An Overview of Microstructural and Experimental Factors That Affect the Irradiation Growth Behavior of Zirconium Alloys

V Fidleris; RP Tucker; RB Adamson

doi:10.1520/STP28108S

SYMPOSIA PAPER Published: 01 January 1987

STP28108S

An Overview of Microstructural and Experimental Factors That Affect the Irradiation Growth Behavior of Zirconium Alloys

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This paper presents an overview of factors affecting irradiation growth of zirconium alloys. Recent data obtained from irradiation programs in EBR-II, ATR, and NRU reactors are used to illustrate the effects of various microstructural and experimental factors on the growth of Zircaloy, zirconium, and zirconium-niobium alloys irradiated to fluences up to 2 × 10²⁶ nm⁻² (E > 1 MeV) over the temperature range 330 to 720 K. Open literature results are also used to confirm or illustrate various effects. Important factors are texture, grain boundary parameters, residual stresses, original dislocation density, microstructure evolution, temperature during irradiation, solute effects, and fluence.

Author Information

Fidleris, V

Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada

Tucker, RP

General Electric Company, Pleasanton, CA

Adamson, RB

General Electric Company, Pleasanton, CA

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Details

Developed by Committee: B10

Pages: 49–85

DOI: 10.1520/STP28108S

ISBN-EB: 978-0-8031-5004-1

ISBN-13: 978-0-8031-0935-3

An Overview of Microstructural and Experimental Factors That Affect the Irradiation Growth Behavior of Zirconium Alloys

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