Phase equilibrium experiments on the simulated high-level waste glass containing platinum group elements

被引:9
作者
Sugawara, Toru [1 ]
Ohira, Toshiaki [1 ]
Minami, Kazuhiro [2 ,3 ]
Komamine, Satoshi [2 ]
Ochi, Eiji [2 ]
机构
[1] Akita Univ, Ctr Engn Sci, 1-1 Tegatagakuenmachi, Akita, Akita 0108502, Japan
[2] Japan Nucl Fuel Ltd, Reproc Business Div, Res & Dev Dept, 4-108 Okitsuke, Obuchi, Aomori 0393212, Japan
[3] Hokuriku Elect Power Co Inc, Shika Nucl Power Stn, 1 Akasumi, Shika, Ishikawa 9250161, Japan
关键词
fission product; glass waste form; high temperature; platinum group metal; SILICATE MELTS; IRON OXIDATION; LIQUID WASTE; GROUP-METALS; VITRIFICATION; BEHAVIOR; KINETICS; CRYSTALLIZATION; CONDUCTIVITY; RUTHENIUM;
D O I
10.1080/00223131.2015.1050474
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
Phase equilibrium experiments for the simulated high-level waste (HLW) glass containing palladium, rhodium and ruthenium discharged from a full scale mock up melter have been carried out between 1073 and 1473 K under air and CO2 atmosphere. The chemical compositions of Pd-Rh-Ru-Te (Pd metal phase) and (Ru, Rh)O-2 (Ru oxide phase) solid solutions and glass matrix were measured by electron probe micro analysis. Palladium content in the Pd metal phase decreased and ruthenium content in the Ru oxide phase increased with increasing temperature and decreasing oxygen fugacity due to progressive reduction of rhodium. The chemical compositions of these crystalline phases are independent of that of borosilicate glass matrix. Partition coefficient of rhodium between Pd metal phase and Ru oxide phase (K-Rh) can be expressed by ln K-Rh = 27264/T - 18.372 + ln f(o2) where T and f(O2) represent absolute temperature and oxygen fugacity. Based on the comparison of crystal compositions in the HLW glass with experimental results, it can be expected that the HLW glass examined in this study had been equilibrated in the temperature range from 1273 to 1373 K and oxygen fugacity close to that of air just before discharging from the melter.
引用
收藏
页码:380 / 390
页数:11
相关论文
共 45 条
[21]   Numerical analysis of platinum group particle behavior in vitrification melter [J].
Kawamura, Takumi ;
Ito, Kei ;
Sakai, Takaaki ;
Nakajima, Masayoshi ;
Fujiwara, Kouji ;
Ohshima, Hiroyuki .
Transactions of the Atomic Energy Society of Japan, 2008, 7 (03) :297-307
[22]   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
[23]   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
[24]   Kinetics of iron oxidation in silicate melts: a preliminary XANES study [J].
Magnien, V ;
Neuville, DR ;
Cormier, L ;
Mysen, BO ;
Briois, V ;
Belin, S ;
Pinet, O ;
Richet, P .
CHEMICAL GEOLOGY, 2004, 213 (1-3) :253-263
[25]  
Matlack KS, 2014, CERAM TRANS, V246, P225
[26]   CRYSTALLINE PHASES IN A DEVITRIFIED SIMULATED HIGH-LEVEL WASTE GLASS CONTAINING THE ELEMENTS OF THE PLATINUM GROUP [J].
MITAMURA, H ;
MURAKAMI, T ;
BANBA, T .
JOURNAL OF NUCLEAR MATERIALS, 1985, 136 (01) :104-116
[27]   SEGREGATION OF THE ELEMENTS OF THE PLATINUM GROUP IN A SIMULATED HIGH-LEVEL WASTE GLASS [J].
MITAMURA, H ;
MURAKAMI, T ;
BANBA, T ;
KIRIYAMA, Y ;
KAMIZONO, H ;
KUMATA, M ;
TASHIRO, S .
NUCLEAR AND CHEMICAL WASTE MANAGEMENT, 1983, 4 (03) :245-251
[28]   The effect of melt composition on trace element partitioning:: an experimental investigation of the activity coefficients of FeO, NiO, CoO, MoO2 and MoO3 in silicate melts [J].
O'Neill, HSC ;
Eggins, SM .
CHEMICAL GEOLOGY, 2002, 186 (1-2) :151-181
[29]  
Pegg IL, 2010, RAD WAST MAN 36 ANN
[30]  
Pentinghaus H, 1994, INT TOP M NUCL HAZ W