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Ishitsuka, Etsuo; Ho, H. Q.; Kitagawa, Kanta*; Fukuda, Takahito*; Ito, Ryo*; Nemoto, Masaya*; Kusunoki, Hayato*; Nomura, Takuro*; Nagase, Sota*; Hashimoto, Haruki*; et al.
JAEA-Technology 2023-013, 19 Pages, 2023/06
JAEA-Technology-2023-013.pdf:1.75MB
Eight people from five universities participated in the 2022 summer holiday practical training with the theme of "Technical development on HTTR". The participants practiced the feasibility study for nuclear battery, the burn-up analysis of HTTR core, the feasibility study for 
Cf production, the analysis of behavior on loss of forced cooling test, and the thermal-hydraulic analysis near reactor pressure vessel. In the questionnaire after this training, there were impressions such as that it was useful as a work experience, that some students found it useful for their own research, and that discussion with other university students was a good experience. These impressions suggest that this training was generally evaluated as good.
Kitagawa, Kanta*; Matsuura, Hideaki*; Kawai, Hitomi*; Katayama, Kazunari*; Otsuka, Teppei*; Ishitsuka, Etsuo; Nakagawa, Shigeaki; Goto, Minoru*; Tobita, Kenji*; Konishi, Satoshi*; et al.
no journal, ,
Tritium production using a high temperature gas cooled reactor has been studied to get for the start-up of an initial DEMO fusion reactor and for technical testing of related tritium circulation systems. The characteristics of hydrogen absorption in the case of change from room temperature to high temperature for zirconium particle with nickel coating was obtained and investigated the analytical simulation model. And the configuration (for example, the numbers of zirconium particle with nickel coating and the amount of LiAlO
) of test specimen for irradiation test and the test method were discussed.