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

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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 ... continued below

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65 p.

Creation Information

Kammenzind, B.F.; Berquist, B.M.; Bajaj, R.; Kreyns, P.H. & Franklin, D.G. November 1, 1998.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 17 times . More information about this report can be viewed below.

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

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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.

Notes

INIS; OSTI as DE99000480

Source

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

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

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • November 1, 1998

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

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  • May 16, 2016, 4:56 p.m.

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Kammenzind, B.F.; Berquist, B.M.; Bajaj, R.; Kreyns, P.H. & Franklin, D.G. The long range migration of hydrogen through Zircaloy in response to tensile and compressive stress gradients, report, November 1, 1998; West Mifflin, Pennsylvania. (digital.library.unt.edu/ark:/67531/metadc677479/: accessed December 13, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.