High-temperature irradiation growth in Zircaloy

Conference · Thu Dec 31 23:00:00 EST 1981 · Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)

OSTI ID:6453757

Adamson, R B; Tucker, R P; Fidleris, V

Irradiation growth behavior of Zircaloy-2 and -4 was studied on specimens irradiated in an experimental breeder reactor. Measurements on Zircaloy-2 slab materials provided evidence that growth was a constant volume process up to 680 K. The growth strains were shown to be determined by the crystallographic texture. The growth strains for annealed and cold-worked Zircaloy were strongly dependent on irradiation temperature and varied linearly with fluence. The data suggest a transition from saturating steady-state growth at lower temperatures to increasing and eventually high steady-state rates at higher temperatures in the temperature range used (644-723K). 29 refs.

• Research Organization: Vallecitos Nucl Cent, Pleasanton, CA, USA
• OSTI ID: 6453757
• 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

Related Subjects

36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
BREEDER REACTORS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
COLD WORKING
EBR-2 REACTOR
ELECTRON MICROSCOPY
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
HEAT TREATMENTS
HIGH TEMPERATURE
IRON ADDITIONS
IRON ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MATERIALS WORKING
MICROSCOPY
NEUTRON FLUX
PHYSICAL RADIATION EFFECTS
POWER REACTORS
RADIATION EFFECTS
RADIATION FLUX
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
TEXTURE
TIN ALLOYS
TRANSMISSION ELECTRON MICROSCOPY
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS