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Waterside corrosion of Zircaloy-clad fuel rods in a PWR environment

Conference · · Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
OSTI ID:6461011
; ; ; ;

A data base of Zircaloy corrosion behavior under PWR operating conditions has been established from previously published reports as well as from new Kraftwerk Union (KWU) fuel examinations. The data show that the reactor environment increases the corrosion. ZrO/sub 2/ film thermal conductivity is another major factor that influences corrosion behavior. It was inferred from KWU film thickness data that the oxide film thermal conductivity may decrease once circumferential cracks develop in the layer. 57 refs.

Research Organization:
Kraftwerk Union, Erlangen, Ger
OSTI ID:
6461011
Report Number(s):
CONF-800834-
Journal Information:
Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States); ISSN ASTTA
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
CHEMICAL REACTIONS
CORROSION
FUEL CANS
FUEL ELEMENTS
FUEL RODS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS