Published 1984 | Version v1
Book

Irradiation growth of Zircaloy (LWBR) development program

  • 1. Westinghouse Electric Corp., West Mifflin, PA

Description

Irradiation growth of recrystallized annealed (RXA) Zircaloy is divided into four stages and a model is presented to account for each stage. Stage I is a short time, low-strain transient caused by the accumulation of point defects, small interstitial loops, and vacancy clusters. Stage II is a quasi-steady-state region of relatively low strain rate during which the loops grow and intrinsic dislocations climb. Stage III is a transient during which the strain rate increases due to the production and motion of irradiation-induced dislocation lines. Stage IV is a high-strain-rate, steady-state region during which nonrecoverable strain is caused predominantly by glide of the irradiationinduced dislocations. The proposed model is based on two new mechanisms: (1) direct production of an interstitial dislocation loop accompanied by a vacancy cluster in the primary damage event, and (2) production of dislocations due to the activation of Frank-Read sources by internal stresses caused by interaction of the loops with themselves and with intrinsic (cold work) dislocations. Nonconservative, recoverable strain is due to climb of all dislocations, whereas conservative, nonrecoverable strain is caused by glide of irradiation-induced and intrinsic dislocations under the action of the internal stress. The conservative strain follows a (1-3f) texture dependence

Additional details

Publishing Information

Publisher
American Society for Testing and Materials.
Imprint Place
Philadelphia, PA (USA)
Imprint Title
Zirconium in the nuclear industry
Journal Page Range
p. 452-480.

Conference

Title
6. international conference on zirconium in the nuclear industry.
Dates
28 Jun - 1 Jul 1982.
Place
Vancouver, British Columbia (Canada).