Rchr
J-GLOBAL ID:201701011855970468   Update date: Jul. 04, 2022

Furukawa Tomohiro

Furukawa Tomohiro
Affiliation and department:
Research field  (1): Nuclear engineering
Papers (92):
  • Yamano Hidemasa, Takai Toshihide, Furukawa Tomohiro, Kikuchi Shin, Emura Yuki, Kamiyama Kenji, Fukuyama Hiroyuki*, Higashi Hideo*, Nishi Tsuyoshi*, Ota Hiromichi*, et al. Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 1; Project overview and progress until 2019. Proceedings of 28th International Conference on Nuclear Engineering; Nuclear Energy the Future Zero Carbon Power (ICONE 28) (Internet). 2021. 11
  • Takai Toshihide, Furukawa Tomohiro, Yamano Hidemasa. Thermophysical properties of austenitic stainless steel containing boron carbide in a solid state. Mechanical Engineering Journal (Internet). 2021. 8. 4. 20-00540\_1-20-00540\_11
  • Ukai Shigeharu, Kato Shoichi, Furukawa Tomohiro, Otsuka Satoshi. High-temperature creep deformation in FeCrAl-oxide dispersion strengthened alloy cladding. Materials Science \& Engineering A. 2020. 794. 139863\_1-139863\_13
  • Takai Toshihide, Furukawa Tomohiro, Yamano Hidemasa. Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 2; Thermophysical properties of eutectic mixture containing of high concentration boron in a solid state. Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet). 2020. 6
  • Yamano Hidemasa, Takai Toshihide, Furukawa Tomohiro, Kikuchi Shin, Emura Yuki, Kamiyama Kenji, Fukuyama Hiroyuki*, Higashi Hideo*, Nishi Tsuyoshi*, Ota Hiromichi*, et al. Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 1; Project overview and progress until 2018. Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet). 2020. 10
more...
MISC (80):
  • Satoshi Ohtsuka, Takashi Tanno, Hiroshi Oka, Yasuhide Yano, Shoichi Kato, Tomohiro Furukawa, Takeji Kaito. Model calculation of Cr dissolution behavior of ODS ferritic steel in high-temperature flowing sodium environment (vol 505, pg 44, 2018). JOURNAL OF NUCLEAR MATERIALS. 2018. 510. 661-661
  • Takai Toshihide, Sato Isamu*, Yamashita Shinichiro, Furukawa Tomohiro. Development of evaluation procedure of vapor species transition behavior; Investigation of applicable measurement technology for estimation of chemical form and physical parameters, and validity verification. JAEA-Technology 2015-043. 2016. 56
  • 近藤浩夫, 金村卓治, 古川智弘, 平川康, 若井栄一, 落合謙太郎. 強力中性子源用液体リチウムターゲットに発生するキャビテーションの音響計測. 混相流シンポジウム講演論文集(CD-ROM). 2016. 2016
  • 上川亮磨, 鵜飼重治, 大野直子, 増田紘士, 佐藤英一, 加藤章一, 古川智弘, 皆藤威二, 鳥丸忠彦, 木村晃彦, et al. FeCrAl-ODS鋼の高温クリープ変形に及ぼすZr添加効果. 日本鉄鋼協会日本金属学会両支部合同冬季講演大会概要集. 2016. 2016
  • Takai Toshihide, Nakajima Kunihisa, Furukawa Tomohiro. Development of measurement technique of the equilibrium vapor pressure of simulated fission products. JAEA-Technology 2015-002. 2015. 20
more...
Lectures and oral presentations  (157):
  • Feasible study for the production of At-211 using Liquid Bismuth Target System
    (International Chemical Congress of Pacific Basin Societies 2021 (Pacifichem 2021))
  • Corrosion behavior of iron-chrome alloys in liquid bismuth
    (28th International Conference on Nuclear Engineering; Nuclear Energy the Future Zero Carbon Power (ICONE 28))
  • Development of advanced reactor knowledge- and AI-aided design integration approach through the whole plant lifecycle, ARKADIA, 1; Overall plan
    (日本原子力学会2021年春の年会)
  • Development of liquid Bi target for continuous production of therapeutic radionuclide astatine-211, 4; Corrosion behavior of candidate materials for the target window in liquid bismuth under low oxygen partial pressure
    (日本原子力学会2021年春の年会)
  • Compatibility of Fe-Cr-Al alloys with liquid bismuth
    (Nuclear Materials Conference 2020 (NuMat 2020))
more...
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