Shinji Sasaki - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101017462436100
researchmap Member ID: R000017511

Papers

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
Sodium-cooled Fast Reactors

Ohshima Hiroyuki, Morishita Masaki*, Aizawa Kosuke, Ando Masanori, Ashida Takashi, Chikazawa Yoshitaka, Doda Norihiro, Enuma Yasuhiro, Ezure Toshiki, Fukano Yoshitaka …

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631, Jul, 2022 Peer-reviewed
Irradiation performance of sodium-bonded control rod for the fast breeder reactor

Sasaki Shinji, Maeda Koji, Furuya Hirotaka*

Journal of Nuclear Science and Technology, 55(3) 276-282, Mar, 2018 Peer-reviewed
Early-in-life fuel restructuring behavior of Am-bearing MOX fuels

Tanaka Kosuke, Sasaki Shinji, Katsuyama Kozo, Koyama Shinichi

Transactions of the American Nuclear Society, 113(1) 619-621, Oct, 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

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

Journal of Nuclear Science and Technology, 51(7-8) 1006-1023, Jul, 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

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

Proceedings of International Nuclear Fuel Cycle Conference; Nuclear Energy at a Crossroads (GLOBAL 2013) (CD-ROM), 1 272-277, Sep, 2013 Peer-reviewed
Fuel-cladding chemical interaction in MOX fuel rods irradiated to high burnup in an advanced thermal reactor

Tanaka Kosuke, Maeda Koji, Sasaki Shinji, Ikusawa Yoshihisa, Abe Tomoyuki

Journal of Nuclear Materials, 357(1-3) 58-68, Oct, 2006 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
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
R\&D of remote decontamination technique in reactor building (2-$ \textcircled{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 2013-025, 123, 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
Investigation on analytical method for the transfer behavior of corrosion product (CP) in the fast breeder reactors

Matsuo Yoichiro, Sasaki Shinji

JAEA-Review 2013-007, 46, May, 2013
Investigation on cause of malfunction of Wide Range Monitor (WRM) in High Temperature engineering Test Reactor (HTTR); Sample tests and destructive tests

Shinohara Masanori, Motegi Toshihiro, Saito Kenji, Haga Hiroyuki, Sasaki Shinji, Katsuyama Kozo, Takada Kiyoshi*, Higashimura Keisuke*, Fujii Junichi*, Ukai Takayuki* …

JAEA-Technology 2012-032, 29, Nov, 2012
Support system for training and education of future expert at PIE Hot Laboratories in Oarai JAEA; FEETS

Osaka Masahiko, Donomae Takako, Ichikawa Shoichi, Sasaki Shinji, Ishimi Akihiro, Inoue Toshihiko, Sekio Yoshihiro, Miwa Shuhei, Onishi Takashi, Asaka Takeo …

Proceedings of 1st Asian Nuclear Fuel Conference (ANFC), 2, Mar, 2012
Measurement of deformation of FBR fuel assembly wrapper tube by an innovative technique

Sasaki Shinji, Abe Kazuyuki, Nagamine Tsuyoshi

JAEA-Conf 2008-010, 362-371, Dec, 2008
Post irradiation-examination results for absorber material irradiation rig AMIR-6; The Results of non-destructive examination for capsules

Abe Kazuyuki, Sasaki Shinji, Kikuchi Shin, Katsuyama Kozo, Nagamine Tsuyoshi, Matsumoto Shinichiro

JNC TN9430 2002-003, 52, May, 2002
Development of multipurpose test Apparatus for core assemblies in FMF-extention; Examination of size and cross section from measurement for core assemblies irradiated in "JOYO"

Abe Kazuyuki, Matsumoto Shinichiro

JNC TN9410 2002-011, 36, Apr, 2002

Presentations

Development of post-irradiation examinations for fast reactors

Sasaki Shinji

日本原子力学会核燃料部会第33回「核燃料・夏期セミナー」
Ac-225 production using the experimental fast reactor Joyo

Sano Aaru, Sasaki Yuto*, Sasaki Shinji, Iwamoto Nobuyuki, Ouchi Kazuki, Kitatsuji Yoshihiro, Maeda Shigetaka, Takaki Naoyuki*

International Symposium on Trends in Radiopharmaceuticals (ISTR-2023)
Medical RI production using domestic nuclear infrastructures for self-sustenance, 5; Ac-225 production using the experimental fast reactor Joyo

Sano Aaru, Maeda Shigetaka, Itagaki Wataru, Sasaki Shinji, Sasaki Yuto*, Takaki Naoyuki*

日本原子力学会2022年春の年会
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
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
Evaluation of fuel behaviors by using science-based integrated models for MOX properties, 2; Evaluation of Pu and Am redistribution

Kamei Miho, Naganuma Masayuki, Ikusawa Yoshihisa, Maeda Koji, Sasaki Shinji, Ozawa Takayuki, Hirooka Shun

日本原子力学会2018年秋の大会
Ceramography and EPMA investigation of irradiation behavior of annular MOX pellets

Sasaki Shinji, Isozaki Misaki, Ishimi Akihiro, Maeda Koji

5th International Conference on Asian Nuclear Prospects 2016 (ANUP 2016)
Restructuring behavior of annular irradiated fuel

Sasaki Shinji, Isozaki Misaki, Ishimi Akihiro, Maeda Koji

日本原子力学会2016年秋の大会
Irradiation behavior of sodium bonded type control rod in the fast reactor, 3 Visual inspection and profilometry results of absorber pins

Sasaki Shinji, Ishimi Akihiro, Katsuyama Kozo, Maeda Koji, Sogame Motomu

日本原子力学会2015年春の年会
Development of remote decontamination techniques for reactor building, 2; Analysis of concrete core sample from south side floor of first floor in Unit 1

Higashiuchi Atsushi, Maeda Koji, Sasaki Shinji, Katsuyama Kozo, Otani Akira, Chigira Takayuki*, Murata Hirotoshi*

日本原子力学会2015年春の年会
Development of remote decontamination techniques for reactor building, 8; Analysis of Concrete core sample from Operation Floor of Unit 2

Higashiuchi Atsushi, Maeda Koji, Otani Akira, Sasaki Shinji, Katsuyama Kozo, Chigira Takayuki*, Murata Hirotoshi*

日本原子力学会2014年秋の大会
Seawater immersion tests of irradiated Zircaloy-2 cladding tube

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

日本原子力学会2014年春の年会
The Post irradiation examinations of Joyo MK-IIfuels stored in water for long-term

Sasaki Shinji, Soga Tomonori, Maeda Koji, Katsuyama Kozo, Kodaka Hideo

日本原子力学会2013年秋の大会
Immersion tests of irradiated zircaloy-2 in artificial seawater, 3

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

日本原子力学会2013年秋の大会
Immersion tests of irradiated Zircaloy-2 in artificial seawater

Hayashi Takehiro, Sasaki Shinji, Mashiko Shinichi*, Yamagata Ichiro, Ogawa Ryuichiro, Inoue Masaki, Yamashita Shinichiro

平成25年度日本原子力学会北関東支部若手研究者発表会
Immersion tests of irradiated Zircaloy-2 in artificial seawater, 2

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

日本原子力学会2013年春の年会
Integrity assessment of zircaloy fuel cladding tube experienced transient environmental history of spent fuel pool in Fukushima Dai-ichi Nuclear Power Plant

Sekio Yoshihiro, Yamagata Ichiro, Yamashita Shinichiro, Sasaki Shinji, Ogawa Ryuichiro, Mashiko Shinichi, Hayashi Takehiro, Inoue Toshihiko, Inoue Masaki, Maeda Koji

International Experts Meeting on Decommissioning and Remediation after a Nuclear Accident
Immersion tests of irradiated Zircaloy-2 specimens in artificial seawater

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

日本原子力学会2012年秋の大会
Installation of shielded FESEM for irradiation fast reactor fuels

Sasaki Shinji, Maeda Koji, Yamada Atsushi*

日本顕微鏡学会第67回学術講演会
Radial redistributions of actinide in irradiated MA-MOX fuel pins

Maeda Koji, Sasaki Shinji, Ikusawa Yoshihisa, Koyama Shinichi, Maeda Seiichiro

日本原子力学会2011年春の年会