Koji Maeda - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101014536621924
researchmap Member ID: R000017505

Research Areas

Energy / Nuclear engineering /

Papers

Estimation of the activity median aerodynamic diameter of plutonium particles using image analysis

Takasaki Koji, Yasumune Takashi, Yamaguchi Yukako, Hashimoto Makoto, Maeda Koji, Kato Masato

Journal of Nuclear Science and Technology, 60(11) 1437-1446, Nov, 2023 Peer-reviewed
Reaction of Np, Am, and Cm ions with CO$_{2}$ and O$_{2}$ in a reaction cell in triple quadrupole inductively coupled plasma mass spectrometry

Kazama Hiroyuki, Konashi Kenji*, Suzuki Tatsuya*, Koyama Shinichi, Maeda Koji, Sekio Yoshihiro, Onishi Takashi, Abe Chikage*, Shikamori Yasuyuki*, Nagai Yasuyoshi*

Journal of Analytical Atomic Spectrometry, 38(8) 1676-1681, Jul, 2023 Peer-reviewed
Data processing and visualization of X-ray computed tomography images of a JOYO MK-III fuel assembly

Tsai T.-H., Sasaki Shinji, Maeda Koji

Journal of Nuclear Science and Technology, 60(6) 715-723, Jun, 2023 Peer-reviewed
Leaching behavior of radionuclides from samples prepared from spent fuel rod comparable to core debris in the 1F NPS

Takashi Onishi, Koji Maeda, Kozo Katsuyama

Journal of Nuclear Science and Technology, 2020
Irradiation performance of sodium-bonded control rod for the fast breeder reactor

Shinji Sasaki, Koji Maeda, Hirotaka Furuya

Journal of Nuclear Science and Technology, 55(3) 276-282, Mar 4, 2018 Peer-reviewed
Distributions of density and fission products in the reaction product between irradiated MOX fuel and molten zircaloy-2

Akihiro Ishimi, Kozo Katsuyama, Koji Maeda, Hirotaka Furuya

Journal of Nuclear Science and Technology, 54(11) 1274-1276, Nov 2, 2017 Peer-reviewed
Oxide-Metal Ratio Dependence of Central Void Formation of Mixed Oxide Fuel Irradiated in Fast Reactors

Yoshihisa Ikusawa, Koji Maeda, Masato Kato, Masayoshi Uno

NUCLEAR TECHNOLOGY, 199(1) 83-95, Jul, 2017 Peer-reviewed
Results of detailed analyses performed on the concrete cores extracted from the Fukushima Daiichi nuclear plant reactor buildings

Koji Maeda, Shinji Sasaki, Masahiko Osaka

Fukushima Daiichi: Causes and Consequences, 1-25, Jan 1, 2017
Penetration behavior of water solution containing radioactive species into dried concrete/mortar and epoxy resin materials

Isamu Sato, Koji Maeda, Mitsuo Suto, Masahiko Osaka, Toshiyuki Usuki, Shin Ichi Koyama

Journal of Nuclear Science and Technology, 52(4) 580-587, Apr, 2015 Peer-reviewed
Distribution of radioactive nuclides of boring core samples extracted from concrete structures of reactor buildings in the Fukushima Daiichi Nuclear Power Plant

Koji Maeda, Shinji Sasaki, Misaki Kumai, Isamu Sato, Mitsuo Suto, Masahiko Ohsaka, Tetsuo Goto, Hitoshi Sakai, Takayuki Chigira, Hirotoshi Murata

Journal of Nuclear Science and Technology, 51(7-8) 1006-1023, Aug 3, 2014 Peer-reviewed
Development and verification of the Thermal behavior analysis code for MA containing MOX fuels

Yoshihisa Ikusawa, Koji Maeda, Takayuki Ozawa, Masato Kato, Shun Hirooka, Seiichiro Maeda

International Conference on Nuclear Engineering, Proceedings, ICONE, 1 6, 2014 Peer-reviewed
Results of detailed analyses performed on boring cores extracted from the concrete floors of the Fukushima Daiichi Nuclear Power Plant reactor buildings

Koji Maeda, Shinji Sasaki, Misaki Kumai, Isamu Sato, Masahiko Osaka, Mineo Fukushima, Shinji Kawatsuma, Tetsuo Goto, Hitoshi Sakai, Takayuki Chigira …

International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads, 1 272-277, 2013 Peer-reviewed
Upgrading of X-ray CT technology for analyses of irradiated FBR MOX fuel

Akihiro Ishimi, Kozo Katsuyama, Koji Maeda, Tsuyoshi Nagamine, Takeo Asaga, Hirotaka Furuya

Journal of Nuclear Science and Technology, 49(12) 1144-1155, Dec, 2012 Peer-reviewed
Development of high resolution X-ray CT technique for highly-radioactive material

Kozo Katsuyama, Akihiro Ishimi, Koji Maeda, Tsuyoshi Nagamine, Takeo Asaga

Materials Research Society Symposium Proceedings, 1475 539-544, 2012
Application of field emission scanning electron microscopy for observing irradiated fuel materials

S. Sasaki, K. Maeda, A. Yamada, T. Asaga

Materials Research Society Symposium Proceedings, 1475 157-160, 2012
Fast spectrum control rod materials

T. Donomae, K. Maeda

Comprehensive Nuclear Materials, 3 509-534, 2012
Ceramic fuel-cladding interaction

K. Maeda

Comprehensive Nuclear Materials, 3 443-483, 2012
Development of a high resolution X-ray CT technique for irradiated fuel pellets

Kozo Katsuyama, Akihiro Ishimi, Koji Maeda, Tsuyoshi Nagamine, Takeo Asaga

IEEE Transactions on Nuclear Science, 59(4 PART 2) 1397-1400, 2012
Diametral strain of fast reactor MOX fuel pins with austenitic stainless steel cladding irradiated to high burnup

Tomoyuki Uwaba, Masahiro Ito, Koji Maeda

Journal of Nuclear Materials, 416(3) 350-357, Sep 30, 2011 Peer-reviewed
Short-term irradiation behavior of low-density americium-doped uranium-plutonium mixed oxide fuels irradiated in a fast reactor

K. Maeda, K. Katsuyama, Y. Ikusawa, S. Maeda

Journal of Nuclear Materials, 416(1-2) 158-165, Sep 1, 2011 Peer-reviewed

Misc.

Analysis of deposits inside the reactor at Fukushima Daiichi Nuclear Power Station in JFY2021; The Subsidy program of "Project of Decommissioning and Contaminated Water Management (Development of Analysis and Estimation Technology for Characterization of Fuel Debris)" starting FY2021

Ikeuchi Hirotomo, Sasaki Shinji, Onishi Takashi, Nakayoshi Akira, Arai Yoichi, Sato Takumi, Ohgi Hiroshi, Sekio Yoshihiro, Yamaguchi Yukako, Morishita Kazuki …

JAEA-Data/Code 2023-005, 418, Dec, 2023
Materials science and fuel technologies of uranium and plutonium mixed oxide

Kato Masato, Machida Masahiko, Hirooka Shun, Nakamichi Shinya, Ikusawa Yoshihisa, Nakamura Hiroki, Kobayashi Keita, Ozawa Takayuki, Maeda Koji, Sasaki Shinji …

Materials Science and Fuel Technologies of Uranium and Plutonium mixed Oxide, 171, Oct, 2022
Development of technologies for enhanced analysis accuracy of fuel debris; Summary results of the 2020 fiscal year (Subsidy program for the project of decommissioning and contaminated water management)

Ikeuchi Hirotomo, Koyama Shinichi, Osaka Masahiko, Takano Masahide, Nakamura Satoshi, Onozawa Atsushi, Sasaki Shinji, Onishi Takashi, Maeda Koji, Kirishima Akira* …

JAEA-Technology 2022-021, 224, Oct, 2022
Analysis of deposits inside the reactor at Fukushima Daiichi Nuclear Power Station in JFY 2017-2018; The Subsidy programs "Project of Decommissioning and Contaminated Water Management in the FY2016 Supplementary Budget, (Development of Technologies for Grasping and Analyzing Properties of Fuel Debris)

Nakayoshi Akira, Mitsugi Takeshi, Sasaki Shinji, Maeda Koji

JAEA-Data/Code 2021-011, 279, Mar, 2022
Summary results of subsidy program for the "Project of Decommissioning and Contaminated Water Management (Development of Analysis and Estimation Technology for Characterization of Fuel Debris (Development of Technologies for Enhanced Analysis Accuracy and Thermal Behavior Estimation of Fuel Debris))"

