Zircaloy growth: in-reactor dimensional changes in Zircaloy-4 fuel assemblies
Technical Report
·
OSTI ID:4075082
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. (auth)
- Research Organization:
- Combustion Engineering, Inc., Windsor, Conn. (USA)
- NSA Number:
- NSA-33-022002
- OSTI ID:
- 4075082
- Report Number(s):
- CENPD--198
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*FUEL CANS-- PHYSICAL RADIATION EFFECTS
*PWR TYPE REACTORS-- FUEL CANS
*ZIRCALOY 4-- PHYSICAL RADIATION EFFECTS
210200* --Nuclear Power Plants--Power Reactors
Non- Breeding
Light-Water Moderated
Non-Boiling Water Cooled
ANNEALING
FUEL ASSEMBLIES
GRAIN GROWTH
N50240 --Metals
Ceramics
& Other Materials--Metals & Alloys--Radiation Effects
N77200* --Reactors--Power Reactors
Non-breeding
Light- water Moderated
Non-boiling Water-cooled
STRAINS
*PWR TYPE REACTORS-- FUEL CANS
*ZIRCALOY 4-- PHYSICAL RADIATION EFFECTS
210200* --Nuclear Power Plants--Power Reactors
Non- Breeding
Light-Water Moderated
Non-Boiling Water Cooled
ANNEALING
FUEL ASSEMBLIES
GRAIN GROWTH
N50240 --Metals
Ceramics
& Other Materials--Metals & Alloys--Radiation Effects
N77200* --Reactors--Power Reactors
Non-breeding
Light- water Moderated
Non-boiling Water-cooled
STRAINS