Strengthening of ordered Zr/sub 3/Al by fast neutron irradiation
Journal Article
·
· Acta Metall.; (United States)
The room temperature tensile properties have been measured of Zr/sub 3/Al irradiated by fast neutrons to a dose of 1.4 x 10/sup 24/ n/m/sup 2/. Yielding occurs discontinuously and is accompanied by the propagation of a Lueders band within which the strain, epsilon/sub L//sup phi/, is given by epsilon/sub L//sup phi/ = lambda/sup phi/d/sup -1/2/, where lambda/sup phi/ is an experimental parameter and d is the average grain size. The flow stress, sigma/sub f//sup phi/, including the yield strength, obeys an expression of the form sigma/sub f//sup phi/ = sigma/sub 0//sup phi/(epsilon) + k/sup phi/d/sup -1/2/ where sigma/sub 0//sup phi/(epsilon) and k/sup phi/ are experimental parameters; sigma/sub 0//sup phi/(epsilon) increases linearly with plastic strain, epsilon, while k/sup phi/ remains constant. The work-hardening rate is essentially independent of the grain size, as are the tensile strength and the ductility. Fracture occurs in a ductile mode. When compared with the behavior of unirradiated material, the results show that the irradiation increases the yield strength and decreases the work-hardening rate, but has little effect on the tensile strength, ductility and fracture.
- Research Organization:
- Chalk River Nuclear Lab., Ont.
- OSTI ID:
- 6556563
- Journal Information:
- Acta Metall.; (United States), Journal Name: Acta Metall.; (United States) Journal Issue: 8 Vol. 26:8; ISSN AMETA
- Country of Publication:
- United States
- Language:
- English
Similar Records
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THE DUCTILE-BRITTLE TRANSITION IN BODY-CENTRED CUBIC TRANSITION METALS
Journal Article
·
Sat Dec 31 23:00:00 EST 1977
· Acta Metall.; (United States)
·
OSTI ID:6783206
Effects of grain size on the strength and ductility of Ni sub 3 Al and Ni sub 3 Al + boron
Conference
·
· TMS (The Metallurgical Society) Paper Selection; (USA)
·
OSTI ID:5449966
THE DUCTILE-BRITTLE TRANSITION IN BODY-CENTRED CUBIC TRANSITION METALS
Journal Article
·
Wed Jan 31 23:00:00 EST 1962
· Phil. Mag.
·
OSTI ID:4828450
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360102 -- Metals & Alloys-- Structure & Phase Studies
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
ALUMINIUM ALLOYS
CRYSTAL STRUCTURE
FAILURES
FRACTURES
GRAIN SIZE
HARDENING
IMPURITIES
MECHANICAL PROPERTIES
MICROSTRUCTURE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR MATERIALS
SIZE
STRAIN HARDENING
SURFACES
TENSILE PROPERTIES
YIELD STRENGTH
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360102 -- Metals & Alloys-- Structure & Phase Studies
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
ALUMINIUM ALLOYS
CRYSTAL STRUCTURE
FAILURES
FRACTURES
GRAIN SIZE
HARDENING
IMPURITIES
MECHANICAL PROPERTIES
MICROSTRUCTURE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR MATERIALS
SIZE
STRAIN HARDENING
SURFACES
TENSILE PROPERTIES
YIELD STRENGTH
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS