Professional Information

Education

  • PhD Mechanical Engineering (Energy Conversion), 1978, Colorado State University
  • MS Mechanical Engineering, 1970, Utah State University
  • BS Mechanical Engineering, 1968, Utah State University

Experience

  • Since 2009 – Chair, Department of Integrated Engineering, Southern Utah University.
  • 1978 to 2009 – Idaho National Laboratory: Fusion Safety Program Manager, Technical Lead on fission reactor experiments, research on tritium production, storage and interactions with structures, beryllium utilization and disposal, space nuclear power systems, nuclear fuels development.
  • 1998 – Safety Manager (loaned executive) Northstar Spaceport Corporation
  • 1995 to 1998 – Industry-shared Professor, Idaho State University.
  • 1970 to 1975 – U.S. Army Materiel Command: Interagency Test Team Leader for development testing of XM-712 Copperhead laser guided artillery round.

Selected Publications

G. R. Longhurst and J. Cleaver, 2008, “Interactions of Hydrogen Isotopes and Oxides With Metal Tubes,” Fusion Science and Technology 54, pp. 565-568.

G. R. Longhurst and J. A. Ambrosek, August 2005, “Verification and Validation of the Tritium Transport Code TMAP7,” Fusion Science and Technology 48, pp. 468 – 471.

G. R. Longhurst, R. A. Anderl, R. J. Pawelko, and  C. J. Stoots, August 2005,  “Storage and Assay of Tritium in STAR,” Fusion Science and Technology 48, pp. 332 – 336.

G. R. Longhurst, “TMAP7 User Manual,” INEEL/EXT-04-02352, October 2004, Idaho National Engineering and Environmental Laboratory.

G. R. Longhurst, G. L. Anderson, M. L. Carboneau, and C. K. Mullen, Irradiated Beryllium Disposal: Situation Appraisal, Rev. 01, INEEL/INT-01-01207, Idaho National Engineering and Environmental Laboratory, July 2002.

G. R. Longhurst, G. L. Anderson, C. K. Mullen, W. H. West, Irradiated Beryllium Disposal Technology Workshop, May 29-30, 2002, INEEL/EXT-02-00785, Idaho National Engineering and Environmental Laboratory, June 2002.

G. R. Longhurst, B. G. Schnitzler, B. T. Parks, “Multi-Megawatt Power System Trade Study,” Space Technology and Applications International Forum-STAIF 2002, Albuquerque, NM, 3-6 February 2002, AIP Conference Proceedings Vol. 608.

G. R. Longhurst, E. A. Harvego, B. G. Schnitzler, G. D. Seifert, J. P. Sharpe, D. A. Verrill, K. D. Watts, B. T. Parks, "Multi-Megawatt Power System Evaluation," INEEL/EXT-01-00938, July 2001, Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, B. G. Schnitzler, B. T. Parks, "Multi-Megawatt Power System Trade Study," INEEL/EXT-01-00913, July 2001, Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, Alkasys Code Adaptation," INEEL/EXT-01-00539, April 2001, Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, "Tritium Inventory in Aries-AT," INEEL/EXT-01-00306, February, 2001, Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, B. J. Merrill, and J. L. Jones, TMAP2000 Use, INEEL/EXT-2000-1337, October 2000, Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, "TMAP2000 Development," INEEL/EXT-2000-678, May 2000, Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, R. A. Anderl, and R. S. Willms, “Tritium Loss in Molten Flibe Systems.” Fusion Technology, 38 (2000) 376-383.

G. R. Longhurst, R. A. Anderl, R. A. Causey, G. Federici, A. A. Haasz, R. J. Pawelko, “Tritium Saturation in Plasma-Facing Materials Surfaces,” Journal of Nuclear Materials, 258-263 (1998) 640-644.

G. R. Longhurst, “Modeling of Hydrogen Interactions with Beryllium.” Proceedings of the Third IEA International Workshop on Beryllium Technology for Fusion, Mito City, Japan, October 22-24, 1997, JAERI-CONF 98-001, Japan Atomic Energy Research Institute.

G. R. Longhurst, D. A. Petti, G. A. Dinneen, J. S. Herring, J. DeLooper, J. D. Levine, M. J. Gouge, "Development of Fusion Safety Standards," Fusion Technology, 29 (1996) pp. 627-633.

G. R. Longhurst, A. Gervash, M. Dalle Donne, J. E. Hanafee, R. D. Watson, H. Kawamura, D. M. Dombrowski, "Meeting Summary, 2nd IEA International Workshop on Beryllium Technology for Fusion," Fusion Technology, 29 (1996) pp. 409-412.

