Vitrification of high-level radioactive waste considering the behavior of platinum group metals

被引:18
作者
Uruga, Kazuyoshi [1 ]
Sawada, Kayo [1 ]
Enokida, Youichi [1 ]
Yamamoto, Ichiro [1 ]
机构
[1] Nagoya Univ, EcoTopia Sci Inst, Chikusa Ku, Nagoya, Aichi 4648603, Japan
关键词
platinum group metals; high-level radioactive waste; melter; liquid metal; copper;
D O I
10.1016/j.pnucene.2007.11.036
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
To demonstrate a method using liquid metal for the removal of PGMs during the vitrification process of high-level radioactive waste, removal of Pd was performed using Cu from molten glass containing fission products such as Nd, Sr, Zr, Mo, Te and Ni. Almost all the Pd, 93%, was extracted into liquid Cu and removed as a separable Cu-Pd metal button from the glass. Tellurium and Ni were also extracted 42 and 5.6%, respectively. Nearly 100% of the other elements, especially the heat generating elements such as Sr and Cs, for which Na was used as a substitute of Cs remained in the glass. (C) 2007 Elsevier Ltd. All rights reserved.
引用
收藏
页码:514 / 517
页数:4
相关论文
共 11 条
[1]   Long-term alteration mechanisms in water for SON68 radioactive borosilicate glass [J].
Advocat, T ;
Jollivet, P ;
Crovisier, JL ;
del Nero, M .
JOURNAL OF NUCLEAR MATERIALS, 2001, 298 (1-2) :55-62
[2]   PHASE-DIAGRAM OF NA2O-B2O3-SIO2 SYSTEM [J].
GHANBARIAHARI, K ;
CAMERON, AM .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1993, 76 (08) :2017-2022
[3]   DEVELOPMENT OF PARTITIONING AND TRANSMUTATION TECHNOLOGY FOR LONG-LIVED NUCLIDES [J].
INOUE, T ;
SAKATA, M ;
MIYASHIRO, H ;
MATSUMURA, T ;
SASAHARA, A ;
YOSHIKI, N .
NUCLEAR TECHNOLOGY, 1991, 93 (02) :206-220
[4]   RECOVERY OF NOBLE-METALS FROM FISSION-PRODUCTS [J].
JENSEN, GA ;
PLATT, AM ;
MELLINGER, GB ;
BJORKLUND, WJ .
NUCLEAR TECHNOLOGY, 1984, 65 (02) :305-324
[5]  
Kanehira Norio, 2005, P GLOBAL 2005 TSUK J
[6]   PROPERTIES AND BEHAVIOR OF THE PLATINUM GROUP-METALS IN THE GLASS RESULTING FROM THE VITRIFICATION OF SIMULATED NUCLEAR-FUEL REPROCESSING WASTE [J].
KRAUSE, C ;
LUCKSCHEITER, B .
JOURNAL OF MATERIALS RESEARCH, 1991, 6 (12) :2535-2546
[7]   Thermochemistry of nuclear waste glasses: an experimental determination [J].
Linard, Y ;
Yamashita, I ;
Atake, T ;
Rogez, J ;
Richet, P .
JOURNAL OF NON-CRYSTALLINE SOLIDS, 2001, 286 (03) :200-209
[8]   Development of glasses for the vitrification of high level liquid waste (HLLW) in a joule heated ceramic melter [J].
Luckscheiter, B ;
Nesovic, M .
WASTE MANAGEMENT, 1996, 16 (07) :571-578
[9]   RECOVERY AND MUTUAL SEPARATION OF NOBLE-METALS FROM THE SIMULATED INSOLUBLE RESIDUE OF SPENT FUEL [J].
NAITO, K ;
MATSUI, T ;
NAKAHIRA, H ;
KITAGAWA, M ;
OKADA, H .
JOURNAL OF NUCLEAR MATERIALS, 1991, 184 (01) :30-38
[10]   RECOVERY OF NOBLE-METALS FROM INSOLUBLE RESIDUE OF SPENT FUEL [J].
NAITO, K ;
MATSUI, T ;
TANAKA, Y .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1986, 23 (06) :540-549