Randy K Nanstad

Randy K Nanstad

Distinguished Research Staff

Bio

Dr. Randy K. Nanstad joined the former Metals & Ceramics Division in 1974, following awarding of a M.S. Degree in Nuclear Engineering and a PhD in Metallurgical Engineering from the University of Wisconsin, Madison. He served as the Fracture Mechanics Group Leader from 1980-2000 and Nuclear Materials Science and Technology Group Leader from 2006-2013.  His research has focused primarily on experimental investigation of fracture behavior and radiation effects in materials, including irradiation-induced microstructural evolution and embrittlement in reactor pressure vessel steels and other structural materials, and the influence of various environmental factors on fracture toughness and mechanical properties. He is a Fellow of the American Nuclear Society and of ASM International, has served as a consultant and member of various expert panels for the International Atomic Energy Agency and other international organizations, and was designated the ORNL Distinguished Engineer for 2013.

Research Interests:

Experimental investigation of fracture behavior and radiation effects in materials, including: irradiation-induced microstructural evolution and embrittlement in reactor pressure vessel steels and other structural materials in nuclear reactor systems; influence of various environmental factors on fracture toughness and mechanical properties of structural materials.

Education:

  • PhD, Metallurgical Engineering, University of Wisconsin, Madison, 1974
  • MS, Nuclear Engineering, University of Wisconsin, Madison, 1971
  • BS, Engineering, U.S. Military Academy, West Point, 1964

Societies:

  • ASM International
  • American Society for Testing and Materials (ASTM)
  • The Metallurgical Society (TMS)
  • American Nuclear Society (ANS)

Professional Activities:

  • Officer, International Group on Radiation Damage Mechanisms (IGRDM) (1989 - present).
  • Member, Subcommittee on Materials, ASME Boiler and Pressure Vessel Code; formerly Chairman, Subgroup on Toughness.
  • Member, American Society for Testing and Materials Committee E-8 on Fracture and Fatigue Testing of Materials.
  • Member, American Society for Testing and Materials Committee E-10 on Nuclear Technology and Applications.
  • International Atomic Energy Agency (IAEA) activities: Chairman, CRP-6 on "Nickel Mechanisms Effects on RPV Steels."
  • Member and Task Leader, CRP-8 on “Master curve Approach to Monitor the Fracture Toughness of Reactor Pressure Vessels (RPV) in Nuclear Power Plants.”
  • Member, CRP-5 on "Surveillance Programs Results Application to RPV Integrity Assessment."
  • Editor and author of two chapters for IAEA Book on "Assessment of Irradiation embrittlement effects in reactor pressure vessel steels”, Nuclear Energy Series, No. NP-T-311 (2006).
  • Author of chapter for IAEA TRS-429 on "IAEA Guidelines on Master Curve Application to Reactor Pressure Vessel Integrity Assessment," 2005.
  • Consultant to IAEA for (1) Evaluation of Mochovce Nuclear Power Plant, and (2) develop strategic plan on NPP management with European Commission.
  • Member, U.S./Russia Joint Coordinating Committee on Civilian Nuclear Reactor Safety (JCCCNRS) Working Group 3 on Radiation Embrittlement and Annealing of Reactor Vessel (1989-1998).
  • General Chairman and Editor of Proceedings, 18th ASTM International Symposium on Effects of Radiation on Materials (1996).
  • Co-Chairman and Editor of Proceedings, 17th ASTM International Symposium on Effects of Radiation on Materials (1994).
  • Co-Chairman and Editor of Proceedings, 16th ASTM International Symposium on Effects of Radiation on Materials (1992).
  • Consultant to Kernkraftwerk Obrigheim (KWO) GmbH on evaluation of the KWO Reactor Pressure Vessel, Obrigheim am Neckar, Germany (1995).
  • Consultant to Preussen Elektra Aktiengesellschaft, on evaluation of the Kernkraftwerk Stade (KKS) Reactor Pressure Vessel, Hannover, Germany (1998).

Scope of Research:

  • Coordinator for ORNL High-Flux Isotope Reactor Surveillance Program.
  • Experimental fracture mechanics with emphasis on elastic-plastic behavior to provide techniques for characterizing material parameters critical to the fracture process.
  • Fracture studies of low-alloy pressure vessel steels to provide engineering data for structural integrity assessments of nuclear reactor vessel, coal conversion pressure vessels, etc., including statistical evaluation.
  • Metallurgical studies of nuclear reactor vessel steels to simulate irradiated properties for performance of large fracture mechanics experiments.
  • Irradiation studies of low-alloy steels, stainless steels and high nickel alloys to determine effects of neutron irradiation on mechanical properties and fracture toughness of light-water nuclear reactors.
  • Fracture toughness studies of graphite materials for nuclear reactor and space applications and of nodular cast irons with emphasis on microstructural interactions.
  • Irradiation studies of advanced high temperature structural materials for Generation IV reactors.
  • Materials studies including fracture properties, radiation effects, and characterization for evaluation of High-Flux Isotope Reactor pressure vessel.

Awards

  • Distinguished Engineer, Oak Ridge National Laboratory Awards Night 2013, for sustained and major contributions to the board area of nuclear materials technology, impact in the field of fracture mechanics of light water reactor pressure vessels, and a key role in preserviing HFIR as a national scientific resource (2013).
  • Fellow, American Nuclear Society (2011).
  • Special Award, American Nuclear Society (ANS (2010).
  • Peter D. Hedgecock Award, American Society for Testing and Materials International Committee E10 on Nuclear Technology and Application (2010).
  • Award of Appreciation, American Society for Testing and Materials Committee E10 (1997).
  • Best Paper Award, American Nuclear Society, 1994.
  • Award of Appreciation, American Society for Testing and Materials Committee E10 (1993).
  • Fellow, ASM International (1992).
  • Award of Appreciation, American Society of Mechanical Engineers (1990).
  • Martin Marietta Energy Systems Publication Award (1989).
  • Martin Marietta Energy Systems Technical Achievement Award (1988).
  • W. H. Hobart Memorial Medal, American Welding Society (1985).
  • Best Paper Award, Ductile Iron Division, American Foundrymen's Society (1975).

Publications

Selected Publications:

  1. R. K. Nanstad, et. al., “Evaluating the fracture toughness of reactor pressure vessel (RPV) materials subject to embrittlement,” Chapter 10 in Irradiation Embrittlement of Reactor Pressure Vessels (RPV) in Nuclear Power Plants, Naoki Soneda, Ed., Woodhead Publishing, September 2014.
  2. W. L. Server and R. K.Nanstad, “Reactor pressure vessel (RPV) design and fabrication: the case of the USA,” Chapter 1 in Irradiation Embrittlement of Reactor Pressure Vessels (RPV) in Nuclear Power Plants, Naoki Soneda, Ed., Woodhead Publishing, September 2014.
  3. W. L. Server and R. K. Nanstad, “Integrity and embrittlement management of reactor pressure vessels (RPVs) in light-water reactors,” Chapter 6 in Irradiation Embrittlement of Reactor Pressure Vessels (RPV) in Nuclear Power Plants, Naoki Soneda, Ed., Woodhead Publishing, September 2014.
  4. L. Tan, R. K. Nanstad, et. al., Effect of thermal aging on precipitation kinetics of gamma prime in alloy 617, Journal of Phase Equilibria and Diffusion, July 2014.
  5. X. Chen, R. K. Nanstad, and M. A. Sokolov, “Determining Ductile Fracture Toughness in Metals, Advanced Materials and Processes,” April 2014.
  6. A. Kryukov, R. K. Nanstad, and M. Brumovsky, “Common comparison of the irradiation embrittlement of WWER/PWR reactor pressure vessel steels,” Nuclear Engineering and Design, 273 (2014) 175–180.
  7. L. Tan, Y. Yang, R. K. Nanstad and J. T. Busby, “Effect of Thermal Aging on Coarsening Kinetics of g# in Alloy 617,” J. Phase Equilib. Diffus. (2014) 35:524-529.
  8. X. Chen and R. K. Nanstad, “Thermal Aging Effects on Fracture Toughness and Microstructure of Grade 91 Steel, March 2014,” ORNL Report.
  9. M. A. Sokolov, R. K. Nanstad, and M. K. Miller, “Comprehensive and Comparative Analysis of Atom Probe, Small-Angle Neutron Scattering, and Other Microstructural Experiments on Available High Fluence Reactor Pressure Vessel Steels,” ORNL/TM-2014/241, June 2014.
  10. R. K. Nanstad, et. al., “Post-irradiation Examination Plan for ORNL and University of California Santa Barbara Assessment of UCSB ATR-2 Irradiation Experiment,” ORNL/TM-2013/598, January 2014.
  11. R. K. Nanstad, G. R. Odette and T. Yamamoto, “Progress report on disassembly of ATR-2 capsule and Revision to post-irradiation examination plan,” ORNL/TM-2014/525, September 2014.
  12. X. Chen, R. K. Nanstad, “Fracture Toughness of Grade 91 Welds and Fracture Surface Reconstruction Study of Thermally Aged Grade 91 Steel,” ORNL Report, published 24 September 2014.
  13. X.Chen, R. K. Nanstad, and M. A. Sokolov, “Fracture Toughness Testing of Unaged Alloy 617 Welds,” Report to INL, 08-2014.
  14. Eason, E. D., G. R. Odette, R. K. Nanstad, and T. Yamamoto, “A physically-based correlation of irradiation-induced transition temperature shifts for RPV steels,” Journal of Nuclear Materials, Volume 433, Issues 1–3, February 2013, Pages 240-254.  
  15. M.K. Miller, K.A. Powers, R.K. Nanstad, P. Efsing, “Atom probe tomography characterizations of high nickel, low copper surveillance RPV welds irradiated to high fluences,” Journal of Nuclear Materials, Volume 437, Issues 1–3, June 2013, Pages 107-115.
  16. Nanstad, Randy K., Xiang Chen, Mikhail A. Sokolov, Barry H. Rabin, and Ying Yang, “Master Curve and J-R Fracture Toughness of SA508/SA533-B-1 Weld and HAZ,” Proceedings of the ASME Pressure Vessels and Piping Conference PVP 2013, American Society of Mech. Engrs, July 2013.
  17. Chen, Xiang, Randy K. Nanstad, and Mikhail A. Sokolov, “Application of Direct Current Potential Drop for Fracture Toughness Measurement,” Transactions SMiRT-22, San Francisco, CA August 2013.
  18. R. K. Nanstad and G. R. Odette, “Reactor Pressure Vessel Task  of Light Water Reactor Sustainability Program: Milestone M2LW-13OR0402013, Progress Report on Status of Advanced Test Reactor-2 Reactor Pressure Vessel Materials Irradiation Project,” ORNL/LTR-2013/129, March 2013.
  19. M. A. Sokolov, K. Littrell, and R. K. Nanstad, “Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone M3LW-13OR0402012, Report on Small-Angle Neutron Scattering Experiments of Irradiated RPV Materials,” ORNL/TM-2012/630, December 2012.