G. R. Longhurst, R. A. Anderl, T. J. Dolan, and M. J. Mulock, "Modeling Tritium Processes in Plasma-Facing Beryllium,"  Fusion Technology, 28 (1995) pp. 1217-1222.

G. R. Longhurst, "A Simplified Model for Tritium Permeation Transient Predictions When Trapping is Active," Journal of Nuclear Materials 212-215 (1994) pp. 1015-1020.

G. R. Longhurst, S. L. Harms, E. S. Marwil, and B. G. Miller, "Verification and Validation of TMAP4," EGG-FSP-10347, Rev. 01, March 19, 1994, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, R. A. Anderl, T. J. Dolan, M. R. Hankins and R. J. Pawelko, "Research of Beryllium Safety Issues," Workshop on Beryllium for Fusion Applications, Karlsruhe, Germany, 4-5 October 1993, KFK 5271, (December 1993).

G. R. Longhurst, "Simplified Tritium Permeation Model," EGG-FSP-10960, September 1993, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

G. R. Longhurst and T. J. Dolan, "HYLIFE-II Tritium Management System," EGG-FSP-9971, June 1993, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, R. A. Anderl, J. R. Bartlit, R. A. Causey and J. R. Haines, "Using the Tritium Plasma Experiment to Evaluate ITER PFC Safety," Journal of Fusion Energy 12, Nos. 1/2 (1993)  pp. 115-119.

G. R. Longhurst, "Tritium Permeation Model for Plasma Facing Components," EGG-FSP-10609, December 1992, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, D. F. Holland, J. L. Jones, and B. J. Merrill, "TMAP4 User's Manual," EGG-FSP-10315, June 12, 1992, Idaho National Engineering Laboratory, Idaho Falls, ID.

G. R. Longhurst, A. G. Heics, Walter T. Shmayda, and R. L. Rossmassler, "Experimental Evaluation of the Consequences of Uranium Bed Air-Ingress Accidents," Fusion Technology 21 (Mar 1992) pp. 1017-1023.

G. R. Longhurst, "Beryllium Technology Workshop, Clearwater Beach, Florida, November 20, 1991," EGG-FSP-10017, December 1991, Idaho National Engineering Laboratory, Idaho Falls, ID.

G. R. Longhurst, "Trapping Effects on Diffusion Transients," EGG-FSP-9789, July 1991, Idaho National Engineering Laboratory, Idaho Falls, ID.

G. R. Longhurst and T. J. Dolan, "Tritium Permeation Losses in HYLIFE II Heat Exchanger Tubes," Fusion Technology 19 (May 1991) pp. 820-825.

G. R. Longhurst, R. A. Anderl, and D. F. Holland, "Evidences of Hydrogen Trapping in Tungsten and Implications for Plasma-Facing Components," Fusion Technology 19 (May 1991) pp. 1799-105.

G. R. Longhurst, "Gas Evolution from Spheres," EGG-FSP-9634, April 1991, Idaho National Engineering Laboratory, Idaho Falls, ID.

G. R. Longhurst, "Preliminary Analysis of Uranium Bed Air-Exposure Test Data," EGG-FSP-9435, December 1990, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, "Tritium Behavior in ITER Beryllium," EGG-FSP-9304, October 1990, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, "The INEL Tritium Research Facility," Fusion Engineering and Design 12 (1990) pp. 403-409.

G. R. Longhurst, "Observing Diffusivity and Traps for Tritium in Metals by Thermal Transient Tests," EGG-FSP-8766, October 1989, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

G. R. Longhurst and W. T. Shmayda, "Uranium Storage Bed Accident Hazards Evaluation," Proceedings, IEEE 13th Symposium on Fusion Engineering, October 2-6, 1989, Knoxville, TN, IEEE Cat. No. 89CH2820 9, pp. 812-815.

G. R. Longhurst, "Permeation of Tritium Through HYLIFE-II Heat Exchanger Tubes," EGG-FSP-8678, September 1989, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, R. A. Jalbert, R. L. Rossmassler, "Atmospheric Deterioration System Performance," Fusion Technology 15, 2, 2B, (1989) pp. 1331-1336.

G. R. Longhurst, T. J. Dolan, and G. L. Henriksen, "An Investigation of Energy Balances in Palladium Cathode Electrolysis Experiments," Workshop on Cold Fusion Phenomena, May 23-25, 1989, Santa Fe, New Mexico.

