A MODEL FOR WATERSIDE OXIDATION OF ZIRCALOY FUEL CLADDING IN PRESSURIZED WATER-REACTORS

被引：15

作者：

ALMARSHAD, AIA ^{[1
]}

KLEIN, AC ^{[1
]}

机构：

[1] OREGON STATE UNIV,CTR RADIAT,DEPT NUCL ENGN,CORVALLIS,OR 97331

来源：

JOURNAL OF NUCLEAR MATERIALS | 1991年 / 183卷 / 03期

关键词：

D O I：

10.1016/0022-3115(91)90487-R

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

A model is developed to simulate the oxidation of Zircaloy fuel rod cladding exposed to pressurized water reactor operating conditions. The model is used to predict the oxidation rate for both ex- and in-reactor conditions in terms of the weight gain and oxide thickness. Comparisons of the model predictions with experimental data show very good agreement.

引用

页码：186 / 194

页数：9

共 17 条

[1]

ALMARSHAD AIA, 1990, THESIS OREGON STATE

[2]

BILLOT P, 1989, ASTM STP, V1023, P165

[3] DIFFUSION IN A SEMI-INFINITE SYSTEM WITH A MOVING INTERPHASE CONSIDERING SOLVENT DENSITY CHANGE - APPLICATION TO THE OXIDATION OF ZIRCONIUM [J].

DENIS, A ;

GARCIA, EA .

JOURNAL OF NUCLEAR MATERIALS, 1981, 96 (1-2) :127-140

[4] A MODEL FOR THE OXIDATION OF ZIRCONIUM-BASED ALLOYS [J].

DOLLINS, CC ;

JURSICH, M .

JOURNAL OF NUCLEAR MATERIALS, 1983, 113 (01) :19-24

[5]

DOMAGALA RF, 1954, T AM I MIN MET ENG, V200, P238

[6]

FORSYTHE GE, 1960, FINITE DIFFERENCE ME

[7] DIFFUSION IN A SEMI-INFINITE SYSTEM WITH A MOVING INTERFACE AT CONSTANT TEMPERATURE FOR APPLICATION TO ALPHA-ZIRCONIUM OXIDATION AT HIGH-TEMPERATURE [J].

GARCIA, EA .

JOURNAL OF NUCLEAR MATERIALS, 1980, 92 (2-3) :249-256

[8]

GARZAROLLI F, 1980, EPRINP1472 EL POW RE

[9]

Hillner E., 1977, ZIRCONIUM NUCL IND, P211, DOI DOI 10.1520/STP35573S

[10]

HILLNER E, 1962, WAPDTM03 BETT AT LAB

← 1 2 →