Defect clusters in neutron-irradiated vanadium containing oxygen

Bajaj, R.; Wechsler, M. S.

doi:10.1007/bf02642830

Cited by 15 publications

(3 citation statements)

References 28 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…[5]. The barrier strength of dislocation loops has been shown to vary with the level of solute segregation, such as observed for vanadium [69]. For the as-irradiated materials [4], the differences in the calculated and measured irradiation hardening for the irradiated Zircaloy-2 and Zircaloy-4 were theorized to result from the influence of solute atoms on the barrier strength of the loops and the level of solute segregation.…”

Section: Irradiation Hardening and Microstructurementioning

confidence: 96%

The recovery of irradiation damage for Zircaloy-2 and Zircaloy-4 following low dose neutron irradiation at nominally 358 °C

Cockeram

Leonard

Byun

et al. 2015

Journal of Nuclear Materials

View full text Add to dashboard Cite

a b s t r a c tThe recovery of irradiation damage in wrought Zircaloy-2 and Zircaloy-4 was determined following a series of post-irradiation anneals at temperatures ranging from 343°C to 510°C and for time periods ranging from 1-h to 500 h. The materials had been irradiated at nominally 358°C in the High Flux Isotope Reactor (HFIR) at neutron fluences of nominally 3 Â 10 25 n/m 2 (E > 1 MeV). Irradiation at nominally 358°C resulted in a coarser distribution of hai loops that result in a 25-45% lower irradiation hardening than reported in the literature for irradiations at 260-326°C. The irradiation hardening and recovery were determined using tensile testing at room-temperature. Post-irradiation annealing at 343-427°C was shown to result in an increase in irradiation hardening to values even higher than for the as-irradiated material in the first 1-10 h of annealing. This Radiation Anneal Hardening (RAH) was followed by a relatively slow recovery of the irradiation damage. Much faster recovery with no RAH was observed for post-irradiation annealing at temperatures of 454-510°C. Irradiation at 358°C was shown to result in different recovery kinetics than observed in the literature for irradiation at 260-326°C. While the general trend described above is true for the four materials tested (alpha-annealed and beta-treated Zircaloy-2 and Zircaloy-4), notable and yet unexplained differences in RAH and in recovery are observed between the materials that might be a result of differing solute effects. Examinations of microstructure using Transmission Electron Microscopy were used to investigate the RAH and recovery mechanisms. Agreement between the measured and calculated irradiation hardening using a generalized Orowan hardening model to account for the observed loop structure was not as close for the post irradiation annealed condition as for the as-irradiated condition, which can likely be attributed to unaccounted for changes in the configuration of the hai loops to dislocation lines, segregation of solutes to dislocation loops, and the potential for the formation of fine clusters of point defects or solutes during annealing.

show abstract

Section: Irradiation Hardening and Microstructurementioning

confidence: 96%

The recovery of irradiation damage for Zircaloy-2 and Zircaloy-4 following low dose neutron irradiation at nominally 358 °C

Cockeram

Leonard

Byun

et al. 2015

Journal of Nuclear Materials

View full text Add to dashboard Cite

show abstract

“…The defect cluster density and size distribution were analyzed for the irradiated and post-irradiation annealed conditions in high purity single crystal vanadium containing oxygen as impurity atoms with concentrations ranging from 95 to 500 wt. ppm [13]. The results showed that the density of defect clusters increases with increasing oxygen concentration.…”

Section: Defect Clustersmentioning

confidence: 93%

Computer simulation of plastic deformation in irradiated metals

Çolak

View full text Add to dashboard Cite

“…CLUSTER SIZE (A)Defect cluster density size-distribution function n' vs defect cluster size in as-irradiated and post-irradiation annealed (to 400*C) vanadium -500 wt ppm oxygen. Refs (11,63). …”

mentioning

confidence: 99%

Dispersed barrier hardening in irradiated metals

Beck

View full text Add to dashboard Cite

Defect clusters in neutron-irradiated vanadium containing oxygen

Cited by 15 publications

References 28 publications

The recovery of irradiation damage for Zircaloy-2 and Zircaloy-4 following low dose neutron irradiation at nominally 358 °C

The recovery of irradiation damage for Zircaloy-2 and Zircaloy-4 following low dose neutron irradiation at nominally 358 °C

Computer simulation of plastic deformation in irradiated metals

Dispersed barrier hardening in irradiated metals

Contact Info

Product

Resources

About