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Steven Hayes

Steven Hayes

Nuclear engineering

Dr Steven Hayes is an internationally known researcher in nuclear fuels, especially behavior under irradiation. He earned bachelor’s, master’s and doctoral degrees in Nuclear engineering from Texas A&M University, College Station, Texas, and took most of his grad school electives in physical chemistry and materials science. He has authored 22 journal articles and written 81 papers presented at conferences in many countries.

Dr Hayes is also a Christian, and a ThM student with Tyndale (Ft. Worth, Texas) in Systematic Theology, and says:

“The more serious my Christian faith has become, the deeper my commitment to young-earth creation!”

Technical interests

  • Irradiation performance of nuclear fuels and materials
  • Plutonium and minor actinide utilization in the nuclear fuel cycle
  • Fast reactor technology
  • Numerical modeling and analysis

Education

PhD in Nuclear engineering, Texas A&M University, College Station, Texas (1992)
Dissertation: “Radiative Heat Transfer in Porous Uranium Dioxide”
Advisor: Dr. K. L. Peddicord

MS in Nuclear engineering, Texas A&M University, College Station, Texas (1989)
Thesis: “Material Property Correlations for Uranium Mononitride”
Advisor: Dr. K. L. Peddicord

BS in Nuclear engineering, Texas A&M University, College Station, Texas (1988)

Experience

[Disclaimer: Organizations and titles are listed for identification only and do not imply organizational endorsement.]

Idaho National Laboratory (2005–present)

Manager, Fuel Performance & Design Department, Nuclear Fuels & Materials Division, 2008–present.

Nuclear Engineer, Fuels Performance Department, Nuclear Fuels & Materials Division, 2005–2008

  • Lead GNEP fuel irradiation test program, testing metallic, oxide and nitride fuels for actinide transmutation mission. Current fuel tests on-going in the ATR and Phénix reactors.
  • Lead irradiation testing of U3 Si2 /Al dispersion fuels for the Boosted Fast Flux Loop concept for ATR.

Argonne National Laboratory (1990, 1992–2005)

Section Manager, Fuel Development Section, Nuclear Technology Division, 1997-2005

Group Leader, Fuels & Irradiated Materials Group, Fuels and Engineering Division, 1994–97

Nuclear Engineer, Fuel Performance Section, EBR-II Division, 1990, 1992–94

  • Led development and testing of nitride, oxide, metallic alloy and metal-matrix dispersion fertile fuels/non-fertile targets for actinide transmutation. Design of FUTURIX-FTA transmutation fuels experiment irradiated in Phénix fast reactor (international collaboration between US-DOE, CEA, ITU).
  • Served as member of DOE-Accelerator Transmutation of Waste Roadmapping Analysis; Leader of the Fuels Technology Subgroup of the Target & Blanket Technical Working Group; recommended candidate fuel forms for actinide transmutation and developed R&D Plan.
  • Development and testing of high-density, low-enrichment aluminum clad dispersion fuels for research and test reactors; design and fabrication of dispersion fuel irradiation tests irradiated in the Advanced Test Reactor 1997–2001; led post-irradiation examinations conducted in Alpha–Gamma Hot Cell Facility.
  • Developed fuel behavior models for aluminum clad dispersion fuel plates; models implemented within PLATE–A Computer Code for the Thermo-Mechanical Analysis of Research Reactor Dispersion Fuel Plates.
  • Served as Fuel Characterization Team Leader, U.S./Republic of Kazakhstan Joint Action Team, “BN-350 Nuclear Material Disposition Study,” 1996. Characterized BN-350 spent fuel in wet storage and developed specifications for drying and packaging fuel assemblies for transfer to dry storage.
  • Developed a uranium ignition model; model implemented within SPARC–A Computer Code for the Prediction of Uranium Ignition Conditions.
  • Participated in the development of metallic fast reactor fuels for the Integral Fast Reactor Concept; designed and fabricated fuels experiments for irradiation in the Experimental Breeder Reactor II (EBR-II), including: X521–Weapons Plutonium Disposition Experiment, 1994; X518, X519 and X520–HT9 Duct Qualification Experiments, 1993–1994; X499–128 Xe Isotope Production Experiment, 1992–1994; X431 and X432–Integral Fast Reactor Blanket Experiments, 1992–1994; X430–Advanced HT9 Driver Fuel Experiment, 1992–1994; conducted postirradiation examinations of these experiments in Hot Fuels Examination Facility and Alpha–Gamma Hot Cell Facility; developed mechanistic models for metallic fuel behavior to be incorporated into LIFE-METAL computer code.
  • Development of SAFE–A Computer Code for the Steady-State and Transient Thermal Analysis of LMR Fuel Elements.