G. R. Longhurst, "Pyrophoricity of Tritium-Storage Bed Materials," EGG-FSP-0850, March, 1988, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

G. R. Longhurst, R. A. Anderl, D. A. Struttman, "Implications of Recent Implantation-Driven Permeation Experiments for Fusion Reactor Safety," Proceedings of the Japan-US Workshop on Tritium Technology, JAERI-M 86-189, January 1987, Japan Atomic Energy Research Institute, Tokyo, Japan.

G. R. Longhurst, R. M. Neilson, Jr., and L. J. Porter, "Tritium Storage Metal-Bed Pyrophoricity Measurements," Proceedings 12th Symposium on Fusion Engineering, October 12-16, 1987, Monterey, California, IEEE Catalog No. 87CH2507-2, p. 536-543.

G. R. Longhurst, R. A. Anderl, and D. A. Struttman, "A Comparison of Implantation-Driven Permeation Characteristics of Fusion Reactor Structural Materials," Journal of Nuclear Materials, 141-143 (1986) pp. 229-233.

G. R. Longhurst, "The Soret Effect and Its Implications for Fusion Reactors," Journal of Nuclear Materials, 131 (1985) pp. 61-66.

D. A.Petti, G. J. Merrill, R. L. Moore, G. R. Longhurst, L. El-Guebaly, E. Mogahed, D. Henderson, P. Wilson, A. Abdou, “ARIES-AT safety design and analysis,” Fusion Engineering and Design, 80 (2006) pp. 111-137.

R. A. Anderl, G. R. Longhurst, R. J. Pawelko, J. P. Sharpe, S. T. Schuetz, and D. A. Petti, July/Aug 2005,  “The Safety and Tritium Applied Research (STAR) Facility Status, 2004,” Fusion Science and Technology 48 (2005), pp 243-249.

W. F. Skerjanc and G. R. Longhurst, July 2005, “Gas Test Loop Facilities Alternative Assessment Report,” INL/EXT-05-00263, Idaho National Laboratory.

J. A. Ambrosek and G. R. Longhurst, “Verification and Validation of TMAP7,” INEEL/EXT-04-01657, October 2004, Idaho National Engineering and Environmental Laboratory.

J. A. Vail, M, L. Carboneau, G. R. Longhurst,  “Estimated Radiological Inventory Sent from the Idaho Nuclear Technology and Engineering Center to the Subsurface Disposal Area from 1952 through 1993,” INEEL/EXT-03-00967, March 2004, Idaho National Engineering and Environmental Laboratory.

C.K. Mullen, G. R. Longhurst, M. L. Carboneau, J. W. Sterbentz, Beryllium Waste Transuranic Inventory in the Subsurface Disposal Area, Operable Unit 7-13/14, INEEL/EXT-01-01678, December 2002, Idaho National Engineering and Environmental Laboratory.

R. A. Anderl, D. A. Petti, K. A. McCarthy, G. R. Longhurst, “The Safety and Tritium Applied Research Facility”, Fusion Science and Technology, 41, No. 3 (2002) pp. 568-572.

A. Khomutov, V. Barabsh, V. Cvhakin, V. Chernov, D. Davydov, V. Gorokhov, H. Kawamura, B. Kolbasov, I. Kupriyanov, G. Longhurst, F. Scaffidi-Argentina, V. Shestikov, “Beryllium for Fusion Application-Recent Results,” Journal of Nuclear Materials 307-311 (2002) pp. 630-637.

D. A. Petti, B. J. Merrill, R. L. Moore, G. R. Longhurst, L. El-Guebalay, E. Mogahed, D. Henderson, P. Wilson, and A. Abdou, "Safety and Environment Assessment of ARIES-AT, Fusion Technology, 9 (2001) 449-457.

F. Scaffidi-Argentina and G. R. Longhurst, "The Fourth International Energy Agency International Workshop on Beryllium Technology for Fusion, Karlsruhe, Germany, September 15-17, 1999," Fusion Technology, 37 (May 2000) pp. 259-263.

F. Scaffidi-Argentina, G. R. Longhurst, V. Shestakov, H, Kawamura, “The Status of Beryllium Technology for Fusion,” Journal of Nuclear Materials, 283-287 (2000) pp.43-51.

F. Scaffidi-Argentina, G. R. Longhurst, V. Shestakov, “Berylium R&D for Fusion Applications,” Fusion Engineering and Design, 51-52 (2000) pp. 23-41.

