Thermal stress relieving of dilute uranium alloys [electronic resource].
- Albuquerque, N.M. : Sandia National Laboratories, 1980. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy
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- Pages: 16 : digital, PDF file
- Additional Creators:
- Sandia National Laboratories and United States. Department of Energy. Office of Scientific and Technical Information
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- Free-to-read Unrestricted online access
- The kinetics of thermal stress relieving of uranium - 2.3 wt. % niobium, uranium - 2.0 wt. % molybdenum, and uranium - 0.75 wt. % titanium are reported and discussed. Two temperature regimes of stress relieving are observed. In the low temperature regime (T < 300/sup 0/C) the process appears to be controlled by an athermal microplasticity mechanism which can be completely suppressed by prior age hardening. In the high temperature regime (300/sup 0/C < T < 550/sup 0/C) the process appears to be controlled by a classical diffusional creep mechanism which is strongly dependent on temperature and time. Stress relieving is accelerated in cases where it occurs simultaneously with age hardening. The potential danger of residual stress induced stress corrosion cracking of uranium alloys is discussed. It is shown that the residual stress relief which accompanies age hardening of uranium - 0.75% titanium more than compensates for the reduction in K/sub ISCC/ caused by aging. As a result, age hardening actually decreases the susceptibility of this alloy to residual stress induced stress corrosion cracking.
- Published through SciTech Connect., 01/01/1980., "sand-80-1441c", " conf-801061-5", Conference on high density penetration materials, Charlottesville, VA, USA, 28 Oct 1980., and Eckelmeyer, K.H.
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