Damage stucture in zirconium alloys irradiated at 573 to 923/sup 0/K. [Neutron fluence 1 x 10/sup 25/ n. m/sup -2/]
The microstructures of annealed zirconium, Zircaloy-2 and Zr-2.5 wt % Nb alloy and of Zr-2.5 Nb containing ..cap alpha..' were studied after neutron irradiation to fluences approximately equal to 1 x 10/sup 25/ n x m/sup -2/ in the temperature range 573 to 923/sup 0/K. The principal form of damage was dislocation loops which increased in size and decreased in density with increasing temperature and which did not exist above 773/sup 0/K. The Burgers vector of the loops was consistent with a/3 <1120>. Half or more of the loops were of vacancy type. No dislocation networks or voids were seen. It is argued that the bias of loops for self-interstitial atoms in ..cap alpha..-zirconium is very weak, permitting competitive vacancy and interstitial loops, preventing growth of loops into gross dislocation structure, and depressing the vacancy super-saturation so that voids cannot arise.
- Research Organization:
- Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.; Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6652366
- Report Number(s):
- CONF-780818-6
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
360101 -- Metals & Alloys-- Preparation & Fabrication
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CREEP
CRYSTAL STRUCTURE
DAMAGE
ELEMENTS
IRON ADDITIONS
IRON ALLOYS
MECHANICAL PROPERTIES
METALS
MICROSTRUCTURE
NIOBIUM ALLOYS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
SWELLING
TIN ALLOYS
TRANSITION ELEMENTS
VOIDS
ZIRCALOY
ZIRCALOY 2
ZIRCONIUM
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS