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Kanamura, Shohei*; Takahashi, Yuya*; Omori, Takashi*; Nohira, Toshiyuki*; Sakamura, Yoshiharu*; Matsumura, Tatsuro
Denki Kagaku, 88(3), p.289 - 290, 2020/09
no abstracts in English
Kitawaki, Shinichi; Sakamura, Yoshiharu*
Denki Kagaku Oyobi Kogyo Butsuri Kagaku, 79(12), p.975 - 976, 2011/12
no abstracts in English
Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo; Sakamura, Yoshiharu*; Murakami, Tsuyoshi*; Akiyama, Naoyuki*
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/09
In the FaCT project, the metal fuel cycle including metal fuel fast reactor and pyrochemical reprocessing has been being developed. JAEA and CRIEPI have continued a collaborative study on pyrochemical reprocessing. In the pyrochemical reprocessing, actinides in the spent fuels dissolve anodically in the LiCl-KCl, and U is collected selectively on a solid cathode, Pu and MA are recovered simultaneously in a liquid Cd cathode. In the previous electrorefining tests, at the anode Zr was allowed to dissolve into the electrolyte salt together with U, Pu and MA. The Zr co-dissolution may cause some problems. In this study, through the anode dissolution test of U-Pu-Zr alloy fuel, the controlling the dissolution of the Zr and the improvement of dissolution ratio of U, Pu were studied. The U-Pu alloy was prepared from MOX pellets by using the electrochemical reduction method. U-Pu-Zr ternary alloy was produced by alloying the obtained U-Pu alloy and prepared U-Zr alloy. U-Pu-Zr ternary alloy was immersed into electrolyte salt, and electrolysis test was carried out.
Murakami, Tsuyoshi*; Sakamura, Yoshiharu*; Akiyama, Naoyuki*; Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo
Journal of Nuclear Materials, 414(2), p.194 - 199, 2011/07
Times Cited Count：17 Percentile：77.43(Materials Science, Multidisciplinary)An electrorefining is one of the main steps of pyrochemical reprocessing of spent metallic fuels (U-Zr, U-Pu-Zr). The electrorefining is carried out dissolving a portion of Zr together with actinides to accomplish a high dissolution ratio of actinides. However, the electrorefining with Zr co-dissolution should bring some practical problems in the pyrochemical reprocessing. Therefore, electrorefining tests of non-irradiated U-Pu-Zr alloy were performed with minimizing the amount of Zr dissolved in LiCl-KCl-(U, Pu, Am)Cl
melts at 773 K. The tests were performed both by potentiostatic electrolysis at -1.0 V (Ag
/Ag) that was more negative than the Zr dissolution potential and by galvanostatic electrolysis with a limited amount of Zr dissolution. The ICP-AES analysis of the anode residues confirmed that a high dissolution ratio of actinides (U; 
99.6%, Pu; 99.9%) was successfully demonstrated at both electrolyses.
O meltKato, Tetsuya*; Sakamura, Yoshiharu*; Iwai, Takashi; Arai, Yasuo
Radiochimica Acta, 97(4-5), p.183 - 186, 2009/05
Times Cited Count：4 Percentile：30.49(Chemistry, Inorganic & Nuclear)The solubility of Pu and rare-earths were measured in LiCl-LiO melt where the sesquioxides were precipitated. As shown in the solubility measurement of Pu(III), Nd(III) and Gd(III) at 923 K, the solubility increased proportionally with LiO concentration in the melt. It was also found that the element of larger ionic radius has higher solubility as far as the trivalent rare-earths and Pu.
, PuO and rare earth oxides using ZrCl
in LiCl-KCl eutectic meltSakamura, Yoshiharu*; Inoue, Tadashi*; Iwai, Takashi; Moriyama, Hirotake*
Journal of Nuclear Materials, 340(1), p.39 - 51, 2005/04
Times Cited Count：40 Percentile：91.4(Materials Science, Multidisciplinary)A new chlorination method using ZrCl in a molten salt has been investigated for the pyrometallurgical reprocessing of spent oxide fuels. UO, PuO and rare earth oxides(LaO, CeO, NdO and YO) were allowed to react with ZrCl in a LiCl-KCl eutectic salt at 500
C to give a metal chloride solution and a precipitate of ZrO. By keeping the system quite still, the solution settled so that the ZrO precipitate could be separated.