University of Idaho (1999–present)

Affiliate Assistant Professor of Mechanical Engineering, since 1999

  • Directed dissertation research for one PhD student; degree conferred in May 2002.
  • Supervised numerous undergraduate and graduate students as summer interns at ANL/INL.

Professional Service

American Nuclear Society

— member since 1992; student member 1984–1992

  • Active in Materials Science and Technology Division (MSTD)
  • MSTD Executive Committee, 1995–1998
  • Chairman, MSTD Program Committee, 1996–1998
  • Organized/chaired numerous technical sessions at ANS General Meetings

AccApp/ADTTA ’01: Nuclear Applications in the New Millennium

November 11–15, 2001

  • Session Organizer — Transmutation Fuels

Eighth International Conference on Nuclear engineering (ICONE-8), 2–6 April 2000

  • Track 9 Session Organizer — Fuel Technology

Technical Reviewer for Journal of Nuclear Materials and Nuclear Technology

Patents

D. C. Crawford, D. L. Porter, S. L. Hayes and R. N. Hill, "Fuel Element Design for the Enhanced Destruction of Plutonium in a Nuclear Reactor," U. S. Patent No. 5,887,044, March 23, 1999.

Honors and Awards

American Nuclear Society:

  • Significant Contribution Award, Materials Science & Technology Division, 2006

Idaho National Laboratory:

  • Exceptional Contribution Award, October 2006

Argonne National Laboratory:

  • Exceptional Performance Award, 1995, 1997, 1998, 1999, 2000, 2001, 2003
  • Pacesetter Award, October 2003

Texas A&M University:

  • U.S. Department of Energy Nuclear engineering Fellowship, 1988–92
  • Texas Engineering Experiment Station Undergraduate Research Fellowship, 1987
  • Institute of Nuclear Power Operations (INPO) Scholarship, 1986–88
  • Jesse L. Easterwood Memorial Scholarship, 1984–88
  • Alpha Nu Sigma National Nuclear engineering Honor Society, 1988
  • Phi Kappa Phi National Honor Society, 1988
  • Alpha Lambda Delta and Phi Eta Sigma National Freshman Honor Societies, 1985

Publications in secular scientific literature

Journals

  1. M. K. Meyer, S. L. Hayes, W. J. Carmack and H. Tsai, “The EBR-II X501 Minor Actinide Burning Experiment,” submitted for publication in Journal of Nuclear Materials.
  2. W. J. Carmack, D. L. Porter, Y. I. Chang, S. L. Hayes, M. K. Meyer, D. E. Burkes and C. B. Lee “Metallic Fuels for Advanced Reactors,” submitted for publication in Journal of Nuclear Materials.
  3. D. D. Keiser, Jr., J. R. Kennedy, B. A. Hilton and S. L. Hayes, “Development of Metallic Nuclear Fuels for Transmutation Applications: Materials Challenges,” JOM—Journal of the Minerals, Metals & Materials Society 60:29–32, 2008.
  4. D. C. Crawford, D. L. Porter, S. L. Hayes, M. K. Meyer, D. A. Petti and K. Pasamehmetoglu, “An Approach to Fuel Development and Qualification,” Journal of Nuclear Materials 371:232–242, 2007.
  5. D. C. Crawford, D. L. Porter and S. L. Hayes, “Fuels for Sodium-cooled Fast Reactors: U.S. Perspective,” Journal of Nuclear Materials 371:202–231, 2007.
  6. Y. S. Kim, G. L. Hofman, H. J. Ryu and S. L. Hayes, “Irradiation Enhancement of Interdiffusion in the Diffusion Zone of U-Mo Dispersion Fuel in Al,” Journal of Phase Equilibria and Diffusion 27:614–621, 2006.
  7. Y. S. Kim, S. L. Hayes, G. L. Hofman and A. M. Yacout, “Modeling of Constituent Redistribution in U-Pu-Zr Metallic Fuel,” Journal of Nuclear Materials 359:17–28, 2006.
  8. Y. S. Kim, G. L. Hofman, S. L. Hayes and Y. H. Sohn, “Constituent Redistribution in U-Pu-Zr Fuel During Irradiation,” Journal of Nuclear Materials 327:27–36, 2004.
  9. D. D. Keiser, S. L. Hayes, M. K. Meyer and C. R. Clark, “High-Density, Low-Enriched Uranium Fuels for Nuclear Research Reactors,” JOM—Journal of the Minerals, Metals & Materials Society 55:55–58, 2003.
  10. M. K. Meyer, G. L. Hofman, S. L. Hayes, C. R. Clark, T. C. Wiencek, J. L. Snelgrove, R. V. Strain and K. H. Kim, "Low-Temperature Irradiation Behavior of Uranium-Molybdenum Alloy Dispersion Fuel," Journal of Nuclear Materials 304:221–236, 2002.
  11. M. K. Meyer, G. L. Hofman, T. C. Wiencek, S. L. Hayes and J. L. Snelgrove, "Irradiation Behavior of U-Nb-Zr Alloy Dispersed in Aluminum," Journal of Nuclear Materials 299:175–179, 2001.
  12. Y. H. Sohn, M. A. Dayananda, G. L. Hofman, R. V. Strain and S. L. Hayes, "Analysis of Constituent Redistribution in the g (bcc) U-Pu-Zr Alloys Under Gradients of Temperature and Concentrations," Journal of Nuclear Materials 279:317–329, 2000.
  13. M. K. Meyer, T. C. Wiencek, S. L. Hayes and G. L. Hofman, "Irradiation Behavior of U6 Mn-Al Dispersion Fuel Elements," Journal of Nuclear Materials 278:358–363, 2000.
  14. T. C. Totemeier, R. G. Pahl, S. L. Hayes and S. M. Frank, "Characterization of Corroded Metallic Uranium Fuel Plates," Journal of Nuclear Materials 256:87–95, 1998.
  15. G. L. Hofman, S. L. Hayes and M. C. Petri, "Temperature Gradient Driven Constituent Redistribution in U-Zr Alloys," Journal of Nuclear Materials 227:277–286, 1996.
  16. R. G. Pahl, C. E. Lahm and S. L. Hayes, "Performance of HT9 Clad Metallic Fuel Elements at High Temperature," Journal of Nuclear Materials 204:141–147, 1993.
  17. S. L. Hayes and K. L. Peddicord, "Radiative Heat Transfer in Porous Uranium Dioxide," Journal of Nuclear Materials 202:87–97, 1993.
  18. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "Development of a Creep Rate Porosity Correction Factor," Materials Letters 9:435–442, 1990.
  19. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "Material Property Correlations for Uranium Mononitride I. Physical Properties," Journal of Nuclear Materials 171:262–270, 1990.
  20. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "Material Property Correlations for Uranium Mononitride II. Mechanical Properties," Journal of Nuclear Materials 171:271–288, 1990.
  21. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "Material Property Correlations for Uranium Mononitride III. Transport Properties," Journal of Nuclear Materials 171:289–299, 1990.
  22. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "Material Property Correlations for Uranium Mononitride IV. Thermodynamic Properties," Journal of Nuclear Materials 171:300–318, 1990.