  20. M. A. Sokolov and R. K. Nanstad, “Critical Assessment of Attenuation of Embrittlement and Material Variability Issues for Reactor Pressure Vessels,” ORNL/TM-2012/471, October 2012.
  21. R. K. Nanstad, M. K. Miller, and W. D. Lewis, “Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Level 2 Milestone (M2LW-12OR0402015) – Results of Examinations of Surveillance Specimens from Commercial Reactors,” ORNL/TM-2012/447, November 2012.
  22. Cyrus Smith, Randy Nanstad, Dwight Clayton, Kathryn Matlack, Pradeep Ramuhalli, and Glenn Light, “Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program,” ORNL/TM-2012/380, September 2012, Distributed March 2013.
  23. Chen, Xiang and Randy K. Nanstad, “Effects of Thermal Aging on Microstructural Evolution and Relation to Fracture in Grade 91 Steel,” ORNL/TM-2013/xxx, September 2013.
  24. R. K. Nanstad and W. L. Server, “Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Level 3 Milestone (M3W-13OR0402017)-Status Report on Assessment of Plan for the Palisades Reactor High Fluence Capsule,” ORNL/LTR-2013/405, September 2013.
  25. R. K. Nanstad, M. A. Sokolov, M. K. Miller, G.T. Williams, and K. C. Littrell, “Microstructural Examinations of Reactor Pressure Vessel surveillance and Test Reactor Irradiated Materials,” ORNL/TM-2013/462, September 2013.
  26. Nanstad, Randy K., Mikhail A. Sokolov, Igor Remec, and Xiang Chen, “Reactor Pressure Vessel Neutron Embrittlement Assessment of Nuclear Power Plant Beznau-1,” ORNL Report-2013/XXX, Submitted to Eidg. Nuklearsicherheitsinspektorat (ENSI), The Switzerland Nuclear Regulatory Authority, September 2013.
  27. Nanstad, Randy  K., Mikhail A. Sokolov and Xiang Chen. "Fracture Toughness of 9Cr-1MoV and Thermally Aged Alloy 617for Advanced Reactor Application," TMS Letters 351, (2012).
  28. Nanstad, Randy K. and G. Robert Odette, “Development of a Robust Predictive Embrittlement Model for Reactor Pressure Vessel Lifetime Extension,” Light Water Reactor Sustainability Newsletter, Issue 6, Idaho National Laboratory, December 2011.
  29. Nanstad, Randy  K., et al. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:Level 3 Milestone (M3W-12OR0402014) - Progress Report on Examinations of the Surveillance Specimens from the Ginna and Palisades Reactors. ORNL/LTR-2012/335. Oak Ridge, TN: Oak Ridge National Laboratory (2012).
  30. Nanstad, Randy  K., et al. Letter Report on Metallurgical Examination of the High Fluence RPV Specimens From the Ringhals Nuclear Reactors. ORNL/LTR-2012/113. Oak Ridge, TN: Oak Ridge National Laboratory (2012).
  31. Nanstad, Randy  K. and W. L. Server. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges. ORNL/LTR-2011/351. Oak Ridge, TN: Oak Ridge National Laboratory (2011).
  32. Nanstad, Randy  K. and G. R. Odette. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Assessment of Further Irradiation Experiment Needs. ORNL/LTR-2011/291. Oak Ridge, TN: Oak Ridge National Laboratory (2011).
  33. Nanstad, Randy  K., et al. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Assessment of High Value Surveillance Materials. ORNL/TM-2011/172. Oak Ridge, TN: Oak Ridge National Laboratory (2011).
  34. Nanstad, Randy K., “Final Report for “ORNL BAC (Boric Acid Corrosion) Expert Panel Support,” Report submitted in accordance with the project agreement (EPRI Contract ID EP-P43796/C19016) between UT Battelle, LLC (Oak Ridge National Laboratory) and the Electric Power Research Institute, Inc., 8 June 2012.
  35. Natesan, K., Meimei Li, S. Majumdar, R. K. Nanstad, and T. –L. Sham, “Resolution of Qualification Issues for Existing Structural Materials,” ANL-AFCI-285, Argonne National Laboratory, Sept. 2009 (Published and Distributed Sept. 2012).
  36. R. K. Nanstad, B. R. Bass, J. G. Merkle,  C. E. Pugh, T. M. Rosseel, and M. A. Sokolov, “ Heavy-section Steel Technology and Irradiation Programs-Retrospective and Prospective Views,” J. Pressure Vessel Technology, December 2010, Vol. 132/064001-1.
  37. L. Tan, L. Rakotojaona, T. R. Allen, R. K. Nanstad, and J. T. Busby, “Microstructure Optimization of Incoloy Alloy 800H,” Materials Science and Engineering A, March 2011.
  38. R. K. Nanstad and G. R. Odette, “Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment,” ORNL/LTR-2011/413, January 2011.
