Sizing of Zircaloy structurals (LWBR Development Program)
Technical Report
·
OSTI ID:6720613
Experiments in sizing large tubular Zircaloy structurals for nuclear core application by thermal, explosive, and cold hydraulic sizing techniques reveal that thermal sizing is the most suitable process of the three in achieving the required tight diametral and boundary surface tolerances. With cylindrical tubes up to 11/sup 1///sub 2/ inches in diameter by 103 inches long and wall thicknesses of 0.062 inch, tolerances which can be met consistently around any desired nominal diameter are +- 0.020 and plus 0.025 inch for the diametral tolerance and boundary diameter, respectively. As a result of strain-rate sensitivity of Zircaloy and limitations placed on the amount of elongation permitted which precluded removal of ovality, experiments in explosive sizing were discounted. Cold hydraulic sizing experiments were discontinued because of the dimensional instability of the sized component under subsequent thermal cycling. (NSA 21: 18234)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AT(11-1)-GEN-14
- OSTI ID:
- 6720613
- Report Number(s):
- WAPD-TM-620
- Country of Publication:
- United States
- Language:
- English
Similar Records
Deformation and collapse of fuel rod cladding due to external pressure (LWBR Development Program)
Recovery and recrystalization kinetics of cold-worked Zircaloy-4 plate and tubing (LWBR Development Program)
In-pile dimensional changes of Zircaloy-4 tubing having low hoop stresses (LWBR Development Program)
Technical Report
·
Sat Dec 31 23:00:00 EST 1966
·
OSTI ID:7098779
Recovery and recrystalization kinetics of cold-worked Zircaloy-4 plate and tubing (LWBR Development Program)
Technical Report
·
Wed Jan 31 23:00:00 EST 1968
·
OSTI ID:6746299
In-pile dimensional changes of Zircaloy-4 tubing having low hoop stresses (LWBR Development Program)
Technical Report
·
Thu Jul 01 00:00:00 EDT 1971
·
OSTI ID:7010518
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
BREEDER REACTORS
LWBR TYPE REACTORS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTORS
SIZE
TESTING
THERMAL REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
BREEDER REACTORS
LWBR TYPE REACTORS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTORS
SIZE
TESTING
THERMAL REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS