2006
DOI: 10.2172/896213
|View full text |Cite
|
Sign up to set email alerts
|

Oxidation of Zircaloy Fuel Cladding in Water-Cooled Nuclear Reactors

Abstract: Our work involves the continued development of the theory of passivity and passivity breakdown, in the form of the Point Defect Model, with the emphasis on zirconium and zirconium alloys in reactor coolant environments, the measurement of critically-important parameters, and the development of a code that can be used by reactor operators to actively manage the accumulation of corrosion damage to the fuel cladding in both BWRs and PWRs. In addition, the modified boiling crevice model has been further developed … Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...

Citation Types

0
0
0

Year Published

2008
2008
2008
2008

Publication Types

Select...
1

Relationship

1
0

Authors

Journals

citations
Cited by 1 publication
references
References 12 publications
0
0
0
Order By: Relevance