Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment

被引:82
作者
Röllin, S
Spahiu, K
Eklund, UB
机构
[1] Studsv Nucl AB, Hot Cell Lab, S-61160 Nykoping, Sweden
[2] SKB, S-10240 Stockholm, Sweden
关键词
D O I
10.1016/S0022-3115(01)00645-6
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Dissolution rates of spent UO2 fuel have been investigated using flow-through experiments under oxidizing, anoxic and reducing conditions. For oxidizing conditions, approximately congruent dissolution rates were obtained in the pH range 3-9.3 for U, Np, Ba, Tc, Cs, Sr and Rb. For these elements, steady-state conditions were obtained in the flow rate range 0.02-0.3 ml min(-1). The dissolution rates were about 3 mg d(-1) m(-2) for pH > 6. For pH < 6, dissolution rates were strongly increasing for decreasing pH. Incongruent dissolution was found for Zr, Mo, Ru, Rh, Pd, Am and the lanthanides. The dissolution rates with H-2(g) saturated solutions dropped by up to four orders of magnitude as compared to oxidizing conditions. Because of the very low concentrations, only U, Pu, Am, Mo, Te and Cs could be measured. For anoxic conditions, both the redox potential and dissolution rates increased approaching the same values as under oxidizing conditions. (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:231 / 243
页数:13
相关论文
共 41 条
[1]  
ALONSO JIG, 1993, RADIOCHIM ACTA, V62, P71
[2]  
Alonso JIG, 1996, J RADIOAN NUCL CH AR, V203, P19
[3]  
[Anonymous], 1992, 9220 SKB SWED NUCL F
[4]   THE KINETICS OF DISSOLUTION OF UO2 UNDER REDUCING CONDITIONS AND THE INFLUENCE OF AN OXIDIZED SURFACE-LAYER (UO2+X) - APPLICATION OF A CONTINUOUS FLOW-THROUGH REACTOR [J].
BRUNO, J ;
CASAS, I ;
PUIGDOMENECH, I .
GEOCHIMICA ET COSMOCHIMICA ACTA, 1991, 55 (03) :647-658
[5]  
BRUNO J, 1999, 9926 SKB SWED NUCL F
[6]  
CASAS I, 1994, RADIOCHIM ACTA, V66-7, P23
[7]  
CUI D, 2000, IN PRESS MAT RES SOC
[8]  
dePablo J, 1997, MAT RES S C, V465, P535
[9]   Solid surface evolution model to predict uranium release from unirradiated UO2 and nuclear spent fuel dissolution under oxidizing conditions [J].
dePablo, J ;
Casas, I ;
Gimenez, J ;
Marti, V ;
Torrero, ME .
JOURNAL OF NUCLEAR MATERIALS, 1996, 232 (2-3) :138-145
[10]   Dissolution of irradiated fuel: A radiolytic mass balance study [J].
Eriksen, TE ;
Eklund, UB ;
Werme, L ;
Bruno, J .
JOURNAL OF NUCLEAR MATERIALS, 1995, 227 (1-2) :76-82