Published December 1975
| Version v1
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Zircaloy growth: in-reactor dimensional changes; in Zircaloy-4 fuel assemblies
Description
The position of Combustion Engineering (C-E) on the in-reactor growth of Zircaloy-4 fuel assembly components is described. A model relating growth strain to neutron fluence is developed by empirical fit. The data base is divided into three groups to reflect the difference between annealed and cold worked material and to separate fuel rods from non-fueled specimens. A literature discussion of the proposed mechanisms of irradiation growth is included in support of the empirical model
Availability note (English)
MF available from INIS under the Report Number.
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Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 34 p.
- Report number
- CENPD--198
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7252298
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- ANNEALING; FUEL ASSEMBLIES; FUEL CANS; GRAIN GROWTH; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; STRAINS; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; HEAT TREATMENTS; RADIATION EFFECTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Combustion Engineering, Inc., Windsor, CT.