Conference proceedings / presentations

  1. D. C. Crawford, S. L. Hayes, D. L. Porter and M. K, Meyer, “Fast Reactor Fuels: The US Perspective”, ANS Topical Meeting on Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Anaheim, CA, 8–12 June 2008.
  2. M. K. Meyer, S. L. Hayes, W. J. Carmack and H. C. Tsai, “The EBR-II X501 Minor Actinide Burning Experiment”, ANS Topical Meeting on Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Anaheim, CA, 8–12 June 2008.
  3. W. J. Carmack, D. L. Porter, Y. I. Chang, S. L. Hayes, M. K. Meyer, D. E. Burkes and C. B. Lee, “Sodium Fast Reactor Fuel Evaluation: Metallic Alloys”, ANS Topical Meeting on Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Anaheim, CA, 8–12 June 2008.
  4. H. J. MacLean and S. L. Hayes, “Irradiation of Metallic and Oxide Fuels for Actinide Transmutation in the ATR,” accepted for publication in Proceedings of the International Conference on Advanced Nuclear Fuel Cycles and Systems (GLOBAL-2007), Boise, ID, 9–13 September 2007.
  5. B. A. Hilton, W. J. Carmack, S. L. Voit, S. L. Hayes and K. O. Pasamehmetoglu, “U.S. Plans for the Next Fast Reactor Actinide Transmutation Fuels Irradiation Test,” accepted for publication in Proceedings of the International Conference on Advanced Nuclear Fuel Cycles and Systems (GLOBAL-2007), Boise, ID, 9–13 September 2007.
  6. S. L. Hayes, M. K. Meyer and W. J. Carmack, “Metallic Fuels for Actinide Transmutation,” submitted to the 8th Russian Conference on Reactor Materials Science, Dimitrovgrad, Russia, 21–25 May 2007.
  7. F. Yapuncich, J. Raffo, D. Ohayon, L. Mariette, A. Ross, S. Brut and S. Hayes, “Packaging and Transportation of FUTURIX-FTA Fuel Pins,” Proceedings of Waste Management ’07, Tucson, AZ, 25 February-1 March 2007.
  8. Y. S. Kim, H. J. Ryu, G. L. Hofman, S. L. Hayes, M. R. Finlay, D. M. Wachs and G. S. Chang, “Interaction Layer Growth Correlations for (U-Mo)/Al and Si-Added (U-Mo)/Al Dispersion Fuels,” Proceedings of the 2006 International Meeting on Reduced Enrichment for Research and Test Reactors, Cape Town, South Africa, 29 October – 2 November 2006.
  9. B. A. Hilton, S. L. Hayes and G. S. Chang, “Irradiation Performance of Fertile-free Metallic Alloys for Actinide Transmutation,” presented at the Inert Matrix Fuels Workshop (IMF-11), Park City, UT, 10–12 October 2006.
  10. J. R. Kennedy, B. A. Hilton, S. L. Hayes and D. C. Crawford, “Metallic Fuels for Actinide Transmutation,” invited presentation at the Ninth OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Nîmes, France, 25–29 September 2006.
  11. W. J. Carmack, J. R. Kennedy, S. L. Hayes, D. Utterbeck, G. S. Chang and B. A. Hilton, “Preliminary Design for the AFC-2 Transmutation Nuclear Fuel Test,” presentation at the Ninth OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Nîmes, France, 25–29 September 2006.
  12. P. Jaecki, S. Pillon, D. Warin, L. Donnet, S. L. Hayes, J. R. Kennedy, K. Pasamehmetoglu, S. L. Voit, D. Haas, A. Fernandez and Y. Arai, “Update on the FUTURIX-FTA Experiment in Phénix,” presentation at the Ninth OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Nîmes, France, 25–29 September 2006.
  13. D. C. Crawford, D. L. Porter and S. L. Hayes, “Fuels for Sodium-cooled Fast Reactors: U.S. Perspective,” Proceedings of the Topical Meeting on Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, American Nuclear Society Summer Meeting, Reno, NV, 4–8 June 2006.
  14. D. C. Crawford, D. L. Porter, S. L. Hayes, M. K. Meyer, D. A. Petti, M. K. Meyer, K. Pasamehmetoglu, A. E. Wright and J. E. Kahalan, “Fuel Development and Safety Testing,” Proceedings of the Topical Meeting on Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, American Nuclear Society Summer Meeting, Reno, NV, 4–8 June 2006.
