Analysis of irradiation growth in zirconium-base alloy

• Published in: Journal of nuclear materials Vol. 140; no. 2; pp. 131 - 139
• Main Author: Fuse, Motomasa
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01.09.1986; Elsevier
• Subjects: Condensed matter: electronic structure, electrical, magnetic, and optical properties; Condensed matter: structure, mechanical and thermal properties; Cross-disciplinary physics: materials science; rheology; Exact sciences and technology; Materials science; Metals, semimetals and alloys; Optical properties and condensed-matter spectroscopy and other interactions of matter with particles and radiation; Other interactions of matter with particles and radiation; Physical radiation effects, radiation damage; Physics; Specific materials; Structure of solids and liquids; crystallography; Frenkel defect; Neutron flux; Grain growth; Computer simulation; Vacancy; Point defect; Temperature effect; Zirconium alloy; Foreign atom; Dislocation climb; Trapping; Stress relaxation; Irradiation; Interstitial; Mathematical model; Residual stress; Radiation damage
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/0022-3115(86)90240-0

Irradiation induced growth phenomena in zirconium-base alloy have been investigated on the basis of the numerical results obtained by dynamical-method computer simulations. Point defect trapping by solute atoms causes transient growth strain which is recoverable during temperature cycling. The growth strain change of cold-worked Zircaloy-2 irradiated at 553 K can be explained by a dislocation climb and a net inflow of vacancies into grain boundaries. The effects of various parameters such as grain size are also discussed.