SEDL / STP / STP681-EB / STP36679S



Primary Creep of Zircaloy-2 Under Irradiation

Fidleris, V
Senior research officer, Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories, Chalk River, Ontario


Pages: 12    Published: Jan 1979


Download this paper for $25 PDF (160K)          View License Agreement
Abstract

Primary in-reactor creep of Zircaloy-2 exhibits approximately linear plots of log(creep strain, ϵ) against log (test time, t) that fit relations of the type ϵ = βtm. For longitudinal specimens of cold-worked Zircaloy-2 at about 570 K, neutron flux of 1 × 1017 n m-2 s-1 (E > 1 MeV) and stresses σ below 310 MPa, the parameters β and m are given by β = (1.5 × 10-5) exp[(1.055 × 10-2)σ] and m = 0.24 + (4.5 × 10-4)σ Increasing the neutron flux from 1 to 3 × 1017 n m-2 s-1 or temperature from 490 to 620 K increases the value of β but has little effect on the time exponent m.

Primary creep of annealed Zircaloy-2 at temperatures between 470 and 570 K shows an abrupt decrease in the time exponent after about 10 h. Irradiation before stressing decreases primary creep strain of annealed and of cold-worked Zircaloy-2 at stresses above 300 MPa, but slightly increases primary creep of cold-worked Zircaloy-2 below about 200 MPa.


Keywords:
zirconium, zirconium alloys, irradiation, fast neutrons, primary creep, anisotropy

Paper ID: STP36679S
Committee/Subcommittee: B10.02
DOI: 10.1520/STP36679S
CrossRef ASTM International is a member of CrossRef.