Fukushima Daiichi Nuclear Power Plants, 115; Integrated evaluation of fuel debris remaining inside the RPV and the PCV; Unit2

Yamashita Takuya, Honda Takeshi*, Mizokami Shinya*, Nozaki Kenichiro*, Suzuki Hiroyuki*, Pellegrini M.*, Sakai Takeshi*

日本原子力学会2018年秋の大会
Assessment of core status of TEPCO's Fukushima Daiichi Nuclear Power Plants, 109; Difference in core energy in core material relocation in Units 2 and 3 of FDNPS and its effects

Sato Ikken, Yamashita Takuya, Yoshikawa Shinji, Li X., Pellegrini M.*, Yamaji Akifumi*, Kojima Yoshihiro*

日本原子力学会2018年秋の大会
Plasma heating test on fuel assembly degradation

Yamashita Takuya, Sato Ikken

3rd International Forum on the Decommissioning of the Fukushima Daiichi Nuclear Power Station
Establishment of evaluation method using material analysis of simulated fuel assembly heating test, 2; Consideration of a wide range of oxygen and boron mapping analysis method using the EPMA

Noro Junji*, Abe Yuta, Yamashita Takuya, Matsushima Tomohiro*

第78回分析化学討論会
Establishment of evaluation method using material analysis of simulated fuel assembly heating test, 1; Outline of simulated fuel assembly heating test using non-transfer type plasma heating

Abe Yuta, Nakagiri Toshio, Yamashita Takuya, Noro Junji*, Matsushima Tomohiro*, Kawakami Tomohiko*

第78回分析化学討論会