Sakamura, Yoshiharu*; Shirai, Osamu; Iwai, Takashi; Suzuki, Yasufumi
Journal of Alloys and Compounds, 321(1), p.76 - 83, 2001/05
Times Cited Count：57 Percentile：89.52(Chemistry, Physical)no abstracts in English
Kato, Tetsuya*; Nakamura, Kinya*; Sakamura, Yoshiharu*; Iwai, Takashi; Arai, Yasuo
no journal, ,
no abstracts in English
from spent fuel with LiCl-KCl; Preliminary experiment by simulated spent fuel consisted of UO and noble metalsOkamura, Nobuo; Koizumi, Tsutomu; Fukushima, Mineo; Kurata, Masaki; Sakamura, Yoshiharu*
no journal, ,
no abstracts in English
O in molten LiCl-LiOKato, Tetsuya*; Sakamura, Yoshiharu*; Iwai, Takashi; Arai, Yasuo
no journal, ,
In order to apply the pyrometallurgical reprocessing to spent oxide fuels, reduction techniques of oxide in molten salt have been studied. In the previous reduction experiments, a small amount of Pu has been found to move out of the reduced fuel and dissolve into molten LiCl-LiO. In this study, solubility of Pu in molten LiCl-LiO was measured to obtain quantitative data for the Pu dissolution. The Pu solubility in the molten LiCl-LiO containing PuO precipitates increased with increasing LiO concentration in the molten salt to be approximately 0.3wt%Pu at 8wt%LiO and 923 K.
Kitawaki, Shinichi; Nakayoshi, Akira; Sakamura, Yoshiharu*; Akiyama, Naoyuki*
no journal, ,
no abstracts in English
Sakamura, Yoshiharu*; Murakami, Tsuyoshi*; Akiyama, Naoyuki*; Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo
no journal, ,
no abstracts in English
Sakamura, Yoshiharu*; Murakami, Tsuyoshi*; Akiyama, Naoyuki*; Iizuka, Masatoshi*; Kitawaki, Shinichi; Nakayoshi, Akira
no journal, ,
no abstracts in English
Kitawaki, Shinichi; Nakayoshi, Akira; Sakamura, Yoshiharu*; Akiyama, Naoyuki*
no journal, ,
no abstracts in English
Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo; Murakami, Tsuyoshi*; Sakamura, Yoshiharu*; Akiyama, Naoyuki*
no journal, ,
no abstracts in English
Murakami, Tsuyoshi*; Sakamura, Yoshiharu*; Akiyama, Naoyuki*; Kitawaki, Shinichi; Nakayoshi, Akira; Koyama, Tadafumi*
no journal, ,
no abstracts in English
and (U,Zr)O in a LiCl moltenNakayoshi, Akira; Kitawaki, Shinichi; Kofuji, Hirohide; Sakamura, Yoshiharu*; Akiyama, Naoyuki*
no journal, ,
no abstracts in English
O meltSakamura, Yoshiharu*; Iizuka, Masatoshi*; Koyama, Tadafumi*; Kitawaki, Shinichi; Nakayoshi, Akira; Kofuji, Hirohide
no journal, ,
An electrolytic reduction process of oxide fuels has recently been developed, however it was found that the behaviors of rare earth elements and zirconium are expected to be complicate because their oxides are stable and complex oxide compounds may form. After Fukushima- Daiichi reactor accident, studies on applicability of pyrometallurgical process to damaged fuel debris consisting of ZrO-UO have been started. In this study, reduction behaviors of ZrO, ZrO-LiO and ZrO-UO were investigated. It was proved that ZrO can be reduced to metallic form in LiCl melt and that ZrO easily reacts with dissolved LiO to give LiZrO. After ZrO is converted to LiZrO, zirconium metal is hardly obtained even in a LiCl melt with low LiO concentration.
in LiCl-LiO meltSakamura, Yoshiharu*; Iizuka, Masatoshi*; Kitawaki, Shinichi; Nakayoshi, Akira; Kofuji, Hirohide
no journal, ,
Zirconium dioxide formed complex oxide like LiZrO or Li
ZrO
according to the concentration of LiO in the LiCl-LiO melt. It was clarified that ZrO could be reduced to metal and formed lithium zirconate was difficult to be reduced by electrolytic reduction operations.
OKitawaki, Shinichi; Nakayoshi, Akira; Kofuji, Hirohide; Sakamura, Yoshiharu*; Iizuka, Masatoshi*
no journal, ,
no abstracts in English
