The change in the hardness of LCAC, TZM, and ODS molybdenum in the post-irradiated and annealed conditions

被引:29
作者
Cockeram, B. V. [1 ]
Smith, R. W. [1 ]
Byun, T. S. [2 ]
Snead, L. L. [2 ]
机构
[1] Bechtel Bettis Inc, W Mifflin, PA 15122 USA
[2] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
关键词
FAST-NEUTRON IRRADIATION; MO-5-PERCENT RE ALLOYS; CARBON ARC CAST; 300; DEGREES-C; TENSILE PROPERTIES; ELECTRICAL-RESISTIVITY; MECHANICAL-PROPERTIES; DEFECT RECOVERY; WROUGHT LCAC; TEMPERATURE;
D O I
10.1016/j.jnucmat.2009.04.025
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Hardness measurements were performed on wrought Low Carbon Arc Cast (LCAC), TZM, and Oxide Dispersion Strengthened (ODS) molybdenum in the post-irradiated and post-irradiated + annealed condition to determine the recovery kinetics. Irradiations performed in the High Flux Isotope Reactor (HFIR) at nominally 300 degrees C and 600 degrees C to neutron fluence levels that range from 10.5 to 246 x 10(24) n/m(2) (E > 0.1 MeV) resulted in relatively large increases in hardness (77-109%), while small increases in hardness (<18%) were observed for irradiations at 870-1100 degrees C. The hardness recovery for ODS and LCAC irradiated at 300 degrees C and 600 degrees C were shown to be complete at 980 degrees C and approximate to 1100-1250 degrees C, respectively. Isothermal annealing at 700 degrees C was used to determine the activation energy for recovery of LCAC and ODS (3.70-4.88 eV +/- 0.28-0.77 eV), which is comparable to values reported in the literature for molybdenum vacancy self-diffusion. This suggests that recovery of LCAC and ODS is controlled by the solid-state diffusion of vacancies in the bulk, and that the finer grain size and particle size ODS does not affect this mechanism. TZM exhibited slower recovery kinetics, which can be explained by the solute atoms (titanium and zirconium) inhibiting vacancy diffusion. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:12 / 21
页数:10
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