DISSOLUTION OF SOLID UO2 BY MOLTEN ZIRCALOY

被引:22
作者
VESHCHUNOV, MS
HOFMANN, P
机构
[1] HAUPTABT INGN,INST MAT,D-76021 KARLSRUHE,GERMANY
[2] RUSSIAN ACAD SCI,INST NUCL SAFETY,MOSCOW 113191,RUSSIA
关键词
13;
D O I
10.1016/0022-3115(94)90244-5
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
On the basis of different experimental data from separate-effect tests on the kinetics Of UO2 interaction with molten Zircaloy at 1900-degrees-C and exceeding temperatures, a theoretical model is proposed which describes the material behavior during different stages of the chemical interaction process before and after liquid phase saturation. In the first stage dissolution of UO2 and quick saturation of the Zircaloy melt by U and O atoms take place. In the second stage the UO2 dissolution continues with a lower reaction rate and a parabolic time law (is-proportional-to t1/2), and is accompanied by precipitation and growth of a ceramic phase in the liquid. It is shown that the main cause of the discrepancy amongst the different experimental results found in the literature is connected with different dimensions of the UO2 Crucibles and different UO2/Zircaloy mass ratios used in the experiments. The analysis in the present paper leads to recommendations for the application of measured Arrhenius correlations for the kinetics of UO2 dissolution by molten Zircaloy in fuel rods during severe reactor accidents by renormalization of the UO2 dissolution rates.
引用
收藏
页码:27 / 40
页数:14
相关论文
共 13 条
[1]  
ADROGUER B, 1992, AICHE S SERIES, V88, P275
[2]  
ALLISON CM, 1992, SCDAP RELAP5 MOD3 AS
[3]   LWR FUEL-ROD BEHAVIOR DURING SEVERE ACCIDENTS [J].
HAGEN, S ;
HOFMANN, P .
NUCLEAR ENGINEERING AND DESIGN, 1987, 103 (01) :85-106
[4]  
HAYWARD PJ, UNPUB J NUCL MATER
[5]  
Hofmann P., 1989, Nuclear Technology, V87, P146
[6]  
HOFMANN P, 1988, MAR P INT S SEV ACC, P3
[7]   DISSOLUTION OF URANIUM-DIOXIDE BY MOLTEN ZIRCALOY .2. CONVECTION-CONTROLLED REACTION [J].
KIM, KT ;
OLANDER, DR .
JOURNAL OF NUCLEAR MATERIALS, 1988, 154 (01) :102-115
[9]   THE CHEMICAL DIFFUSIVITY OF OXYGEN IN UO2-X [J].
OLANDER, DR .
JOURNAL OF NUCLEAR MATERIALS, 1982, 110 (2-3) :352-352
[10]  
OLANDER DR, UNPUB NUCL ENG DES