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Biaxial Creep Behavior of Nb-Modified Zircaloys

Journal Article · · Nuclear Technology
 [1];  [1];  [2];  [1];  [3]
  1. North Carolina State Univ., Raleigh, NC (United States)
  2. North Carolina State Univ., Raleigh, NC (United States); Univ. of Alabama, Tuscaloosa, AL (United States)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Zr-Nb alloys are used as cladding materials to encapsulate radioactive fuel in nuclear reactors. They possess excellent corrosion resistance at high temperatures making it possible to achieve high fuel burn-up directly increasing the thermal efficiency of the reactor. While they are commonly used in recrystallized (Rx) form in boiling water reactors, there is a need to understand the effect of cold work and stress relief (CWSR) on biaxial creep characteristics of these materials due to their use in pressurized water reactors. In this study, the biaxial creep behaviors of as-received Zr-Nb alloys, HANA and Zirlo, have been investigated at 500 and 400 0C respectively using internally pressurized tubing superimposed with axial load under varied hoop (s?) to axial (sz) stress ratios of 0 to 2 while monitoring both the axial and hoop strains using an LVDT and a laser telemetric extensometer respectively. The crystallographic textures and creep loci of these as-received Zr-Nb alloys have been evaluated to correlate with the previous studies on recrystallized HANA4 and CWSR Zircaloy-4. The creep locus of HANA4 was found to be unaffected by initial state (CWSR or Rx) and showed close correspondence to planar isotropy while the creep locus of CWSR Zirlo exhibited more resistance to axial deformation than diametrical as per CWSR Zircaloy4 reported earlier. These differences are shown to arise from grain shape anisotropy of CWSR Zirlo and Zircaloy4. The simulated creep loci using crystallite orientation distribution functions (CODFs) in conjunction with prism slip models, showed excellent agreement with experimental results.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1631160
Report Number(s):
INL/JOU--19-55019-Rev000
Journal Information:
Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 5 Vol. 206; ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)Copyright Statement
Country of Publication:
United States
Language:
English

References (11)

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Biaxial creep behavior of textured zircaloy tubing journal February 1992
Coble, Orowan Strengthening, and Dislocation Climb Mechanisms in a Nb-Modified Zircaloy Cladding journal July 2015
Biaxial creep of textured zircaloy II: Crystal mean plastic modelling journal April 1985
Effect of grain shape and texture on equi-biaxial creep of stress relieved and recrystallized zircaloy-4 journal November 1994
Creep behavior of niobium-modified zirconium alloys journal March 2008
Dislocation cross-slip controlled creep in Zircaloy-4 at high stresses journal January 2015
Texture development and anisotropic deformation of zircaloys journal May 2006
Out-of-pile and In-pile Perfomance of Advanded Zirconium Alloys (HANA) for High Burn-up Fuel journal September 2006
A theory of the yielding and plastic flow of anisotropic metals journal May 1948
Plastic Instability and Mechanical Anisotropy of Textured Zinc journal January 2002

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