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

[1]

*ASTM, 1998, 117497 ASTM EBS C

[2] THE EFFECTS OF THE ALPHA-RADIOLYSIS OF WATER ON THE CORROSION OF UO2 [J].

BAILEY, MG ;

JOHNSON, LH ;

SHOESMITH, DW .

CORROSION SCIENCE, 1985, 25 (04) :233-238

[3]

BETTERIDGE JS, 1997, AECL11647 COG96331I

[4] Construction of an electrode for irradiated UO2 fuel and preliminary results concerning its use in aqueous solutions [J].

Bottomley, PDW ;

Wegen, DH ;

Coquerelle, M .

JOURNAL OF NUCLEAR MATERIALS, 1996, 238 (01) :23-37

[5]

BRUNO J, 1995, MATER RES SOC SYMP P, V353, P601, DOI 10.1557/PROC-353-601

[6] A new uranyl oxide hydrate phase derived from spent fuel alteration [J].

Buck, EC ;

Wronkiewicz, DJ ;

Finn, PA ;

Bates, JK .

JOURNAL OF NUCLEAR MATERIALS, 1997, 249 (01) :70-76

[7] Retention of neptunium in uranyl alteration phases formed during spent fuel corrosion [J].

Buck, EC ;

Finch, RJ ;

Finn, PA ;

Bates, JK .

SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXI, 1998, 506 :87-94

[8] Incorporation mechanisms of actinide elements into the structures of U6+ phases formed during the oxidation of spent nuclear fuel [J].

Burns, PC ;

Ewing, RC ;

Miller, ML .

JOURNAL OF NUCLEAR MATERIALS, 1997, 245 (01) :1-9

[9] The crystal structure of ianthinite, [U-2(4+)(UO2)(4)O-6(OH)(4)(H2O)(4)](H2O)(5): a possible phase for Pu4+ incorporation during the oxidation of spent nuclear fuel [J].

Burns, PC ;

Finch, RJ ;

Hawthorne, FC ;

Miller, ML ;

Ewing, RC .

JOURNAL OF NUCLEAR MATERIALS, 1997, 249 (2-3) :199-206

[10]

CASAS I, 1993, MATER RES SOC SYMP P, V294, P67, DOI 10.1557/PROC-294-67

← 1 2 3 4 5 6 7 8 9 10 →