Strain ageing in zirconium alloys

Veevers, K.

doi:10.1016/0022-3115(75)90140-3

Cited by 12 publications

(1 citation statement)

References 3 publications

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“…One possible explanation can be advanced on the basis of the effect of strain aging. Strain aging of Zr, 38 Zr alloys, 39 Zr-0 alloys, 40 Zircaloy-2, 41 " 43 and Zircaloy-4 43 has been reported in the temperature range of 150-750°C. Strain aging at 250-330°C is generally attributed to the interaction of oxygen with dislocations, 40 " 42 whereas a similar interaction of Sn has been suspected for the strain aging at 750°C.…”

Section: Effect Of Cold Workmentioning

confidence: 99%

Characteristics of Autoclave and In-Reactor Nodular Corrosion of Zircaloys

Jeong

Rheem

Chung

1991

Zirconium in the Nuclear Industry: Ninth International Symposium

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Nodular corrosion characteristics of recrystallized Zircaloy-4 were investigated in static autoclave tests at 500°C and 10.3 MPa. The roles of annealing temperature, cooling rate after beta-treating at 1050°C, cold work, and surface treatment in corrosion tests were correlated with the results of microstructural characterization by scanning and transmission electron microscopies. A good correlation was obtained between average size of intermetallic precipitates and weight gain, in contrast to nodule coverage and nodule number density. These results could be best explained by the hypothesis that nodules nucleate in local regions that are depleted of Fe and Cr alloying elements. Some observations were inconsistent with the premise that nodules nucleate on or near intermetallic precipitates. Nodular corrosion characteristics and microstructures of commercial Zircaloy-2 cladding of fuel and gadolinia rods, obtained from several BWRs after burnup of 11-30 MWd/kgU, were also examined. Partial amorphization of intermetallic precipitates in BWR

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