An assessment of the influence of microstructure and test conditions on the irradiation growth phenomenon in zirconium alloys

Murgatroyd, R.A.; Rogerson, A.

doi:10.1016/0022-3115(80)90261-5

Cited by 63 publications

(7 citation statements)

References 8 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…All the important properties of zirconium alloys are dependent on the microstructure obtained from the manufacturing process. Several different processing routes to optimize the microstructure of fuel rods are proposed in literature [4][5][6] with most of them indicating the recrystallized microstructure as more suitable for nuclear applications 7,8 . In fact, most of zirconium alloys in Pressurized Water Reactors (PWR) display a partial or fully-recrystallized microstructure 8 .…”

Section: Introductionmentioning

confidence: 99%

Hydrogen Kinetics and Hydride Formation Effect on Zr-1Nb and Zr-1Nb-1Sn-0.1Fe Alloys for Nuclear Application

et al. 2018

View full text Add to dashboard Cite

The purpose of this study was to investigate the kinetics of hydrogen absorption and hydride formation and their effect on the mechanical properties in Zr-1Nb and Zr-1Nb-1Sn-0.1Fe alloys, which were thermomechanically processed and gaseously hydrided at 320ºC under 10 bar hydrogen pressure. X-ray diffraction (XRD) confirmed the formation of α-Zr matrix after final heat treatment. The alloys absorbed almost the same amount of hydrogen, although with different kinetics. Absorption began almost immediately in Zr-1Nb alloy whilst in Zr-1Nb-1Sn-0.1Fe hydrogen absorption started after 11 h besides a faster hydrogen kinetics. Results showed that tensile strengths for both alloys were nearly independent of absorbed hydrogen. Fractographic examinations indicated ductile fractures for unhydrided condition whereas quasi-cleavage features were observed for all hydrided specimens.

show abstract

Section: Introductionmentioning

confidence: 99%

Hydrogen Kinetics and Hydride Formation Effect on Zr-1Nb and Zr-1Nb-1Sn-0.1Fe Alloys for Nuclear Application

et al. 2018

View full text Add to dashboard Cite

show abstract

“…Early results for cold-worked material irradiated at 330-350 K demonstrates the same shrinkage along directions containing a high proportion c-axes as at high temperatures [8] showing that true growth is occurring (at approximately constant volume), by precipitation of SIAs on the prism planes and vacancies on the basal planes. The fact that the growth rate does not saturate in cold-worked materials as it does in annealed materials shows that the network dislocations are acting as sinks for the point defects, which would otherwise recombine.…”

Section: Introductionmentioning

confidence: 84%

Deformation of zirconium irradiated by 4.4 MeV protons at 347 K

Chow

Holt

Woo

et al. 2004

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…Recrystallized zirconium alloys are suitable for nuclear applications because of their low irradiation growth [5], and high irradiation creep resistance [6,7]. In addition, recrystallized microstructures are indispensable during a manufacturing since a recrystallization enables a stress relief that should be performed to restore a ductility after a cold deformation process.…”

Section: Introductionmentioning

confidence: 99%