Performance of V–Cr–Ti alloys in a hydrogen environment
Source abstract
Abstract
A systematic study is underway at Argonne National Laboratory to evaluate the mechanical properties of several V-Cr-Ti alloys after exposure to environments containing hydrogen at various partial pressures. The goal is to correlate the chemistry of the exposure environment with hydrogen uptake by the samples and with the resulting influence on microstructures and tensile properties of the alloys. Other variables examined are specimen cooling rate and synergistic effects, if any, of oxygen and hydrogen on tensile behavior of the alloys. Experiments were conducted to evaluate the effect of pH{sub 2} in the range of 3 x 10{sup {minus}6} and 1 torr on tensile properties of two V-Cr-Ti alloys. Up to pH{sub 2} of 0.05 torr, negligible effect of H was observed on either maximum engineering stress or uniform and total elongation. However, uniform and total elongation decreased substantially when the alloys were exposed at 500 C to 1.0 torr of H{sub 2} pressure. Preliminary data from sequential exposures of the materials to low-pO{sub 2} and several low-pH{sub 2} environments did not reveal adverse effects on the maximum engineering stress or on uniform and total elongation when the alloy contained {approx} 2,000 wppm O and 16 wppm H. Furthermore, tests in H{sub 2}-exposed specimens, initially annealed at various temperatures, showed that grain-size variation by a factor of {approx} 2 had little or no effect on tensile properties. Also, specimen cooling rate had a small effect, if any, on the tensile properties of the alloy.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Corrosion Behavior and Inhibition · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (7)
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1. K. Natesan, W.K. Soppet, in: Fusion Reactor Materials Progress Report for the Period Ending 31 December 1997, Argonne National Laboratory, DOE/ER-0313/23, March 1998, p. 127
2. K. Natesan, W.K. Soppet, in: Fusion Reactor Materials Progress Report for the Period Ending 30 June 1998, Argonne National Laboratory, DOE/ER-0313/24, September 1998, p. 68
3. K. Natesan, W.K. Soppet, in: Fusion Reactor Materials Progress Report for the Period Ending 31 December 1998, Argonne National Laboratory, DOE/ER-0313/25, April 1999, p. 21
4. J.R. DiStefano, B.A. Pint, J.H. DeVan, H.D. Röhrig, L.D. Chitwood, these Proceedings, p. 841
5. K. Natesan, M. Uz, in: Fusion Reactor Materials Progress Report for the Period Ending 30 June 1996, Argonne National Laboratory, DOE/ER-0313/20, October 1996, p. 105
6. Uz · J. Nucl. Mater. · 1997 · 245 · 19110.1016/S0022-3115(97)00008-1 ↗
7. K. Natesan, W.K. Soppet, Performance of V–Cr–Ti alloys in a hydrogen environment, in: Proc. 4th IEA Workshop on Vanadium Alloys for Fusion Applications, Apr. 1999, Argonne National Laboratory, Argonne, IL, p. 423