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Hayashi, Hirokazu; Shibata, Hiroki; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo
Proceedings of 2008 Joint Symposium on Molten Salts (USB Flash Drive), p.910 - 915, 2008/10
R&D of the nitride fuel cycle technology is underway at JAEA. Behavior of americium (Am) in the pyrochemical process, which include anodic dissolution of AmN and recovery of Am into liquid Cd cathode by electrorefining in LiCl-KCl eutectic melts, and nitride formation of Am recovered in liquid Cd cathode, are presented.
/U
and U/U couples in molten LiCl-RbCl eutecticNagai, Takayuki; Uehara, Akihiro*; Fujii, Toshiyuki*; Shirai, Osamu*; Sato, Nobuaki*; Yamana, Hajimu*
Proceedings of 2008 Joint Symposium on Molten Salts (USB Flash Drive), p.927 - 932, 2008/10
Formal redox potentials of the U/U and U/U couples in molten LiCl-RbCl eutectic were determined by cyclic voltammetry. These redox potentials were more negative than those in the LiCl-KCl eutectic but approximately similar to those in the NaCl-CsCl eutectic. These redox potentials in molten alkali chlorides would be correlated with the averaged alkali cationic radius of the melt.
Toda, Taro*; Maruyama, Takehiro*; Moritani, Kimikazu*; Moriyama, Hirotake*; Hayashi, Hirokazu
Proceedings of 2008 Joint Symposium on Molten Salts (USB Flash Drive), p.933 - 938, 2008/10
The distribution coefficients of Am and Ce were measured in the LiCl-KCl/Ga system at 773 K. By using ZrCl
as the oxide ion scavenger in order to avoid the formation of such oxychlorides as CeO
and AmO, the effect of oxide ion concentration was well controlled on the distribution coefficients of Am and Ce. The separation factor between Am and Ce was then obtained to be about 100. By comparing the present value with the other experimental and the predicted ones, it was confirmed that solvent metals were ordered from the most selective to the less selective one as Al
GaBiCd.
Fujita, Reiko*; Nakamura, Hitoshi*; Mizuguchi, Koji*; Utsunomiya, Kazuhiro*; Amamoto, Ippei
Proceedings of 2008 Joint Symposium on Molten Salts (USB Flash Drive), p.886 - 891, 2008/10
Pyrochemical treatment in molten salts is a promising process for decontamination of radioactive wastes without producing large amounts of secondary waste. In this report, the fundamental experiment was carried out to treat the wastes which had complicated shapes such as Magnoxend corps, metallic waste contaminated by uranium, spent chemical trap fillers and spent Zircaloy channel boxs from BWR and acquired good results.
Inoue, Tadashi*; Koyama, Tadafumi*; Myochin, Munetaka; Arai, Yasuo
Proceedings of 2008 Joint Symposium on Molten Salts (USB Flash Drive), p.851 - 856, 2008/10
Recent progress of pyrochemical reprocessing technology based on metal electrorefining process and nitride electrorefining process is introduced. This technology can be applied to oxide fuel as well as metal fuel by adding the oxide reduction process. In addition to the development of process technology for electrorefining, thermodynamic database of actinides and lanthanides in molten salt or liquid metal has been prepared. The progress of pyrochemical reprocessing technology, which has the advantage of proliferation resistance and whole recovery of minor actinides, has been demonstrated.