A regression model for zircaloy cladding in-reactor creepdown: Database, development, and assessment

• Published in: Nuclear engineering and design Vol. 101; no. 3; pp. 233 - 247
• Main Authors: Shah, V.N., Tolli, J.E., Lanning, D.
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01.05.1987; Elsevier
• Subjects: Applied sciences; Condensed matter: structure, mechanical and thermal properties; Creep; Cross-disciplinary physics: materials science; rheology; Exact sciences and technology; Materials science; Mechanical and acoustical properties of condensed matter; Mechanical properties and methods of testing. Rheology. Fracture mechanics. Tribology; Metals, semimetals and alloys; Metals. Metallurgy; Physics; Specific materials; Boiling water reactor; Creep; Transition metal Alloys; Irradiation; Neutrons; Data table; Neutron irradiation; Models; Regression analysis; Creep deformation; Pressurized water reactor; Strain rate
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/0029-5493(87)90052-5

This paper presents a cladding deformation model developed to analyze cladding creepdown during steady state operation in a pressurized water reactor (PWR) and a boiling water reactor (BWR). This model accounts for variation in the zircaloy cladding heat treatments - cold worked and stress relieved material typically used in a PWR and fully recrystallized material typically used in a BWR. This model calculates cladding creepdown as a function of hoop stress, fast neutron flux, exposure time, and temperature. This paper also presents a comparison between cladding creep calculations by the creepdown model and corresponding test results from the KWU/CE program, ORNL HOBBIE experiments, and EPRI/Westinghouse Engineering cooperative project. The comparisons show that the creepdown model calculates cladding creep strains reasonably well.