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Murakami, Tsuyoshi*; Hayashi, Hirokazu
Journal of Nuclear Materials, 558, p.153330_1 - 153330_7, 2022/01
Times Cited Count：0 Percentile：0.01(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.
Fujita, Reiko*; *; Kondo, Naruhito*; Utsunomiya, Kazuhiro*
JNC TJ8420 2000-004, 41 Pages, 2000/03
JNC-TJ8420-2000-004.pdf:5.08MB
no abstracts in English
H.-R.Paur*; Namba, Hideki; Tokunaga, Okihiro; H.Maetzing*
Aerosols: Science,Industry,Health and Environment,Vol. 2, p.745 - 748, 1991/00
no abstracts in English
Sakamura, Yoshiharu*; Uruga, Kazuyoshi*; Ando, Hidekazu*; Kitawaki, Shinichi; Nakayoshi, Akira; Kofuji, Hirohide
no journal, ,
no abstracts in English
Hayashi, Hirokazu; Sato, Takumi; Shibata, Hiroki; Kurata, Masaki
no journal, ,
Uranium-free nitride fuel was chosen as the first candidate for transmutation of long-lived minor actinides (MA) using accelerator-driven system (ADS) under the double strata fuel cycle concept by Japan Atomic Energy Agency (JAEA). The advantages of nitride fuel are good thermal properties and large mutual solubility among actinide elements. A pyrochemical process has been proposed as the first candidate for reprocessing of the spent MA nitride fuel, because this technique has some advantages over aqueous process, such as the resistance to radiation damage, compactness of the facility, margin of criticality, and recycling feasibility of N-15. This presentation overviews recent progress and future R&D plan on the pyrochemical treatment of spent nitride fuel in JAEA.
Murakami, Tsuyoshi*; Sakamura, Yoshiharu*; Iizuka, Masatoshi*; Nohira, Toshiyuki*; Kitawaki, Shinichi; Kofuji, Hirohide
no journal, ,
no abstracts in English
Hayashi, Hirokazu
no journal, ,
no abstracts in English
Murakami, Tsuyoshi*; Iizuka, Masatoshi*; Hayashi, Hirokazu
no journal, ,
no abstracts in English