  15. B. A. Hilton, D. L. Porter and S. L. Hayes, “Postirradiation Examination of AFCI Metallic Transmutation Fuels at 8 at.%,” presented at Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Embedded Topical Meeting at the American Nuclear Society Summer Meeting, Reno, NV, 4–8 June 2006.
  16. B. A. Hilton, D. L. Porter and S. L. Hayes, “Postirradiation Examination of AFCI Nitride and Oxide Transmutation Fuels at 8 at.%,” presented at Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Embedded Topical Meeting at the American Nuclear Society Summer Meeting, Reno, NV, 4–8 June 2006.
  17. Y. S. Kim, G. L. Hofman, S. L. Hayes, H. J. Ryu and M. R. Finlay, “Irradiation Enhancement of Interdiffusion in the Interaction Zone of U-Mo or U3 Si2 Dispersion Fuel in Al,” presented at the 2006 TMS Annual Meeting and Exhibition, San Antonio, TX, 12–16 March 2006.
  18. Y. S. Kim, S. L. Hayes, G. L. Hofman and A. M. Yacout, “RECON-T: REdistribution of CONstituents in a Ternary U-Pu-Zr Fuel,” Trans. Am. Nucl. Soc., 93: 755, American Nuclear Society Winter Meeting, Washington, DC, 13–17 November 2005.
  19. P. Jaecki, S. Pillon, D. Warin, S. L. Hayes, J. R. Kennedy, K. Pasamehmetoglu, S. L. Voit, D. Haas and A. Fernandez, “Update on the FUTURIX-FTA Experiment in PHÉNIX,” Proceedings of the International Conference on Nuclear Energy Systems for Future Generation and Global Sustainability (GLOBAL-2005), Tsukuba, Japan, 9–13 October 2005.
  20. L. Donnet, F. Jorion, N. Drin, S. L. Hayes, J. R. Kennedy, K. Pasamehmetoglu, S. L. Voit, D. Haas and A. Fernandez, “The FUTURIX-FTA Experiment in Phénix: Status of Fuel Fabrication,” Proceedings of the International Conference on Nuclear Energy Systems for Future Generation and Global Sustainability (GLOBAL-2005), Tsukuba, Japan, 9–13 October 2005.
  21. C. R. Clark, D. M. Wachs, S. L. Hayes, M. K. Meyer, T. C. Wiencek, G. L. Hofman and M. R. Finlay, “Irradiation Testing of Monolithic Fuel at Argonne National Laboratory,” Transactions of the 2004 International Topical Meeting on Research Reactor Fuel Management, Budapest, Hungary, 10–13 March 2005.
  22. M. K. Meyer, J. R. Kennedy, S. L. Hayes, J. R. Stuart and D. D. Keiser, “Metal Alloy Fuels for Plutonium and Minor Actinide Transmutation,” presented at the Workshop on Advanced Reactors with Innovative Fuels (ARWIF-2005), Oak Ridge, TN, 16–18 February 2005.
  23. S. L. Hayes, D. M. Wachs and R. A. Brazener, “Enhancements to the PLATE Fuel Performance Code for Analyzing Full-Size and Monolithic Fuel Plates,” presented at the 2004 International Meeting on Reduced Enrichment for Research and Test Reactors, Vienna, Austria, 7–12 November 2004.
  24. C. R. Clark, T. C. Wiencek, M. R. Finlay, R. L. Briggs, D. M. Wachs, S. L Hayes, G. L. Hofman and C. J. Mothershead, “Update on Fuel Fabrication Development and Testing at Argonne National Laboratory,” Proceedings of the 2004 International Meeting on Reduced Enrichment for Research and Test Reactors, Vienna, Austria, 7–12 November 2004.
  25. E. Brunon, L. Donnet, N. Drin, P. Jaecki, S. Pillon, F. Sudreau, D. Warin, S. L. Hayes, J. R. Kennedy, M. K. Meyer, S. Willson, A. Fernandez, D. Haas and Y. Arai “The FUTURIX-FTA Experiment in Phénix,” 8th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (OECD-NEA), Las Vegas, Nevada, 9–11 November 2004.
  26. S. L. Hayes, “AFCI Irradiation Testing in the Advanced Test Reactor,” invited presentation at the ATR Users Conference, Jackson Hole, WY, 20–22 October 2004.
