Kinetics of UO2 oxidation in steam atmosphere

被引：15

作者：

Dobrov, BV

Likhanskii, VV

Ozrin, VD

Solodov, AA

Kissane, MP

Manenc, H

机构：

[1] Russian Acad Sci, Nucl Safety Inst, Moscow 113191, Russia

[2] Russian Res Ctr Triniti, Moscow 113191, Russia

[3] CE Cadarache, Inst Protect & Surete Nucl, F-13108 St Paul Durance, France

来源：

JOURNAL OF NUCLEAR MATERIALS | 1998年 / 255卷 / 01期

关键词：

D O I：

10.1016/S0022-3115(97)00364-4

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

An adsorption model for calculation of UO(2 )oxidation in H2O/H-2 gas mixture is proposed. The model is based on the assumption that the rate of fuel oxidation by steam is controlled mainly by surface oxygen exchange reactions which are described in terms of Langmuir-like theory. Corrections to the oxidation rate related to the volume diffusion of oxygen are taken into account using an adiabatic approach to the diffusion problem. Parameters of the model were optimized on the experiments with steam pressure up to 10(5) Pa at 1200 to 2000 K. (C) 1998 Elsevier Science B.V. All rights reserved.

引用

收藏

页码：59 / 66

页数：8

相关论文

共 13 条

[1] HIGH-TEMPERATURE OXIDATION OF UO2 IN STEAM-HYDROGEN MIXTURES [J].

ABREFAH, J ;

BRAID, AD ;

WANG, W ;

KHALIL, Y ;

OLANDER, DR .

JOURNAL OF NUCLEAR MATERIALS, 1994, 208 (1-2) :98-110

[2] STEAM OXIDATION KINETICS AND OXYGEN DIFFUSION IN UO2 AT HIGH TEMPERATURES [J].

BITTEL, JT ;

SJODAHL, LH ;

WHITE, JF .

JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1969, 52 (08) :446-&

[3] SURFACE-CONTROLLED OXIDATION-REDUCTION OF UO2 [J].

CARTER, RE ;

LAY, KW .

JOURNAL OF NUCLEAR MATERIALS, 1970, 36 (01) :77-&

[4]

Cox D.S., 1990, P INT S HIGH TEMP OX

[5]

Cox D.S., 1986, P S CHEM PHEN ASS RA

[6] KINETICS AND MECHANISM OF OXIDATION AND REDUCTION OF WUSTITE IN MIXTURES OF WATER VAPOR AND HYDROGEN [J].

GALA, A ;

GRABKE, HJ .

ARCHIV FUR DAS EISENHUTTENWESEN, 1972, 43 (06) :463-&

[7] DEFECT STRUCTURE AND OXYGEN DIFFUSION IN UO2+DELTA [J].

GOFF, JP ;

FAK, B ;

HAYES, W ;

HUTCHINGS, MT .

JOURNAL OF NUCLEAR MATERIALS, 1992, 188 :210-215

[8] A KINETIC-MODEL FOR FISSION-PRODUCT RELEASE AND FUEL OXIDATION BEHAVIOR FOR ZIRCALOY-CLAD FUEL-ELEMENTS UNDER REACTOR ACCIDENT CONDITIONS [J].

LEWIS, BJ ;

COX, DS ;

IGLESIAS, FC .

JOURNAL OF NUCLEAR MATERIALS, 1993, 207 :228-241

[9] Modelling the release behaviour of cesium during severe fuel degradation [J].

Lewis, BJ ;

Andre, B ;

Morel, B ;

Dehaudt, P ;

Maro, D ;

Purdy, PL ;

Cox, DS ;

Iglesias, FC ;

Osborne, MF ;

Lorenz, RA .

JOURNAL OF NUCLEAR MATERIALS, 1995, 227 (1-2) :83-109

[10] A MODEL FOR FISSION-GAS RELEASE AND FUEL OXIDATION BEHAVIOR FOR DEFECTED UO2 FUEL-ELEMENTS [J].

LEWIS, BJ ;

IGLESIAS, FC ;

COX, DS ;

GHEORGHIU, E .

NUCLEAR TECHNOLOGY, 1990, 92 (03) :353-362