  39. R. K. Nanstad and M. A. Sokolov, “Fracture Toughness of Grade 91 Steel in the Unaged Condition, ORNL/TM-2011/146, Oak Ridge National Laboratory, Oak Ridge, Tennessee, May 2011.
  40. R. K. Nanstad, “Progress Report on Thermal Aging Effects on Fracture Toughness of Grade 91 Steel,” ORNL/TM-2011/171, Oak Ridge National Laboratory, Oak Ridge, Tennessee, June 2011.
  41. R. K. Nanstad, M. A. Sokolov, and G. R. Odette, “Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Assessment of High Value Surveillance Materials,” ORNL/LTR-2011/172, Oak Ridge National Laboratory, Oak Ridge, Tennessee, June 2011.
  42. R. K. Nanstad and G. R. Odette, “Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Assessment of Further Irradiation Experiment Needs,” ORNL/LTR-2011/291, August 2011.
  43. R. K. Nanstad and W. L. Server, “Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges,” ORNL/LTR-2011/351, September 2011.
  44. R. D. Cheverton, R. K. Nanstad, E. D. Blakeman, and H. A. Kmieciak, “HFIR PRESSURE VESSEL AND STRUCTURAL COMPONENTS MATERIALS SURVEILLANCE PROGRAM – SUPPLEMENT 3,” ORNL/TM-1372/S3, Oak Ridge National Laboratory, Oak Ridge, Tennessee, 2010.
  45. R. D. Cheverton, R. K. Nanstad, E. D. Blakeman, T. L. Dickson, H. A. Kmieciak, and I. Remec,  “Impact of 2008/2009 Dosimetry and Surveillance Data on the HFIR Vessel Radiation Embrittlement Trend Curve, Hydrostatic Proof Test Conditions, Pressure/Temperature Limits, and Life Extension,”  ORNL/RRD/QLR/10-1, Oak Ridge National Laboratory, Oak Ridge, Tennessee (2010).
  46. R. K. Nanstad and G. Robert Odette, “Reactor Pressure Vessel Issues for the Light-Water reactor Sustainability Program”, pgs. 1667-1676 in Proceedings of the Fourteenth International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, Am. Nuclear Society, LaGrange, IL (2010).
  47. W. L. Server and R. K. Nanstad, “International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels ,” J. of ASTM Intern., Vol. 6 (7) 2009.
  48. Randy K. Nanstad, G. Robert Odette, and Mikhail A. Sokolov, “Ensuring The Performance Of Nuclear Reactor Pressure Vessels For Long-Time Service,” Paper PVP2010-25832, July 2010.
  49. Rowcliffe, A. F., L. K. Mansur, D. T. Hoelzer, and R. K. Nanstad, “Perspectives on Radiation Effects in Nickel-Base Alloys for Applications in Advanced Reactors,” Journal of Nuclear Materials 392 (2009) 341–352.
  50. Allen, T., H. Burlet, R. K. Nanstad, M. Samaras, and S. Ukai, “Advanced Structural Materials and Cladding,” MRS Bulletin, Vol. 34, January 2009.
  51. M. K. Miller, A. A. Chernobaeva, Y. I Shtrombakh, K. F. Russell, R. K. Nanstad, D. Y. Erak and O. O. Zabusov,  “Evolution of VVER-1000 RPV materials nano-structure under irradiation and post irradiation annealing,” J. Nucl. Mater. 385 (2009) 615-622, doi:10.1016/j.jnucmat.2009.01.299.  
  52. Odette, G. R. and R. K. Nanstad, “Predictive Reactor Pressure Vessel Steel Irradiation Embrittlement Models: Issues and Opportunities,” J. Metals, 61, 7, July 2009.
  53. Nanstad, R. K., et. al., “IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Final Results of the Experimental Exercise to Support Constraint Effects,” Proceedings of ASME 2009 Pressure Vessels and Piping Conference (PVP2009), PVO2009-78022, July, 2009, Prague, Czech Republic.
  54. 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.
  55. 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.
  56. 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).
  57. 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.
  58. 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).
  59. 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).
  60. 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).
  61. D. J. Downing, V. V. Federov, and R. K. Nanstad, “Heteroscedasticity Generated by Errors in Predictors,” ORNL/TM-13140, November 1995.
  62. 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).
  63. R. K. Nanstad, “A Review of Concrete Properties for Prestressed Concrete Pressure Vessels,” ORNL/TM-5497, October 1976.
  64. 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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