Koyama Shinichi, Nakagiri Toshio, Osaka Masahiko, Yoshida Hiroyuki, Kurata Masaki, Ikeuchi Hirotomo, Maeda Koji, Sasaki Shinji, Onishi Takashi, Takano Masahide …

Hairo, Osensui Taisaku jigyo jimukyoku Homu Peji (Internet), 144, Aug, 2021
Activity median aerodynamic diameter relating to contamination at Plutonium Fuel Research Facility in Oarai Research and Development Center; Particle size analysis for plutonium particles using imaging plate

Takasaki Koji, Yasumune Takashi, Hashimoto Makoto, Maeda Koji, Kato Masato, Yoshizawa Michio, Momose Takumaro

JAEA-Review 2019-003, 48, Mar, 2019
Electrochemical corrosion tests for core materials utilized in BWR under conditions containing seawater

Shizukawa Yuta, Sekio Yoshihiro, Sato Isamu*, Maeda Koji

Proceedings of 54th Annual Meeting of Hot Laboratories and Remote Handling (HOTLAB 2017) (Internet), 5, Jan, 2017
Application of FE-SEM to the measurement of U, Pu, Am in the irradiated MA-MOX fuel

Sasaki Shinji, Tanno Takashi, Maeda Koji

Proceedings of 54th Annual Meeting of Hot Laboratories and Remote Handling (HOTLAB 2017) (Internet), 6, Jan, 2017
Development of field emission SEM to observe high radioactive irradiated fuels

Isozaki Misaki, Sasaki Shinji, Maeda Koji, Katsuyama Kozo

JAEA-Technology 2015-058, 28, Mar, 2016
Seawater immersion tests of irradiated Zircaloy-2 cladding tube

Sekio Yoshihiro, Yamagata Ichiro, Yamashita Shinichiro, Inoue Masaki, Maeda Koji

Proceedings of 2014 Nuclear Plant Chemistry Conference (NPC 2014) (USB Flash Drive), 10, Oct, 2014
Development of science-based fuel technologies for Japan's Sodium-Cooled Fast Reactors

Kato Masato, Hirooka Shun, Ikusawa Yoshihisa, Takeuchi Kentaro, Akashi Masatoshi, Maeda Koji, Watanabe Masashi, Komeno Akira, Morimoto Kyoichi

Proceedings of 19th Pacific Basin Nuclear Conference (PBNC 2014) (USB Flash Drive), 12, Aug, 2014
Penetration behavior of solution containing radioactive nuclides into floor and wall materials

Usuki Toshiyuki, Sato Isamu, Suto Mitsuo, Maeda Koji, Osaka Masahiko, Koyama Shinichi, Tokoro Daishiro*, Sekioka Ken*, Ishigamori Toshio*

JAEA-Testing 2014-001, 29, May, 2014
R&D of Remote Decontamination Technique in Reactor Building (2-(1)-1) Towards the Decommissioning of Fukushima Daiichi Nuclear Power Plant : Results of Examinations of Contaminated Samples at JAEA Hot Laboratories

Maeda Koji, Sasaki Shinji, Kumai Misaki, Sato Isamu, Suto Mitsuo, Osaka Masahiko

JAEA-research, 2013(25) 1-123,巻頭1-2, Jan, 2014
Immersion test in artificial water and evaluation of strength property on fuel cladding tubes irradiated in Fugen Nuclear Power Plant

Yamagata Ichiro, Hayashi Takehiro, Mashiko Shinichi*, Sasaki Shinji, Inoue Masaki, Yamashita Shinichiro, Maeda Koji

JAEA-Testing 2013-004, 23, Nov, 2013
Immersion tests of irradiated Zircaloy-2 in artificial seawater (2nd report)

Yamagata Ichiro, Hayashi Takehiro, Sasaki Shinji, Mashiko Shinichi, Inoue Masaki, Yamashita Shinichiro, Maeda Koji

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2013 402-402, 2013
Basic Data Acquisitions for Development of Remote Decontamination Techniques:(4)-Results of a detailed examination of contamined samples in Fukushima-Daiichi nuclear power plant

Kumai Misaki, Maeda Koji, Sato Isamu, Osaka Masahiko, Fukushima Mineo, Kawatsuma Shinji, Goto Tetsuo

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2013 683-683, 2013
BDI behavior evaluation of an upgraded Monju core and a demonstration core, 1; Plans for the out of pile bundle compressive tests for large diameter pins

Ichikawa Shoichi, Haga Hiroyuki, Katsuyama Kozo, Uwaba Tomoyuki, Maeda Koji, Nishinoiri Kenji

JAEA-Testing 2012-001, 36, Jul, 2012
BDI behavior evaluation of "Monju" advanced reactor and demonstration reactor:(1) Out of pile bundle compressive test plan for a thick pin

Ichikawa Shoichi, Katsuyama Kozo, Maeda Koji, Nishinoiri Kenji, Uwaba Tomoyuki, Koyama Shinichi

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2012 473-473, 2012
Decontamination Experiment for Floor of Fukushima Daiichi Reactor Buildings:Penetration Behavior of Simulated-contaminated Water into Floor and Wall Materials

Usuki Toshiyuki, Sekioka Ken, Ishigamori Toshio, Sato Isamu, Kanayama Fumihiiko, Suto Mitsuo, Maeda Koji, Koyama Shinichi, Kawatsuma Shinji, Fukushima Mineo …

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2012 642-642, 2012
Evaluation of the effect in immersion test about irradiated Zircaloy-2

Hayashi Takehiro, Sasaki Shinji, Mashiko Shinichi, Yamagata Ichiro, Ogawa Ryuichiro, Yamashita Shinichiro, Maeda Koji

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2012 427-427, 2012

Presentations

$\alpha$-emitting nuclides analysis of the stagnant water including sediments in Fukushima Daiichi NPS, 10; Chemical state analysis of $\alpha$-emitting nuclide particles obtained from stagnant water sludge sampled from Unit \#1 and centralized radioactive waste treatment facility

Toyota Chihiro, Nitta Asahi, Usui Akane, Sekio Yoshihiro, Maeda Koji, Koma Yoshikazu, Konno Katsuhiro*

日本原子力学会2024年春の年会
Development of rapid Nd analysis method using ICP-MS/MS

Kazama Hiroyuki, Toyota Chihiro, Onishi Takashi, Maeda Koji

日本原子力学会2024年春の年会
Establishment of characterization method for small fuel debris using the world's first isotope micro imaging apparatus, 5; Micro-area isotope composition analysis of Fukushima Daiichi Nuclear Power Plant contaminant

Yoshida Takeru, Sekio Yoshihiro, Maeda Koji, Morita Masato*, Sakamoto Tetsuo*, Mizokami Masato*, Hirai Mutsumi*

日本原子力学会2023年秋の大会
Estimation of reaction constants of actinide ions with O$_{2}$ in reaction cell in triple quadrupole inductively coupled plasma mass spectrometry

Kazama Hiroyuki, Konashi Kenji*, Suzuki Tatsuya*, Sekio Yoshihiro, Maeda Koji, Koyama Shinichi, Abe Chikage*, Nagai Yasuyoshi*

日本放射化学会第67回討論会(2023)
Development of ultramicro analysis technology for fuel debris analysis, 21; Actinide separation from irradiated fuels by extraction chromatography

Kazama Hiroyuki, Onishi Takashi, Ikhwan F. H.*, Suzuki Tatsuya*, Sekio Yoshihiro, Maeda Koji, Koyama Shinichi, Konashi Kenji*, Idemitsu Kazuya*, Nagai Yasuyoshi*

日本原子力学会2023年秋の大会
$\alpha$-emitting nuclides analysis of the stagnant water including sediments in Fukushima Daiichi NPS, 6; Chemical state analysis of $\alpha$-emitting nuclide particles obtained from unit \#3 stagnant water sludge (Part 2)

Nitta Asahi, Usui Akane, Yamaguchi Yukako, Sekio Yoshihiro, Maeda Koji, Koma Yoshikazu, Konno Katsuhiro*

日本原子力学会2023年秋の大会
$\alpha$-emitting nuclides analysis of the stagnant water including sediments in Fukushima Daiichi NPS, 3; Chemical state analysis of $\alpha$-emitting nuclide particles obtained from unit \#3 stagnant water sludge

Usui Akane, Yamaguchi Yukako, Sekio Yoshihiro, Maeda Koji, Koma Yoshikazu, Konno Katsuhiro*

日本原子力学会2023年春の年会
Analysis for investigation of sludge observed in the storage tank of Fukushima Daiichi Nuclear Power Station

Yamaguchi Yukako, Sekio Yoshihiro, Maeda Koji, Koma Yoshikazu, Fujiya Akihiko*

日本原子力学会2022年秋の大会
Prediction of gas-phase reactivity of actinide ions using triple quadrupole ICP-MS for fuel debris analysis

Kazama Hiroyuki, Sekio Yoshihiro, Maeda Koji, Koyama Shinichi, Suzuki Tatsuya*, Konashi Kenji*, Abe Chikage*, Nagai Yasuyoshi*

日本放射化学会第66回討論会(2022)
Development of ultramicro analysis technology for fuel debris analysis, 15; Mutual discrimination of Am/Cm using ICP-MS/MS

Kazama Hiroyuki, Sekio Yoshihiro, Maeda Koji, Koyama Shinichi, Suzuki Tatsuya*, Konashi Kenji*, Abe Chikage*, Nagai Yasuyoshi*

日本原子力学会2022年秋の大会
Development of ultramicro analysis technology for fuel debris analysis, 5; Consideration of analytical methods for actinide elements with ICP-MS/MS

Kazama Hiroyuki, Sekio Yoshihiro, Maeda Koji, Konashi Kenji*, Abe Chikage*, Nagai Yasuyoshi*, Suzuki Tatsuya*

日本原子力学会2021年秋の大会
X-ray computed tomography image analysis of an irradiated Joyo fuel assembly; Visualization of the structural changes in the irradiated fuels

Tsai T.-H., Sasaki Shinji, Katsuyama Kozo, Maeda Koji

日本原子力学会2021年春の年会
Development of ultramicro analysis technology for fuel debris analysis, 1; Outline of the research program and collaborative laboratory

Sekio Yoshihiro, Iwamoto Yasuhiro, Hamada Maho, Maeda Koji, Higuchi Toru*, Suzuki Tatsuya*, Idemitsu Kazuya*, Konashi Kenji*, Nagai Yasuyoshi*

日本原子力学会2020年秋の大会
A Study on the chemical reaction between fuel materials and graphite block, 3-2; Differential scanning calorimetry of the uranium dioxide and graphite

Naito Hiroyuki, Yamamoto Masaya, Maeda Shigetaka, Kurematsu Shigeru*, Sato Isamu*, Maeda Koji

日本原子力学会2020年秋の大会
Development of highly microstructure-controlled neutron control ceramics for improving safety of fast reactors, 3; Post-irradiation microstructure evaluation of "Joyo" irradiated B$_{4}$C control materials

Shizukawa Yuta, Sekio Yoshihiro, Inoue Toshihiko, Maeda Koji, Yoshida Katsumi*

日本原子力学会2020年春の年会
Study on forming condition of rim structure and the effect on integrity in a fast reactor fuel

Naganuma Masayuki, Kamei Miho, Maeda Koji

日本原子力学会2020年春の年会
Investigation of in-reactor cesium chemical behavior in TEPCO's Fukushima Daiichi Nuclear Power Station accident, 13; Chemical analysis of samples collected from the operating floor of the reactor building of Unit 2

Morishita Kazuki, Onishi Takashi, Maeda Koji, Mizokami Masato*, Ito Kenichi*, Mizokami Shinya*

日本原子力学会2019年秋の大会
Analysis of samples collected in PCV interior of Fukushima Daiichi NPP, 3; Nuclide analysis of samples collected in PCV interior

Sasaki Shinji, Maeda Koji, Morishita Kazuki, Onishi Takashi, Sato Ikken, Mizokami Masato*, Mizokami Shinya*

日本原子力学会2019年秋の大会
A Study on the chemical reaction between fuel materials and graphite block, 1; Thermodynamic equilibrium calculations

Maeda Shigetaka, Sato Isamu*, Yamamoto Masaya, Naito Hiroyuki, Maeda Koji

日本原子力学会2019年秋の大会
A Study on the chemical reaction between fuel materials and graphite block, 2; Differential scanning calorimetry of the uranium dioxide and graphite

Naito Hiroyuki, Yamamoto Masaya, Maeda Shigetaka, Kurematsu Shigeru*, Sato Isamu*, Maeda Koji

日本原子力学会2019年秋の大会