MECHANISM FOR IN-REACTOR OXIDATION OF ZIRCONIUM ALLOYS FROM OXIDE ELECTRICAL CHARACTERISTICS .1. ZIRCALOY-2

被引：14

作者：

SHIRVINGTON, PJ ^{[1
]}

机构：

[1] AUSTRALIAN ATOM ENERGY COMM, RES ESTAB, LUCAS HTS, NEW S WALES, AUSTRALIA

来源：

JOURNAL OF NUCLEAR MATERIALS | 1974年 / 50卷 / 02期

关键词：

D O I：

10.1016/0022-3115(74)90155-X

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

引用

页码：183 / 199

页数：17

共 31 条

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[3]

ASHER RC, 1962, P IAEA S CORROSION R, P209

[4]

ASHER RC, 1969, UKAEA HARWELL INT RE

[5] EFFECTS OF RADIATION AND OXYGEN ON AQUEOUS OXIDATION OF ZIRCONIUM AND ITS ALLOYS AT 290 DEGREES C [J].

BRADHURST, DH ;

SHIRVINGTON, PJ ;

HEUER, PM .

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[6]

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[7]

CATHCART JV, 1961, CORROSION, V17, pT55

[8] EFFECTS OF IRRADIATION ON OXIDATION OF ZIRCONIUM ALLOYS IN HIGH TEMPERATURE AQUEOUS ENVIRONMENTS [J].

COX, B .

JOURNAL OF NUCLEAR MATERIALS, 1968, 28 (01) :1-&

[9]

COX B, 1969, J AUST I MET, V14, P123

[10] RATE CONTROLLING PROCESSES DURING PRE-TRANSITION OXIDATION OF ZIRCONIUM ALLOYS [J].

COX, B .

JOURNAL OF NUCLEAR MATERIALS, 1969, 31 (01) :48-&

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