Abstract
The microstructural changes and corresponding effects on mechanical properties, electrical resistivity and density of Nb-1Zr were examined following neutron irradiation up to 1.8 dpa at temperatures of 1073, 1223 and 1373 K and compared with material thermally aged for similar exposure times of ∼1100 h. Thermally driven changes in the development of intragranular and grain boundary precipitate phases showed a greater influence on mechanical and physical properties compared to irradiation-induced defects for the examined conditions. Initial formation of the zirconium oxide precipitates was identified as cubic structured plates following a Baker-Nutting orientation relationship to the β-Nb matrix, with particles developing a monoclinic structure on further growth. Tensile properties of the Nb-1Zr samples showed increased strength and reduced elongation following aging and irradiation below 1373 K, with the largest tensile and hardness increases following aging at 1098 K. Tensile properties at 1373 K for the aged and irradiated samples were similar to that of the as-annealed material. Total elongation was lower in the aged material due to a strain hardening response, rather than a weak strain softening observed in the irradiated materials due in part to an irregular distribution of the precipitates in the irradiated materials. Though intergranular fracture surfaces were observed on the 1248 K aged tensile specimens, the aged and irradiated material showed uniform elongations >3% and total elongation >12% for all conditions tested. Cavity formation was observed in material irradiated to 0.9 dpa at 1073 and 1223 K. However, since void densities were estimated to be below 3 × 1017 m-3 these voids contributed little to either mechanical strengthening of the material or measured density changes.
Original language | English |
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Pages (from-to) | 286-302 |
Number of pages | 17 |
Journal | Journal of Nuclear Materials |
Volume | 414 |
Issue number | 2 |
DOIs | |
State | Published - Jul 15 2011 |
Funding
The authors thank Marie Williams, Mike Pershing, and Cliff Davison for their help in the acid cleaning and annealing of the specimens prior to thermal aging; Jeffrey McNabb and Bob Sitterson for welding and leak testing the alloy 600 aging cans; Brian Sparks and David Harper for thermal aging the encapsulated materials; and J. Wade Jones and Mary J. Myers for their help in preparing samples for microscopy. Research at the Oak Ridge National Laboratory (ORNL) SHaRE User Center was sponsored by the Division of Materials Sciences and Engineering, DOE. ORNL is managed for the DOE by UT-Battelle, LLC, under Contract No. DE-AC-05-00OR22725.
Funders | Funder number |
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U.S. Department of Energy | |
Oak Ridge National Laboratory | |
Division of Materials Sciences and Engineering | |
UT-Battelle | DE-AC-05-00OR22725 |