Osaka Masahiko

オオサカマサヒコ | Osaka Masahiko

Affiliation and department：

Research field (1)： Nuclear engineering

Research theme for competitive and other funds (7)：

2011 - 2016 Study on hybrid nuclide separation method by using solid-type extractants combined with atmospheric-pressure non-thermal plasma chemical conversion method.
2008 - 2010 DENSIFICATION OF ADVANCED NUCLEAR FUELS USING ASBESTOS WASTE-DERIVED MATERIALS AS A SINTERING ADDITIVE
2007 - 2009 Study of microscopic electron state of non-stoichiometric plutonium oxide including oxygen vacancy
電気的手法による核燃料内の化学・物理状態分布評価
核燃料酸化物における酸素不定比に起因する欠陥構造の解明

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Papers (95)：

Liu J., Miwa Shuhei, Karasawa Hidetoshi, Osaka Masahiko. Effect of molybdenum release on UO$_{2}$/MOX fuel oxidation under severe light water reactor accident conditions. Nuclear Materials and Energy (Internet). 2023. 37. 101532\_1-101532\_5
Mohamad A. B., Nakajima Kunihisa, Miwa Shuhei, Osaka Masahiko. Chemical interaction between Sr vapor species and nuclear reactor core structure. Journal of Nuclear Science and Technology. 2023. 60. 3. 215-222
Rizaal M., Nakajima Kunihisa, Saito Takumi*, Osaka Masahiko, Okamoto Koji*. High-temperature gaseous reaction of cesium with siliceous thermal insulation; The Potential implication to the provenance of enigmatic Fukushima cesium-bearing material. ACS Omega (Internet). 2022. 7. 33. 29326-29336
Liu J., Nakajima Kunihisa, Miwa Shuhei, Shirasu Noriko, Osaka Masahiko. A New method of measuring ruthenium activity in ruthenium-containing alloys by using thermogravimetric analysis. Journal of Nuclear Science and Technology. 2022. 59. 4. 484-490
Osaka Masahiko, Gouello M.*, Nakajima Kunihisa. Cesium chemistry in the LWR severe accident and towards the decommissioning of Fukushima Daiichi Nuclear Power Station. Journal of Nuclear Science and Technology. 2022. 59. 3. 292-305

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MISC (46)：

Sato Nobuaki*, Kameo Yutaka, Sato Soichi, Kumagai Yuta, Sato Tomonori, Yamamoto Masahiro*, Watanabe Yutaka*, Nagai Takayuki, Niibori Yuichi*, Watanabe Masayuki, et al. Introduction to dismantling and decommissioning chemistry. Introduction to Dismantling and Decommissioning Chemistry. 2024. 251
Ikeuchi Hirotomo, Koyama Shinichi, Osaka Masahiko, Takano Masahide, Nakamura Satoshi, Onozawa Atsushi, Sasaki Shinji, Onishi Takashi, Maeda Koji, Kirishima Akira*, et al. 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). JAEA-Technology 2022-021. 2022. 224
Koyama Shinichi, Nakagiri Toshio, Osaka Masahiko, Yoshida Hiroyuki, Kurata Masaki, Ikeuchi Hirotomo, Maeda Koji, Sasaki Shinji, Onishi Takashi, Takano Masahide, et al. 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))". Hairo, Osensui Taisaku jigyo jimukyoku Homu Peji (Internet). 2021. 144
Imoto Jumpei, Miwa Shuhei, Osaka Masahiko. Experimental investigation on boron oxidative vaporization processes from zirconium-boron and iron-boron alloys in a high temperature steam atmosphere. Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) (Internet). 2019. 4
Mohamad A.*, Nakajima Kunihisa, Suzuki Eriko, Miwa Shuhei, Osaka Masahiko, Oishi Yuji*, Muta Hiroaki*, Kurosaki Ken*. Chemical trapping of Sr vapor species by Zircaloy cladding under a specific chemical condition. Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) (Internet). 2019. 4

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Patents (3)：

モリブデン化合物の製造方法
核燃料ペレットの製造方法および核燃料ペレット
核分裂生成物、キュリウム及びアメリシウムを含む溶液からアメリシウムを分離する方法

Lectures and oral presentations (250)：

Challenge in development and implementation of Accident-Tolerant Fuel (ATF) in Japan
(31st International Conference on Nuclear Engineering (ICONE31))
Overview of ATF R\&D program in Japan
(Collaborative Research on Advanced Fuel Technologies (CRAFT))
Study on coating technic to enhance accident tolerance of fuel cladding, 1; Overview of accident tolerant coating technic studies and apparatus development in JAEA
(日本原子力学会2024年春の年会)
Fundamental research program on zircalloy with accident tolerance
(6th Asian Zirconium Workshop (AZW))
Overview of ATF R\&D in Japan
(事故耐性燃料開発に関するワークショップ)

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