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Journal Articles

Electrochemical recovery of Zr and Cd from molten chloride salts for reprocessing of used nitride fuels

Murakami, Tsuyoshi*; Hayashi, Hirokazu

Journal of Nuclear Materials, 558, p.153330_1 - 153330_7, 2022/01

Excess amounts of dissolution agents, CdCl$$_2$$ and ZrCl$$_4$$, 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$$_2$$/ZrCl$$_4$$ 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$$_2$$/ZrCl$$_4$$ 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$$_2$$/ZrCl$$_4$$ concentration ratio in the melts.

Journal Articles

Momentum-resolved charge excitations in high-$$T$$$$_{rm c}$$ cuprates studied by resonant inelastic X-ray scattering

Ishii, 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)

Journal Articles

Non-destructive and destructive measurements on burnup characteristics of Japan Power Demonstration Reactor-I full-core fuel assemblies

; ; ; ; ; ; ; ; ; 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

Oral presentation

Development of C-14 decontamination technology in concrete

Kitamura, Koichi; Hayashi, Hirokazu; Morishita, Yoshitsugu; Murakami, Kazuo*; Namba, Haruyuki*; Matsuo, Kiyoshi*

no journal, , 

no abstracts in English

Oral presentation

Measurement of trace elements in an erythrocyte of myelodysplastic syndrome (MDS) using in-air micro-PIXE

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

Oral presentation

R&D on nitride fuel cycle technologies for MA transmutation in the aspects of safety and economy, 1; Introduction of overall plan

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.

Oral presentation

R&D on nitride fuel cycle for MA transmutation to enhance safety and economy, 8; Reductive extraction of Zr and Ce in liquid Cd

Murakami, Tsuyoshi*; Iizuka, Masatoshi*; Hayashi, Hirokazu

no journal, , 

no abstracts in English

Oral presentation

Details of research and development for pyrochemical reprocessing in JAEA

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.

Oral presentation

R&D on nitride fuel cycle for MA transmutation to enhance safety and economy, 13; Reductive extraction of Zr and lanthanides in liquid Cd

Murakami, Tsuyoshi*; Iizuka, Masatoshi*; Hayashi, Hirokazu

no journal, , 

no abstracts in English

Oral presentation

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