The long range migration of hydrogen through Zircaloy in response to tensile and compressive stress gradients Metadata

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  • Main Title The long range migration of hydrogen through Zircaloy in response to tensile and compressive stress gradients


  • Author: Kammenzind, B.F.
    Creator Type: Personal
  • Author: Berquist, B.M.
    Creator Type: Personal
  • Author: Bajaj, R.
    Creator Type: Personal
  • Author: Kreyns, P.H.
    Creator Type: Personal
  • Author: Franklin, D.G.
    Creator Type: Personal


  • Sponsor: United States. Office of the Assistant Secretary for Nuclear Energy.
    Contributor Type: Organization
    Contributor Info: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)


  • Name: Bettis Atomic Power Laboratory
    Place of Publication: West Mifflin, Pennsylvania
    Additional Info: Bettis Atomic Power Lab., West Mifflin, PA (United States)


  • Creation: 1998-11-01


  • English


  • Content Description: Zircaloy-4, which is used widely as a core structural material in pressurized water reactors (PWRs), picks up hydrogen during service. Hydrogen solubility in Zircaloy-4 is low and zirconium hydride phases precipitate after the Zircaloy-4 lattice becomes supersaturated with hydrogen. These hydrides embrittle the Zircaloy-4, degrading its mechanical performance as a structural material. Because hydrogen can move rapidly through the Zircaloy-4 lattice, the potential exists for large concentrations of hydride to accumulate in local regions of a Zircaloy component remote from its point of entry into the component. Much has been reported in the literature regarding the long range migration of hydrogen through Zircaloy under concentration gradients and temperature gradients. Relatively little has been reported, however, regarding the long range migration of hydrogen under stress gradients. This paper presents experimental results regarding the long range migration of hydrogen through Zircaloy in response to both tensile and compressive stress gradients. The importance of this driving force for hydrogen migration relative to concentration and thermal gradients is discussed.
  • Physical Description: 65 p.


  • Keyword: Stresses
  • Keyword: Hydrides
  • STI Subject Categories: 36 Materials Science
  • Keyword: Mathematical Models
  • Keyword: Pwr Type Reactors
  • Keyword: Experimental Data
  • Keyword: Thermal Cycling
  • Keyword: Permeability
  • STI Subject Categories: 21 Nuclear Power Reactors And Associated Plants
  • Keyword: Hydrogen
  • Keyword: Zircaloy 4
  • Keyword: Atom Transport


  • Conference: 12. ASTM international symposium on zirconium in the nuclear industry, Toronto (Canada), 15-18 Jun 1998


  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report


  • Text


  • Other: DE99000480
  • Report No.: WAPD-T--3197
  • Report No.: CONF-9806141--
  • Grant Number: AC11-93PN38195
  • DOI: 10.2172/290949
  • Office of Scientific & Technical Information Report Number: 290949
  • Archival Resource Key: ark:/67531/metadc677479


  • Display Note: INIS; OSTI as DE99000480