Kh Klepikov, O. G. Romanenko, Y. V. Chikhray, I. L. Tazhibaeva, V. P. Shestakov, G. R. Longhurst, “Hydrogen Release from Irradiated V-4Cr-4Ti,” Fusion Engineering and Design, 51-52 (2000) pp. 127-133.

R. A. Anderl, R. A. Causey, J. W. Davis, R. P. Doerner, G. Federici, A. A. Haasz, G. R. Longhurst, W. R. Wampler, and K. L. Wilson, “Hydrogen Isotope Retention in Beryllium for Tokamak Plasma-Facing Applications,” Journal of Nuclear Materials, 273 (1999) pp. 1-26.

R. A. Anderl, M. R. Hankins, G. R. Longhurst, R. J. Pawelko, "Deuterium transport in Cu, CuCrZr and Cu/Be," Journal of Nuclear Materials, 266-269 (1999) pp. 761-765.

G. Federici, R.A. Anderl, P. Andrew, J.N. Brooks, R.A. Causey, J.P.Coad, D. Cowgill, R.P. Doerner, A.A.Haasz, G. Janeschitz, W. Jacob, G.R. Longhurst, R. Nygren, A. Peacock, M. Pick, V. Philipps, J. Roth, C. Skinner, W.R. Wampler, “Implications of In-Vessel Tritium Retention and Removal for ITER, Journal of Nuclear Materials, 266-269 (1999) 14-29.

M. Dalle Donne, G. R. Longhurst, H. Kawamura, and F. Scaffidi-Argentina, “Beryllium R&D for blanket application,” Journal of Nuclear Materials, 258-263 (1998) 601-606.

G. Federici, R. Anderl, J. N. Brooks, R. Causey, J. P. Coad, D. Cowgill, R. Doerner, A. A. Haasz, G. Longhurst, S. Luckhardt, D. Mueller, A. Peacock, M. Pick, C. H. Skinner, W. Wampler, K. Wilson, C. Wong, C. Wu, D. Youchison, “Tritium Inventory in the ITER PFCs: Predictions, Uncertainties, R&D Status and Priority Needs,” Fusion Engineering and Design 39-40 (1998) pp. 445-464.

R. A. Anderl, G. R. Longhurst, M. A. Oates, and R. J. Pawelko, “Tritium and Helium Retention and Release from Irradiated Beryllium,” Third IAEA International Workshop on Beryllium Technology for Fusion, Mito City, Japan, October 22-24, 1997.

K. A. McCarthy, G. R. Smolik, R. A. Anderl, W. J. Carmack, and G. R. Longhurst, “An Overview of INEL Fusion Safety R&D Facilities,” Journal of Fusion Energy, Vol. 16, Nos. 1&2 (1997) pp. 113-118.

R. A. Anderl, G. R. Longhurst, R. J. Pawelko, and M. A. Oates, "Implanted Deuterium Retention and Release in Carbon-Coated Beryllium," IEA 6th Technical Committee Meeting on Developments in Fusion Safety, 21-25 October 1996, Naka, Japan, Journal of Fusion Energy, 16 (1997) pp. 95-100.

R. A. Causey, G. R. Longhurst, W. Harbin, "Measurement of Tritium Migration in Beryllium Using the Tritium Plasma Experiment," 12th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, May 20-24, 1996, Saint Raphael, France, Journal of Nuclear Materials, 241-243 (1997) pp. 1041-1046.

T. J. Dolan, G. R. Longhurst, O. K. Kveton, L. J. Wittenberg, S. Tanaka, "Materials Management and Target Materials Recovery," Section 3.6 of the book Energy from Inertial Fusion, International Atomic Energy Agency, Vienna, 1995, pp. 245-259.

W. D. Manly, D. E. Dombrowski, J. E. Hanafee, L. A. Jacobson, G. J. Landon, G. R. Longhurst, R. D. Watson, J. L. Yuen, M. A. Ulrickson, Report of a Technical Evaluation Panel on the Use of Beryllium for ITER Plasma Facing Material and Blanket Breeder Material, SAND95-1963, August 1995, Sandia National Laboratories, Albuquerque, NM.

G. Federici, T. Dolan, D. Holland, R. Causey, J. Brooks, and G. Longhurst, "Preliminary Assessment of the Tritium Inventory and Permeation in the PFCs of ITER," Proceedings, 16th IEEE/NPSS Symposium on Fusion Engineering, September 30 - October 5, 1995, Urbana, IL, 0-7803-2969-4/95 IEEE (1995) pp. 418-423.

R. A. Anderl, R. J. Pawelko, M. R. Hankins, G. R. Longhurst, R. A. Neiser, "Hydrogen Permeation Properties of Plasma-Sprayed Tungsten," Journal of Nuclear Materials 212-215 (1994) pp. 1416-1420.

R. W. Moir, R. L. Biere, X. M. Chen, T. J. Dolan, M. A. Hoffman, P. A. House, R. L. Leber, J. D. Lee, Y. T. Lee, J. C. Liu, G. R. Longhurst, W. R. Meier, P. F. Peterson, R. W. Petzold, V. E. Schrock, M. T. Tobin, and W. H. Williams, "HYLIFE-II: A Molten-Salt Inertial Fusion Energy Power Plant Design-Final Report," Fusion Technology 25 (1994) pp. 5-25.

P. D. Ritter, T. J. Dolan, and G. R. Longhurst, "Tritium Environmental Transport Studies at TFTR," Journal of Fusion Energy 12, Nos. 1/2 (1993) pp. 145-148.

T. J. Dolan, G. R. Longhurst, and E. Garcia-Otero, "A Vacuum Disengager for Tritium Removal from HYLIFE-II Reactor Flibe," Fusion Technology 21, 3, 2B (May 1992) pp. 1949-1954.

R. A. Anderl, M. R. Hankins, G. R. Longhurst, R. J. Pawelko, and R. G. Macaulay-Newcombe, "Hydrogen Transport Behavior of Beryllium," Journal of Nuclear Materials 196-198 (1992) pp.986-991.

J. M. Beeston, G. R. Longhurst, R. S. Wallace, and S. P. Abeln, "Mechanical Properties of Irradiated Beryllium," Journal of Nuclear Materials 195 (1992) pp. 102-108.

R. A. Anderl, D. F. Holland, G. R. Longhurst, R. J. Pawelko, C. L. Trybus, and C. H. Sellers, "Deuterium Transport and Trapping in Polycrystalline Tungsten," Fusion Technology 21 (Mar 1992) pp. 745-752.

L. J. Porter and G. R. Longhurst, "Thermogravimetric Experiments with Titanium," EGG-FSP-9499, February 1991, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

R. W. Moir, ..., G. R. Longhurst, ..., "HYLIFE-II Progress Report," UCID-21816, December 1991, Lawrence Livermore National Laboratory, Livermore, California.

S. J. Piet, K. A. McCarthy, D. F. Holland, G. R. Longhurst, and B. J. Merrill, "Safety Characteristics of Options for Plasma-Facing Components for ITER and Beyond," Proceedings 14th Symposium on Fusion Engineering, September 30 - October 3, 1991, San Diego, California, IEEE Catalog No. 91CH3035-3, pp. 444-449.

T. J. Dolan and G. R. Longhurst, "Safety and Environmental Issues of HYLIFE-II," Fusion Technology 19 (May 1991) pp. 1392-1396.

J. M. Beeston, G. R. Longhurst, and T. Parsonage, "Beryllium Fabrication/Cost Assessment for ITER," EGG-FSP-9120, June 1990, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

R. A. Anderl, D. F. Holland, and G. R. Longhurst, "Hydrogen Transport Behavior of Metal Coatings for Plasma-Facing Components," Journal of Nuclear Materials 176 & 177 (1990) pp. 683-688.

J. M. Beeston, G. R. Longhurst, L. G. Miller, and R. A. Causey, "Gas Retention in Irradiated Beryllium," EGG-FSP-9125, October 1990, Idaho National Engineering Laboratory, Idaho Falls, Idaho.

R. A. Anderl, D. F. Holland, and G. R. Longhurst, "Hydrogen Ion-Driven Permeation in Carbonaceous Films," 8th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices, May 2-6, 1988, Julich, Federal Republic of Germany.

R. A. Anderl, G. R. Longhurst, and D. A. Struttmann, "Permeation of Deuterium Implanted into V-15Cr-5Ti," Journal of Nuclear Materials 145-147 (1987) pp. 344-347.

H. J. Reilly, G. R. Longhurst, and S. J. Piet, "Evaluating Fuel Cycle Safety for CIT," International Symposium on Fusion Reactor Blanket and Fuel Cycle Technology, October 27-29, 1986, Tokai-mura, Ibaraki-ken, Japan.