Pyrochemical Reprocessing of Used Nuclear Fuel

被引:4
作者
Koyama, T. [1 ]
Sakamura, Y. [1 ]
Iizuka, M. [1 ]
机构
[1] Cent Res Inst Elect Power Ind, Adv Fuel Cycle Sect, Nucl Technol Res Lab, Tokyo 2018511, Japan
来源
MOLTEN SALTS AND IONIC LIQUIDS 17 | 2010年 / 33卷 / 07期
关键词
METAL; ACTINIDES; PLUTONIUM; SALT; PU;
D O I
10.1149/1.3484792
中图分类号
O646 [电化学、电解、磁化学];
学科分类号
081704 ;
摘要
Pyrochemical reprocessing has potential advantage in proliferation resistance, reduction of waste burden and economy. The authors have been developing pyrochemistry since late 80s with both domestic and international collaborations. In addition to electrochemical properties in LiCl-KCl eutectic melt, thermodynamic properties have been measured. Flowsheet has been developed through experiments with using active and inactive elements. Demonstration of feasibility in industrialization is carried out through development of engineering-scale equipments. This paper summarize the current progress of the study.
引用
收藏
页码:339 / 349
页数:11
相关论文
共 19 条
  • [1] [Anonymous], JRC ITU ANN REP 2009
  • [2] Chow L. S., 1993, P GLOB 93 SEATTL WA
  • [3] Hijikata T., 2009, J POWER ENERGY SYST, V3, P170
  • [4] Development of High-Temperature Transport Technologies for Liquid Cadmium in Pyrometallurgical Reprocessing
    Hijikata, Takatoshi
    Koyama, Tadafumi
    [J]. JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME, 2009, 131 (04):
  • [5] Electrochemical reduction of (U-40Pu-5Np)O2 in molten LiCl electrolyte
    Iizuka, Masatoshi
    Sakamura, Yoshiharu
    Inoue, Tadashi
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2006, 359 (1-2) : 102 - 113
  • [6] Development of an Innovative Electrorefiner for High Uranium Recovery Rate from Metal Fast Reactor Fuels
    Iizuka, Masatoshi
    Uozumi, Koichi
    Ogata, Takanari
    Omori, Takashi
    Tsukada, Takeshi
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2009, 46 (07) : 699 - 716
  • [7] Actinide recycling by pyro-process with metal fuel FBR for future nuclear fuel cycle system
    Inoue, T
    [J]. PROGRESS IN NUCLEAR ENERGY, 2002, 40 (3-4) : 547 - 554
  • [8] JOHNSON I, 1965, T METALL SOC AIME, V233, P1408
  • [9] Countercurrent Extraction Test with Continuous Flow of Molten LiCl-KCl Salt and Liquid Cd for Pyro-Reprocessing of Metal FBR Fuel
    Kinoshita, Kensuke
    Tsukada, Takeshi
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2010, 47 (02) : 211 - 218
  • [10] Koyama, P GLOB 2009