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Title: Hydrogen transport and embrittlement for palladium coated vanadium-chromium-titanium alloys

Abstract

Vanadium based alloys have been identified as a leading candidate material for fusion first-wall blanket structure application because they exhibit favorable safety and environmental characteristics, good fabricability, potential for high performance and long-time operation lifetime in a fusion environment. As part of a study of the thermodynamics, kinetics and embrittlement properties of hydrogen in vanadium based alloys, experiments were conducted to determine the rate of hydrogen transport through the vanadium reference alloys, V-7.5Cr-15Ti and V-4Cr-4Ti, and to determine these alloys` hydrogen embrittlement, they were exposed to hydrogen pressures of 3 and 300 kPa (0.03--3 atm) at temperatures between 380 and 475 C. To facilitate hydrogen entry and egress, tubes of these alloys were coated with palladium on the inside and outside faces. Observed permeabilities were 0.015 to 0.065 {micro}moles/(m{sup 2}sPa{sup 0.5}) for the V-7.5Cr-15Ti alloy and 0.02 to 0.05 {micro}moles/m{sup 2}sPa{sup 0.5} for the V-4Cr-4Ti alloy depending on the quality of the coat and the operating temperature. At 1.7 atm hydrogen, V-7.5Cr-15Ti embrittled at temperatures below 380 C while V-4Cr-4Ti embrittled around 330 C.

Authors:
;  [1]; ;  [2]
+ Show Author Affiliations
  1. REB Research and Consulting, Ferndale, MI (United States)
  2. Argonne National Lab., IL (United States). Fusion Power Program
Publication Date:
Research Org.:
Argonne National Lab., IL (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
195724
Report Number(s):
ANL/ET/CP-87987; CONF-950961-6
ON: DE96005528; TRN: AHC29605%%100
DOE Contract Number:
W-31109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Conference: ICFRM-7: international conference on fusion reactor materials, Obninsk (Russian Federation), 25-29 Sep 1995; Other Information: PBD: Sep 1995
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 70 PLASMA PHYSICS AND FUSION; FIRST WALL; THERMONUCLEAR REACTOR MATERIALS; BREEDING BLANKETS; VANADIUM BASE ALLOYS; PERMEABILITY; HYDROGEN EMBRITTLEMENT; CHROMIUM ALLOYS; TITANIUM ALLOYS; HYDROGEN; DIFFUSION; EXPERIMENTAL DATA

Citation Formats

Buxbaum, R.E., Subramanian, R., Park, J.H., and Smith, D.L. Hydrogen transport and embrittlement for palladium coated vanadium-chromium-titanium alloys. United States: N. p., 1995. Web. doi:10.2172/195724.
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Buxbaum, R.E., Subramanian, R., Park, J.H., & Smith, D.L. Hydrogen transport and embrittlement for palladium coated vanadium-chromium-titanium alloys. United States. doi:10.2172/195724.
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Buxbaum, R.E., Subramanian, R., Park, J.H., and Smith, D.L. Fri . "Hydrogen transport and embrittlement for palladium coated vanadium-chromium-titanium alloys". United States. doi:10.2172/195724. https://www.osti.gov/servlets/purl/195724.
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@article{osti_195724,
title = {Hydrogen transport and embrittlement for palladium coated vanadium-chromium-titanium alloys},
author = {Buxbaum, R.E. and Subramanian, R. and Park, J.H. and Smith, D.L.},
abstractNote = {Vanadium based alloys have been identified as a leading candidate material for fusion first-wall blanket structure application because they exhibit favorable safety and environmental characteristics, good fabricability, potential for high performance and long-time operation lifetime in a fusion environment. As part of a study of the thermodynamics, kinetics and embrittlement properties of hydrogen in vanadium based alloys, experiments were conducted to determine the rate of hydrogen transport through the vanadium reference alloys, V-7.5Cr-15Ti and V-4Cr-4Ti, and to determine these alloys` hydrogen embrittlement, they were exposed to hydrogen pressures of 3 and 300 kPa (0.03--3 atm) at temperatures between 380 and 475 C. To facilitate hydrogen entry and egress, tubes of these alloys were coated with palladium on the inside and outside faces. Observed permeabilities were 0.015 to 0.065 {micro}moles/(m{sup 2}sPa{sup 0.5}) for the V-7.5Cr-15Ti alloy and 0.02 to 0.05 {micro}moles/m{sup 2}sPa{sup 0.5} for the V-4Cr-4Ti alloy depending on the quality of the coat and the operating temperature. At 1.7 atm hydrogen, V-7.5Cr-15Ti embrittled at temperatures below 380 C while V-4Cr-4Ti embrittled around 330 C.},
doi = {10.2172/195724},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Sep 01 00:00:00 EDT 1995},
month = {Fri Sep 01 00:00:00 EDT 1995}
}
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Technical Report:
View Technical Report (0.44 MB)
DOI:  10.2172/195724
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    Extensive investigations intended to provide information relating to the mechanism of H embrittlement in titanium-base alloys were carried out. Studies included detailed measurements of thc effects of temperature, strain rate, and H content on embrittlement, examination of all-alpha and all-beta alloys for susceptibility to embrittlement, calculations of probable H solubility in alpha and beta Ti, and several other informative investigations. An embrittlement mechanism is outlined. Alloys previously prepared and examined to determine the effects of alloy content and microstructure on H embrittlement were further studied by means of notched stress-rupture tests. This work resulted in alteration of previously expressed conclusionsmore » regarding alloying and microstructural effects. (auth)« less

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