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Evaluation of the Possible Susceptibility of Titanium Grade 7 to Hydrogen Embrittlement in a Geologic Repository Environment

Published online by Cambridge University Press:  21 March 2011

Charles A. Greene ,
Alvin J. Henry ,
C. Sean Brossia  and
Tae M. Ahn
Charles A. Greene
Affiliation:
US Nuclear Regulatory Commission, Mail Stop T-7C6, Washington, DC 20555-0001, USA
Alvin J. Henry
Affiliation:
Previously at US Nuclear Regulatory Commission, MPR Associates, 320 King Street, Alexandria, VA 22314, USA
C. Sean Brossia
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238, USA
Tae M. Ahn
Affiliation:
US Nuclear Regulatory Commission, Mail Stop T-7C6, Washington, DC 20555-0001, USA
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Abstract

Ti grade 7 has been selected by the U.S. DOE as the current material of choice for the drip shield in the proposed high level waste (HLW) repository design. Due to the addition of Pd, Ti grade 7 exhibits enhanced resistance to hydrogen embrittlement (HE), yet there is relatively little data on HE of this material. Calculations of hydrogen absorption/recombination, solubility, and free energy of hydride formation in Ti and Pd are presented to qualitatively evaluate Keff, the stress intensity factor for crack propagation induced by hydride formation, of Ti grade 7 in relation to other Ti alloys without Pd. Calculations were performed that show concentration of hydrogen in Ti grade 7 may exceed the critical hydrogen concentration, Hc, where the material becomes embrittled, when accelerated passive dissolution of Ti grade 7 in concentrated Cl- and Cl-+F- solutions as the source of hydrogen is considered.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 515
Copyright
Copyright © Materials Research Society 2001

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