  27. B. A. Hilton, S. L. Hayes, M. K. Meyer, J. R. Kennedy, D. C. Crawford, G. S. Chang, R. G. Ambrosek, “Irradiation Tests and Postirradiation Examination of Metallic Alloy and Nitride Based Transmutation Fuels,” Proceedings of the 12th International Conference on Nuclear engineering (ICONE-12), Arlington, VA, 25–29 April 2004.
  28. C. R. Clark, S. L. Hayes, M. K. Meyer, G. L. Hofman and J. L. Snelgrove, “Update on U-Mo Monolithic and Dispersion Fuel Development,” Transactions of the 2004 International Topical Meeting on Research Reactor Fuel Management, Munich, Germany, 21–24 March 2004.
  29. G. L. Hofman, Y. S. Kim, M. R. Finlay, J. L. Snelgrove, S. L. Hayes, M. K. Meyer, C. R. Clark and F. Huet, “Recent Observations at the Postirradiation Examination of Low-Enriched U-Mo Miniplates irradiated to High Burnup,” Transactions of the 2004 International Topical Meeting on Research Reactor Fuel Management, Munich, Germany, 21–24 March 2004.
  30. J. D. B. Lambert, D. C. Crawford, R. N. Hill, S. L. Hayes, A. E. Waltar, R. B. Baker and B. J. Makenas, “Fifty Years of US Fuels and Materials Development for Fast Reactors” Proceedings of the Russian Forum for Science and Technology Meeting on Fast Neutron Reactors, Obninsk, Russia, 8–12 December 2003.
  31. S. L. Hayes and M. K. Meyer, “Fuel Performance Modeling for Metallic and Dispersion Actinide Transmutation Fuels,” presented at the Workshop on Materials Modeling and Simulations for Nuclear Fuels, New Orleans, LA, 20–21 November 2003.
  32. S. L. Hayes and R. A. Brazener, “Validation of the PLATE Code for Predicting U-Mo/Al Fuel Plate Swelling,” Trans. Am. Nucl. Soc. 89:379, American Nuclear Society Winter Meeting, New Orleans, LA, 20–21 November 2003.
  33. B. A. Hilton, S. L. Hayes, M. K. Meyer, D. C. Crawford, G. S. Chang and R. G. Ambrosek, “The AFC-1Æ and AFC-1F Irradiation Tests of Metallic and Nitride Fuels for Actinide Transmutation,” Proceedings of the Topical Meeting on Advanced Nuclear Energy Systems and Fuel Cycle Systems (GLOBAL-2003), New Orleans, LA, 16–20 November 2003, pp. 215–219.
  34. S. Pillon, N. Schmidt, E. Abonneau, Y. Croixmarie, L. Donnet S. Hayes, M. Meyer, K. Chidester, B. Margevicius, A. Fernandez and D. Haas, “The FUTURIX-FTA Experiment in Phénix,” Proceedings of the Topical Meeting on Advanced Nuclear Energy Systems and Fuel Cycle Systems (GLOBAL-2003), New Orleans, LA, 16–20 November 2003, pp. 220–227.
  35. S. L. Hayes, M. K. Meyer, G. L. Hofman, J. L. Snelgrove and R. A. Brazener, “Modeling RERTR Experimental Fuel Plates Using the PLATE Code,” Proceedings of the 2003 International Meeting on Reduced Enrichment for Research and Test Reactors, Chicago, Illinois, 5–10 October 2003.
  36. G. L. Hofman, Y. S. Kim, M. R. Finlay, J. L. Snelgrove, S. L. Hayes, M. K. Meyer and C. R. Clark, “Recent Observations at the Postirradiation Examination of Low-Enriched U-Mo Miniplates Irradiated to High Burnup,” Proceedings of the 2003 International Meeting on Reduced Enrichment for Research and Test Reactors, Chicago, Illinois, 5–10 October 2003.
  37. Y. S. Kim, G. L. Hofman, S. L. Hayes and Y. H. Sohn, “Analysis of Thermomigration in Irradiated U-Pu-Zr Fuel,” presented at Plutonium Futures—The Science 2003, Albuquerque, NM, 6–10 July 2003.
  38. S. L. Hayes, “U-Mo/Al Dispersion Fuel Modeling,” invited paper/presentation to be published in the Proceedings of the IAEA Technical Meeting on the Development of High Density Uranium-Molybdenum Dispersion Fuels, Vienna, Austria, 23–25 June 2003.
  39. M. K. Meyer, J. R. Kennedy, S. L. Hayes, D. D. Keiser, S. M. Frank, R. G. Ambrosek and G. S. Chang, “Fabrication, Characterization and Irradiation Testing of Minor Actinide Fuels in the AFC-1 Test,” presented at the American Nuclear Society Summer Meeting, San Diego, CA, 1–5 June 2003.
