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Murakami, Tsuyoshi*; Hayashi, Hirokazu
Journal of Nuclear Materials, 558, p.153330_1 - 153330_7, 2022/01
Excess amounts of dissolution agents, CdCl
and ZrCl
, are required to dissolve transuranium (TRU: Pu and minor actinides) nitrides into LiCl-KCl melts at the chemical dissolution step, which is the first step in the reprocessing of used nitride fuels. We propose an electrochemical process where the remaining Zr and Cd are recovered from the melts to be recycled as dissolution agents for the chemical dissolution step, leaving TRU in the melts. Since the initial concentration ratio of CdCl/ZrCl remaining in the melts would depend on the condition of the chemical dissolution step and would vary during the proposed electrochemical recovery process, electrochemical behaviors of Zr and Cd were investigated in LiCl-KCl melts with various concentration ratios of CdCl/ZrCl at 723 K to confirm the basic feasibility of the proposed process. Potentiostatic electrolysis was performed using a liquid Cd cathode at -1.05 V (vs. Ag/AgCl), which was a more positive potential than the redox potentials of TRU on the liquid Cd electrode. The obtained results showed that the current efficiency for recovering Zr and Cd from the melts was as high as 100% regardless of the CdCl/ZrCl concentration ratio in the melts.
cuprates studied by resonant inelastic X-ray scatteringIshii, Kenji; Hoesch, M.*; Inami, Toshiya; Kuzushita, Kaori*; Owada, Kenji; Tsubota, Masami; Murakami, Yoichi; Mizuki, Junichiro; Endo, Yasuo; Tsutsui, Kenji*; et al.
Journal of Physics and Chemistry of Solids, 69(12), p.3118 - 3124, 2008/12
Times Cited Count：3 Percentile：19.29(Chemistry, Multidisciplinary); ; ; ; ; ; ; ; ; Ono, Akio; et al.
Journal of Nuclear Science and Technology, 23(1), p.53 - 72, 1986/00
Times Cited Count：8 Percentile：67.65(Nuclear Science & Technology)no abstracts in English
Kitamura, Koichi; Hayashi, Hirokazu; Morishita, Yoshitsugu; Murakami, Kazuo*; Namba, Haruyuki*; Matsuo, Kiyoshi*
no journal, ,
no abstracts in English
Kasamatsu, Tetsuhiro*; Nagashima, Tomomi*; Nagai, Kiyoe*; Nagamine, Takeaki*; Murakami, Hirokazu*; Koka, Masashi; Yamada, Naoto; Kitamura, Akane; Sato, Takahiro; Yokoyama, Akihito; et al.
no journal, ,
no abstracts in English
Takano, Masahide; Hayashi, Hirokazu; Murakami, Tsuyoshi*; Arima, Tatsumi*
no journal, ,
The overall plan of "R&D on Nitride Fuel Cycle Technologies for MA Transmutation in the Aspects of Safety and Economy" entrusted by MEXT (FY 2017-2020) is introduced in this presentation. The main subjects are (1) fuel fabrication technologies, (2) fuel behavior during transmutation, and (3) pyrochemical reprocessing technologies. In the subject (1), application of sol-gel process and economical use of N-15 enriched nitrogen gas will be treated. Application of laser-heating technique for melting point measurement to the nitride will be examined in the subject (2), as well as the compatibility between the nitride and the candidate cladding material, and He release behavior at high temperature. In the subject (3), the chemical dissolution of the nitride into molten salt will be examined as a potential, alternative technique to the electrolysis.
Murakami, Tsuyoshi*; Iizuka, Masatoshi*; Hayashi, Hirokazu
no journal, ,
no abstracts in English
Kofuji, Hirohide; Tada, Kohei; Kitawaki, Shinichi; Hayashi, Hirokazu; Murakami, Tsuyoshi*; Sakamura, Yoshiharu*
no journal, ,
Metal electrorefining technology which is the most promising method of pyro-reprocessing has been developed in JAEA under the collaboration with CRIEPI. Through the research and development, feasibility of the process had been confirmed and design of process equipment and facility has been progressed. Technology would be expected suitable for the future nuclear fuel cycle concept which will be focused on reduction of environmental burden of the radioactive waste.
Murakami, Tsuyoshi*; Iizuka, Masatoshi*; Hayashi, Hirokazu
no journal, ,
no abstracts in English
Murakami, Tsuyoshi*; Iizuka, Masatoshi*; Hayashi, Hirokazu
no journal, ,
no abstracts in English
