Fuel corrosion processes under waste disposal conditions

被引：363

作者：

Shoesmith, DW ^{[1
]}

机构：

[1] Univ Western Ontario, Dept Chem, London, ON N6A 5B7, Canada

来源：

JOURNAL OF NUCLEAR MATERIALS | 2000年 / 282卷 / 01期

关键词：

D O I：

10.1016/S0022-3115(00)00392-5

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The release of the majority of radionuclides from spent nuclear fuel under permanent disposal conditions will be controlled by the rate of dissolution of the UO2 fuel matrix. In this manuscript the mechanism of the coupled anodic (fuel dissolution) and cathodic (oxidant reduction) reactions which constitute the overall fuel corrosion process is reviewed, and the many published observations on fuel corrosion under disposal conditions discussed. The primary emphasis is on summarizing the overall mechanistic behaviour and establishing the primary factors likely to control fuel corrosion. Included are discussions on the influence of various oxidants including radiolytic ones, pH, temperature, groundwater composition, and the formation of corrosion product deposits. The relevance of the data recorded on unirradiated UO2 to the interpretation of spent fuel behaviour is included. Based on the review, the data used to develop fuel corrosion models under the conditions anticipated in Yucca Mountain (NV, USA) are evaluated. (C) 2000 Elsevier Science B.V. All rights reserved.

引用

页码：1 / 31

页数：31

共 95 条

[71]

SIEGMANNN E, 1997, WAST FORMS DEGR EXP

[72]

STEWARD SA, 1994, MATER RES SOC S P, V465, P557

[73]

STEWARD SA, 1997, MATER RES SOC S P, V333, P409

[74]

STEWARD SA, 1994, P 5 INT C HIGH LEV R, P2602

[75]

STOUT RB, 1997, UCRL10108314

[76]

StroesGascoyne S, 1997, MAT RES S C, V465, P511

[77] Calculation of used nuclear fuel dissolution rates under anticipated Canadian waste vault conditions [J].

Sunder, S ;

Shoesmith, DW ;

Kolar, M ;

Leneveu, DM .

JOURNAL OF NUCLEAR MATERIALS, 1997, 250 (2-3) :118-130

[78] OXIDATION OF UO2 FUEL BY THE PRODUCTS OF GAMMA-RADIOLYSIS OF WATER [J].

SUNDER, S ;

SHOESMITH, DW ;

CHRISTENSEN, H ;

MILLER, NH .

JOURNAL OF NUCLEAR MATERIALS, 1992, 190 :78-86

[79] Anodic oxidation and dissolution of CANDU fuel (UO2) in slightly alkaline sodium perchlorate solutions [J].

Sunder, S ;

Strandlund, LK ;

Shoesmith, DW .

ELECTROCHIMICA ACTA, 1998, 43 (16-17) :2359-2372

[80] Oxidation and dissolution of nuclear fuel (UO2) by the products of the alpha radiolysis of water [J].

Sunder, S ;

Shoesmith, DW ;

Miller, NH .

JOURNAL OF NUCLEAR MATERIALS, 1997, 244 (01) :66-74

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