  40. M. K. Meyer, S. L. Hayes, J. R. Kennedy, D. D. Keiser, B. A. Hilton, S. M. Frank, Y. S. Kim, G. S. Chang and R. G. Ambrosek, “Development and Testing of Metallic Fuels with High Minor Actinide Content,” Proceedings of the 11th International Conference on Nuclear engineering (ICONE-11), Tokyo, Japan, 20–23 April 2003.
  41. G. L. Hofman, J. L. Snelgrove, S. L. Hayes, M. K. Meyer and C. R. Clark, “Progress in Postirradiation Examination and Analysis of Low-Enriched U-Mo Research Reactor Fuels,” Transactions of the 2003 International Topical Meeting on Research Reactor Fuel Management: RRFM-2003, Aix-en-Provence, France, 9–11 March 2003.
  42. S. L. Hayes, B. A. Hilton, M. K. Meyer, G. S. Chang, F. W. Ingram, S. Pillon, N. Schmidt, L. Leconte and D. Haas, “U. S. Test Plans for Actinide Transmutation Fuel Development,” Trans. Am. Nucl. Soc. 87:353, American Nuclear Society Winter Meeting, Washington, DC, 17–21 November 2002.
  43. G. S. Chang, R. G. Ambrosek, F. W. Ingram, S. L. Hayes and M. K. Meyer, “Neutronic Analysis of Fast Neutron Flux Enhancement in the ATR,” Trans. Am. Nucl. Soc. 87:529, American Nuclear Society Winter Meeting, Washington, DC, 17–21 November 2002.
  44. S. L. Hayes, G. L. Hofman, M. K. Meyer, J. Rest and J. L. Snelgrove, “Modeling of High-Density U-Mo Dispersion Fuel Plate Performance,” Proceedings of the 2002 International Meeting on Reduced Enrichment for Research and Test Reactors, San Carlos de Bariloche, Argentina, 3–8 November 2002.
  45. C. R. Clark, M. K. Meyer, S. L. Hayes, G. L. Hofman and J. L. Snelgrove, “RERTR Fuel Development Work at Argonne National Laboratory,” Proceedings of the Americas Nuclear Energy Symposium 2002 (ANES-2002), Miami, FL, 16–18 October 2002.
  46. S. L. Hayes, "Testing of High-Density, Low-Enrichment Dispersion Fuels in the Advanced Test Reactor," invited presentation at the ATR Users Conference, Salt Lake City, UT, 20–22 October 2002.
  47. S. L. Hayes, "Irradiation Testing of Actinide Transmutation Fuels in the Advanced Test Reactor," invited presentation at the ATR Users Conference, Salt Lake City, UT, 20–22 October 2002.
  48. D. C. Crawford, M. K. Meyer, S. L. Hayes and J. J. Laidler, “Requirements and Long-Term Development Plan for Fast-Spectrum Transmutation Fuels in the U.S.,” Proceedings of the 7th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Jeju, Korea, 14–16 October 2002.
  49. D. M. Wachs, S. L. Hayes and T. C. Totemeier, "Modeling the Ignition Behavior of Hydride Bearing Uranium Corrosion Products," Proceedings of the 5th Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, Charleston, SC, 16–19 September 2002.
  50. G. L. Hofman, J. L. Snelgrove, S. L. Hayes and M. K. Meyer, “Progress in Development of Low-Enriched U-Mo Dispersion Fuels,” Transactions of the 2002 International Topical Meeting on Research Reactor Fuel Management, Ghent, Belgium, 17–20 March 2002.
  51. Languille, D. Plancq, F. Huet, B. Guigon, P. Lemoine, P. Sacristan, G. Hofman, J. Snelgrove, J. Rest, S. Hayes, M. Meyer, H. Vacelet, E. Leborgne, and G. Dassel, “Experimental Irradiation of UMo Fuel: PIE Results and Modeling of Fuel Behaviour,” Transactions of the 2002 International Topical Meeting on Research Reactor Fuel Management: RRFM-2002, Ghent, Belgium, 17–20 March 2002.
  52. S. L. Hayes, M. K. Meyer, D. C. Crawford, G. S. Chang and F. W. Ingram, "Irradiation Testing of Actinide Transmutation Fuels in the Advanced Test Reactor," Proceedings of the Conference on Accelerator Applications/Accelerator Driven Transmutation Technology and Applications ’01 (AccApp/ADTTA-01), American Nuclear Society, Reno, NV, 12–15 November 2001.
