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Murakami, Tsuyoshi*; Hayashi, Hirokazu
Journal of Nuclear Materials, 558, p.153330_1 - 153330_7, 2022/01
Times Cited Count：2 Percentile：20.20(Materials Science, Multidisciplinary)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.
Abe, Mitsushi*; Bae, S.*; Beer, G.*; Bunce, G.*; Choi, H.*; Choi, S.*; Chung, M.*; da Silva, W.*; Eidelman, S.*; Finger, M.*; et al.
Progress of Theoretical and Experimental Physics (Internet), 2019(5), p.053C02_1 - 053C02_22, 2019/05
Times Cited Count：161 Percentile：99.30(Physics, Multidisciplinary)This paper introduces a new approach to measure the muon magnetic moment anomaly 
and the muon electric dipole moment (EDM) 
at the J-PARC muon facility. The goal of our experiment is to measure 
and using an independent method with a factor of 10 lower muon momentum, and a factor of 20 smaller diameter storage-ring solenoid compared with previous and ongoing muon g-2 experiments with unprecedented quality of the storage magnetic field. Additional significant differences from the present experimental method include a factor of 1000 smaller transverse emittance of the muon beam (reaccelerated thermal muon beam), its efficient vertical injection into the solenoid, and tracking each decay positron from muon decay to obtain its momentum vector. The precision goal for is a statistical uncertainty of 450 parts per billion (ppb), similar to the present experimental uncertainty, and a systematic uncertainty less than 70 ppb. The goal for EDM is a sensitivity of 
e
cm.
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：17.72(Chemistry, Multidisciplinary); ; ; ; ; ; ; ; ; Ono, Akio; et al.
Journal of Nuclear Science and Technology, 23(1), p.53 - 72, 1986/00
Times Cited Count：11 Percentile：74.48(Nuclear Science & Technology)no abstracts in English
Murakami, Tsuyoshi*; Iizuka, Masatoshi*; Hayashi, Hirokazu
no journal, ,
no abstracts in English
Murakami, Tsuyoshi*; Iizuka, Masatoshi*; Hayashi, Hirokazu
no journal, ,
no abstracts in English
Kitamura, Koichi; Hayashi, Hirokazu; Morishita, Yoshitsugu; Murakami, Kazuo*; Namba, Haruyuki*; Matsuo, Kiyoshi*
no journal, ,
no abstracts in English
Yamashita, Shinichiro; Mohamad, A. B.; Ioka, Ikuo; Nemoto, Yoshiyuki; Kawanishi, Tomohiro; Kaji, Yoshiyuki; Osaka, Masahiko; Murakami, Nozomu*; Owaki, Masao*; Sasaki, Masana*; et al.
no journal, ,
Japan's Accident Tolerant Fuel (ATF) research and development (R&D) program has been conducted since 2015 in cooperation with power plant providers, fuel venders and universities for making the most use of the experiences in R&D, practical design, and evaluations of fuels and cores of commercial Light Water Reactors (LWRs). An overview of the present R&D progress is given, in relation to the role of Japan Atomic Energy Agency (JAEA) in the program. The ATF candidate materials currently under consideration are the following three claddings: the silicon carbide (SiC) composite which is potentially applicable for Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR), the FeCrAl steel strengthened by dispersion of fine oxide particles (FeCrAl-ODS) for BWR, and Cr-coated zircalloy claddings for PWR. In addition to the cladding materials, R&D on the SiC-made BWR channel box and accident tolerant control rods are also underway.
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.
