Rchr
J-GLOBAL ID：202101016569129980
Update date: Nov. 27, 2024
Hirosawa Takashi
ヒロサワ タカシ | Hirosawa Takashi
Affiliation and department：
Papers (13)：
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Do V. K., Furuse Takahiro, Ota Yuki, Iwahashi Hiroyuki, Hirosawa Takashi, Watanabe Masahisa, Sato Soichi. Development of HCl-free solid phase extraction combined with ICP-MS/MS for rapid assessment of difficult-to-measure radionuclides, 2; Highly sensitive monitoring of $^{126}$Sn in concrete rubble. Journal of Radioanalytical and Nuclear Chemistry. 2022. 331. 12. 5631-5640
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Tanaka Kosuke, Sato Isamu*, Onishi Takashi, Ishikawa Takashi, Hirosawa Takashi, Katsuyama Kozo, Seino Hiroshi, Ohno Shuji, Hamada Hirotsugu, Tokoro Daishiro*, et al. Release behavior of radionuclides from MOX fuels irradiated in a fast reactor during heating tests. Journal of Nuclear Materials. 2020. 536. 152119\_1-152119\_8
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Tanaka Kosuke, Sato Isamu, Hirosawa Takashi, Kurosaki Ken*, Muta Hiroaki*, Yamanaka Shinsuke*. Thermophysical properties of americium-containing barium plutonate. Journal of Nuclear Science and Technology. 2015. 52. 10. 1285-1289
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Tanaka Kosuke, Miwa Shuhei, Sato Isamu, Hirosawa Takashi, Sekine Shinichi, Osaka Masahiko, Obayashi Hiroshi, Koyama Shinichi. Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior. Journal of Nuclear Science and Technology. 2014. 51. 7-8. 876-885
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Sato Isamu, Suto Mitsuo, Miwa Shuhei, Hirosawa Takashi, Koyama Shinichi. Americium and plutonium release behavior from irradiated mixed oxide fuel during heating. Journal of Nuclear Materials. 2013. 437. 1-3. 275-281
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MISC (18)：
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Ishikawa Takashi, Onishi Takashi, Hirosawa Takashi, Tanaka Kosuke, Katsuyama Kozo. High temperature physicochemical properties of irradiated fuels. Proceedings of 54th Annual Meeting of Hot Laboratories and Remote Handling (HOTLAB 2017) (Internet). 2017. 10
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Sato Isamu, Miwa Shuhei, Tanaka Kosuke, Nakajima Kunihisa, Hirosawa Takashi, Iwasaki Maho, Onishi Takashi, Osaka Masahiko, Takai Toshihide, Amaya Masaki, et al. Research program for the evaluation of fission product release and transport behavior focusing on FP chemistry. Proceedings of 2014 Water Reactor Fuel Performance Meeting/ Top Fuel / LWR Fuel Performance Meeting (WRFPM 2014) (USB Flash Drive). 2014. 6
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Tanaka Kosuke, Miwa Shuhei, Sato Isamu, Hirosawa Takashi, Sekine Shinichi, Seki Takayuki*, Tokoro Daishiro*, Obayashi Hiroshi, Koyama Shinichi. Evaluation of fission product and actinide release behaviors focusing on their chemical forms; Phase relation and fission product release behavior resulting from interaction between molten zircaloy and irradiated MOX fuel. JAEA-Research 2013-022. 2014. 62
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Hirosawa Takashi, Sato Isamu, Tanaka Kosuke, Miwa Shuhei. Melting temperature evaluation for burnt fast reactor (U, Pu)O$_{2}$ fuels. Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM). 2011. 7
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Miwa Shuhei, Osaka Masahiko, Usuki Toshiyuki, Sato Isamu, Tanaka Kosuke, Hirosawa Takashi, Yoshimochi Hiroshi, Onose Shoji. MgO-based inert matrix fuels for a minor actinides recycling in a fast reactor cycle. Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM). 2011. 8
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Patents (4)：
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熱物性測定装置
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加熱炉および加熱炉を使用した熱物性値測定装置
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マニプレ-タ爪先用機能別回転式工具
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放射性廃棄物の輸送方法
Lectures and oral presentations (38)：
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Interference removal for high-sensitivity rapid analysis of $^{107}$Pd in radioactive rubbles by ICP-MS/MS
(日本原子力学会2021年秋の大会)
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Removal of interferences for ultrasensitive detection of $^{126}$Sn in radioactive rubbles by ICP-MS/MS
(日本原子力学会2021年春の年会)
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Development of chemical separation of Sn from concrete matrices using TEVA resin
(日本原子力学会2021年春の年会)
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Release behavior of radionuclides from MOX fuels irradiated in a fast reactor during heating tests
(Nuclear Materials Conference 2016 (NuMat 2016))
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Release behavior of radioactive materials from over-heated fuels for fast reactor, 3 Evaluation of fractional release rate
(日本原子力学会2016年春の年会)
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