  53. M. K. Meyer, S. L. Hayes, D. C. Crawford, R. G. Pahl and H. Tsai, "Fuel Design for the U.S. Accelerator Driven Transmutation System," Proceedings of the Conference on Accelerator Applications/Accelerator Driven Transmutation Technology and Applications ’01 (AccApp/ADTTA-01), American Nuclear Society, Reno, NV, 12–15 November 2001.
  54. J. L. Snelgrove, G. L. Hofman, S. L. Hayes and M. K. Meyer, "Progress in Qualifying Low-Enriched U-Mo Dispersion Fuels," Transactions of the 2001 International Topical Meeting on Research Reactor Fuel Management, Aachen, Germany, 1–4 April 2001.
  55. D. C. Crawford, S. L. Hayes and M. K. Meyer, "Current U.S. Plans for Development of Fuels for Accelerator Transmutation of Waste" Proceedings of the IAEA Technical Committee Meeting on Core Physics and Engineering Aspects of Emerging Nuclear Energy Systems for Energy Generation and Transmutation, Chicago, IL, 26 November 2000.
  56. S. L. Hayes, “Advanced Test Reactor Experiments with Reduced-Enrichment Fuels,” invited presentation at the ATR Users Conference, Salt Lake City, UT, 4–6 October 2000.
  57. S. L. Hayes, C. R. Clark, J. R. Stuart, M. K. Meyer, T. C. Wiencek, J. L. Snelgrove and G. L. Hofman, "Irradiation Testing of Intermediate and High-Density U-Mo Alloy Dispersion Fuels to High Burnup," Proceedings of the 2000 International Meeting on Reduced Enrichment for Research and Test Reactors, Las Vegas, NV, 1–6 October 2000.
  58. M. K. Meyer, J. L. Snelgrove, G. L. Hofman, S. L. Hayes, J. R. Stuart, C. R. Clark and R. V. Strain, "Advanced Research Reactor Fuel Development," Proceedings of the Eighth International Conference on Nuclear engineering (ICONE-8), Baltimore, MD, 2–6 April 2000.
  59. T. R. Allen, D. C. Crawford and S. L. Hayes, "Fuels and Cladding for Advanced Reactors," Proceedings of the 23rd National Society of Black Physicists Annual Conference, Greensboro, NC, March 15–18, 2000, pp. 41–54.
  60. M. K. Meyer, G. L. Hofman, J. L. Snelgrove, C. R. Clark, S. L. Hayes, R. V. Strain J. M. Park and K. H. Kim, "Irradiation Behavior of Uranium-Molybdenum Fuel: Quantitative Data from RERTR-1 and-2," Proceedings of the 1999 International Meeting on Reduced Enrichment for Research and Test Reactors, Budapest, Hungary, 3–8 October 1999.
  61. S. L. Hayes, M. K. Meyer, C. R. Clark, J. R. Stuart, I. G. Prokofiev and T. C. Wiencek, "Prototypic Irradiation Testing of High-Density U-Mo Alloy Dispersion Fuels," Proceedings of the 1999 International Meeting on Reduced Enrichment for Research and Test Reactors, Budapest, Hungary, 3–8 October 1999.
  62. L. Yakovlev, A. P. Blynski, V. N. Karaulov, J. D. B. Lambert and S. L. Hayes, "Characterization of Spent Fuel Assemblies from BN-350," presented at the 2nd International Conference on Nuclear and Radiation Physics (ICNRP), Almaty, Kazakhstan, 7–10 June 1999.
  63. L. Snelgrove, G. L. Hofman, M. K. Meyer, S. L. Hayes, T. C. Wiencek and R. V. Strain, "Progress in Developing Very-High-Density Low-Enriched-Uranium Fuels," Transactions of the 1999 International Topical Meeting on Research Reactor Fuel Management: RRFM-1999, Bruges, Belgium, 28–30 March 1999.
  64. S. L. Hayes, M. K. Meyer, G. L. Hofman and R. V. Strain, "Postirradiation Examination of High-Density Uranium Alloy Dispersion Fuels," Proceedings of the 1998 International Meeting on Reduced Enrichment for Research and Test Reactors, São Paulo, Brazil, 18–23 October 1998.
  65. M. K. Meyer, J. L. Snelgrove, G. L. Hofman and S. L. Hayes, "U. S. RERTR Advanced Fuel Development Plans: 1999," Proceedings of the 1998 International Meeting on Reduced Enrichment for Research and Test Reactors, São Paulo, Brazil, 18–23 October 1998.
