STP939

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

    Published: Jan 1987


      Format Pages Price  
    PDF Version (672K) 37 $25   ADD TO CART
    Complete Source PDF (18M) 37 $121   ADD TO CART


    Abstract

    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.

    Keywords:

    zirconium, zirconium alloys, recrystallized, cold-worked, neutron irradiation, irradiation growth, fluence, temperature, texture, microstructure, dislocation density, solutes, residual stresses, thermal stability, volume change


    Author Information:

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

    Tucker, RP
    General Electric Company, Pleasanton, CA

    Adamson, RB
    General Electric Company, Pleasanton, CA


    Paper ID: STP28108S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP28108S


    CrossRef ASTM International is a member of CrossRef.