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Randy K. Nanstad, Group Leader
Nuclear Materials Science & Technology Group
Materials Science & Technology Division
Oak Ridge National Laboratory
P.O. Box 2008
Oak Ridge, TN 37831-6138
Phone: (865) 574-4471
Fax: (865) 241-3650
email: nanstadrk@ornl.gov

Selected Publications:

  1. R. K. Nanstad, M.A. Sokolov, and D.E. McCabe, “Applicability of the Fracture Toughness Master Curve to Irradiated Highly Embrittled Steel and Intergranular Fracture,” J. ASTM Int., Vol. 5, No. 3, Paper ID JAI101346, March, 2008.
  2. R. K. Nanstad, M. Niffenegger, R. D. Kalkhof, M. K. Miller, M. A. Sokolov, and Ph. Tipping, ”Fracture Toughness, Thermo-Electric Power, and Atom Probe Investigations of JRQ Steel in I, IA, IAR, and IARA Conditions,” J. ASTM Int., Vol. 2, No. 9, Paper ID JAI12888, October 2005.
  3. R. K. Nanstad, D. E. McCabe, M. A. Sokolov, C. A. English, and S. R. Ortner, Comparison of Effects of Thermal Aging, Irradiation, and Thermal Annealing on Propensity for Temper Embrittlement on an RPV Submerged-Arc Weld HAZ, ORNL/NRC/LTR-01/07 (2002).
  4. M. A. Sokolov and R. K. Nanstad, "Comparison of Irradiation-Induced Shifts of Fracture Toughness and Calculative Procedures of Regulatory Guides," pp. 557-558 in Transactions of the American Nuclear Society, Vol. 88, June 2003.
  5. R. K. Nanstad, D. E. McCabe, M. A. Sokolov, C. A. English, and S. R. Ortner, "Investigation of Temper Embrittlement in Reactor Pressure Vessel Steels Following Thermal Aging, Irradiation, and Thermal Annealing," pp. 356-382 in Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405, S. T. Rosinski, M. L. Grossbeck, T. R. Allen, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2001.
  6. R. K. Nanstad, R. E. Stoller, M. K. Miller, and M. A. Sokolov, "In-Service Degradation and Life Extension of Nuclear Reactor Vessels: Combining Experiments and Modelling," pp. 565-582 in Ageing Studies and Lifetime Extension of Materials, L. G. Mallinson, Ed., Kluwer Academic/Plenun Publishers, New York, 2001.
  7. R. K. Nanstad, D. E. McCabe, and R. L. Swain, "Evaluation of Variability in Material Properties and Chemical Composition for Midland Reactor Weld WF-70," pp. 125-156 in Effects of Radiation on Materials: 18th International Symposium, ASTM STP 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, Pa., 1999.
  8. D. J. Downing, V. V. Federov, and R. K. Nanstad, “Heteroscedasticity Generated by Errors in Predictors,” ORNL/TM-13140, November 1995.
  9. R. K. Nanstad, K. Farrell, D. N. Braski, and W. R. Corwin, "Accelerated Neutron Embrittlement of Ferritic Steels at Low Fluence: Flux and Spectrum Effects," J. Nucl. Mater. 158, 1-6 (1988).
  10. R. K. Nanstad, “A Review of Concrete Properties for Prestressed Concrete Pressure Vessels,” ORNL/TM-5497, October 1976.
  11. R. K. Nanstad, F. J. Worzala, C. R. Loper, Jr., "Static and Dynamic Toughness of Ductile Cast Iron," pp. 245-56 in Trans. Am Foundrymen Soc. (1975 AFS Casting Congress, May 5-9, 1975), St. Louis, Missouri, 1975.




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