  66. S. L. Hayes, "Advanced Test Reactor Experiments with Reduced-Enrichment Fuels," invited presentation at the ATR Users Conference, Jackson Hole, WY, 17–18 September 1998.
  67. L. Snelgrove, G. L. Hofman, M. K. Meyer, S. L. Hayes, C. L. Trybus and T. C. Wiencek, "Development of Very-High-Density Low-Enriched-Uranium Fuels," presented at the American Nuclear Society Winter Meeting, Albuquerque, NM, 16–20 November 1997.
  68. S. L. Hayes, C. L. Trybus and M. K. Meyer, "Irradiation Testing of High-Density Uranium Alloy Dispersion Fuels," Proceedings of the 1997 International Meeting on Reduced Enrichment for Research and Test Reactors, Jackson Hole, WY, 5–10 October 1997.
  69. T. C. Totemeier, S. L. Hayes, R. G. Pahl and D. C. Crawford, "Corrosion and Pyrophoricity of ZPPR Fuel Plates: Implications for Basin Storage," presented at the American Institute of Chemical Engineers Spring 1997 National Meeting, Houston, TX, 10–13 March 1997.
  70. S. L. Hayes, G. L. Hofman and R. V. Strain, "Thermal Diffusion in U-Zr and U-Pu-Zr Metal Alloys," invited presentation at the Minerals, Metals & Materials Society Fall Meeting, Cincinnati, OH, 6–10 October 1996.
  71. T. C. Totemeier and S. L. Hayes, "Analytical and Numerical Models of Uranium Ignition Assisted by Hydride Formation," Proceedings of the American Nuclear Society Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, Reno, NV, 16–20 June 1996, p. 345.
  72. S. E. Aumeier, K. A. Bunde, S. L. Hayes and C. L. Trybus, "Calculation of Displacement Rate in EBR-II Reactor Materials," Trans. Am. Nucl. Soc. 73:161, American Nuclear Society Winter Meeting, San Francisco, CA, 29 October – 2 November 1995.
  73. S. L. Hayes and G. L. Hofman, "Constituent Redistribution Modeling in U-Zr Fast Reactor Fuel," Trans. Am. Nucl. Soc. 71:179, American Nuclear Society Winter Meeting, Washington, D.C., 13–17 November 1994.
  74. D. C. Crawford, S. L. Hayes and R. G. Pahl, "Large-Diameter, High-Plutonium Metallic Fuel Testing in EBR-II," Trans. Am. Nucl. Soc. 71:178, American Nuclear Society Winter Meeting, Washington, D. C., 13–17 November 1994.
  75. R. G. Pahl, C. E. Lahm and S. L. Hayes, "Performance of HT9 Clad Metallic Fuel at High Temperature," Proceedings of the ANS/ENS International Symposium on Fuels for Liquid Metal Reactors, Chicago, IL, 15–20 November 1992.
  76. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "Material Property Correlations for Uranium Mononitride," 7th Symposium on Space Nuclear Power Systems, Albuquerque, NM, 7–10 January 1990.
  77. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "A Steady-State Creep Rate Correlation for Uranium Mononitride," 91st Meeting of the American Ceramic Society, Indianapolis, IN, 23–27 April 1989.
  78. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "Development of a Porosity Correction Factor for Creep Rate," 91st Meeting of the American Ceramic Society, Indianapolis, IN, 23–27 April 1989.
  79. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "Elastic Constants and Creep of Uranium Mononitride," 6th Symposium on Space Nuclear Power Systems, Albuquerque, NM, 9–12 January 1989.
  80. S. L. Hayes, J. K. Thomas and K. L. Peddicord, "Mechanical Properties of Uranium Nitride," 90th Meeting of the American Ceramic Society, Cincinnati, OH, 1–5 May 1988.
  81. J. K. Thomas, D. E. Brozak, S. L. Hayes and K. L. Peddicord, "Material Property and Irradiation Performance Correlations for Nitride Fuels," 5th Symposium on Space Nuclear Power Systems, Albuquerque, NM, 12–16 January 1988.
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