Radiation-enhanced relaxation in Zircaloy-4 and in a zirconium--2. 5 wt. percent niobium--0. 5 wt. percent copper alloy (LWBR Development Program)

Technical Report · Fri Mar 01 04:00:00 EST 1968

OSTI ID:6746016

Kreyns, P H; Burkart, M W

An irradiation-enhanced strain relaxation has been observed in Zircaloy-4 and in a zirconium + 2.5 wt % niobium + 0.5 wt % copper alloy for fast-neutron fluxes of 2.4 x 10/sup 14/ nv > 1 MeV. The effects of several material and test parameters were investigated, and the results compared with out-of-pile stress relaxation data using a thermally-activated creep model. It was found that in-reactor relaxation of Zircaloy-4 was temperature and structure sensitive, independent of initial stress, and consistent with an accelerated thermal creep model. (NSA 22: 43622)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 6746016
• Report Number(s): WAPD-TM-746
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BREEDER REACTORS
COPPER ADDITIONS
COPPER ALLOYS
LWBR TYPE REACTORS
NIOBIUM ALLOYS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTORS
STRESS RELAXATION
TEMPERATURE DEPENDENCE
THERMAL REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS