MSTD Awards
The Materials Science and Technology Division presents a variety of awards and scholarships at its biennial awards luncheon held in conjunction with the ANS Winter Meeting. The awards honor specific contributions to the literature or condition of the nuclear fuels and materials field. Information about awards nomination can be found on the ANS Honors and Awards page.
A list of awards and honorees can be found here:
Mishima Award
The Mishima Award is named in honor of Dr. Mishima Yoshitsugu, Professor Emeritus at the University of Tokyo. It is presented annually to recognize outstanding contributions in research and development on nuclear fuels and materials. More information and nomination materials may be obtained on the American Nuclear Society Honors and Awards web site.
Recent Mishima Award Recipients
| 2022 | James F. Stubbins | |
| 2021 | Robin William Grimes | |
| 2020 | Rudolph Johannes | |
| 2020 | Maria (Rudy) Konings |
Past Mishima Award Recipients
| 2019 | Yutai Katoh | |
| 2018 | Joseph Y.R. Rashid | |
| 2017 | Gary S. Was | |
| 2016 | Brian Wirth | |
| 2015 | Arthur T. Motta | |
| 2014 | Tatsuo Shikama | |
| 2012 | Lance L. Snead | |
| 2010 | Theodore M. Besmann | |
| 2009 | Louis K. Mansur | |
| 2008 | Robert E. Einziger | |
| 2007 | Steven J. Zinkle | |
| 2006 | Donald R. Olander | |
| 2005 | Everett E. Bloom | |
| 2004 | J. Stephen Herring | |
| 2002 | Gerard L. Hofman | |
| 2001 | James J. Laidler | |
| 2000 | Gary L. Rinehart | |
| 1998 | G. Robert Odette | |
| 1997 | James S. Tulenko | |
| 1996 | Ronald B. Adamson | For outstanding contributions to the development of PCI-resistant zirconium liner fuel for BWRs and to the understanding of the radiation growth, corrosion, microstructures and reliability of LWR fuel cladding. |
| 1995 | Ersel A. Evans | For outstanding achievements and inspirational leadership in the development of the nation’s nuclear fuels and materials technology. |
| 1994 | Leon C. Walters | For technical contributions illustrating the viability of metallic fuel for liquid metal cooled fast reactor applications. |
| 1993 | A. Burtron Johnson, Jr. | For meritorious contributions to the understanding of in-reactor and post-irradiation behavior of fuels and materials important to the development of the international light water reactor industry. |
| 1993 | K. Linga Murty | For outstanding contributions in understanding the deformation, creep and formability of hcp metals Zr, Ti, Mg, and their alloys; in the application of textures in predicting in-reactor cladding performance; in understanding radiation effects on the fracture behavior of nuclear reactor structural alloys and synergistic effects of radiation-induced defects and impurities. |
Special Achievement Award
The Special Achievement Award is presented to recognize an individual that has made a single and unique special achievement in the field of materials science and technology by contributing an outstanding book, an innovative concept, or an entity or product that has had significant impact on the direction or success of nuclear materials technology.
Recent Special Achievement Recipients
| 2015 | Rich Williamson and Michael Tonks | For their development of the BISON-MARMOT fuel performance codes |
| 2010 | Todd Allen and Lance Snead | For their pioneering efforts to in the creation of the Nuclear Fuels and Structural Materials for Next Generation Nuclear Reactors (NFSM) technical topical meeting |
| 2009 | David A. Petti | For his leadership in the US TRISO fuel performance project that led to greater burnups than ever previously achieved |
Past Special Achievement Recipients
| 2007 | Gary S. Was | For book entitled, Fundamentals of Radiation Materials Science, Metals and Alloys |
| 2004 | Ronald L. Klueh and Donald R. Harries | High-Chromium Ferritic and Martensitic Steels for Nuclear Applications (American Society for Testing and Materials, West Conshohocken, PA, 2001) |
| 1999 | Henri Bailly, Denise Menessierand ClaudePrunier | For editing the book entitled The Nuclear Fuel of Pressurized Water Reactors and Fast Reactors: Design and Behavior. |
| 1995 | Norbert E. Hoppe | For his significant pioneering and sustained contributions to understanding and modeling nuclear fuel rod performance and his continued development of modern fuel rod performance codes. |
| 1994 | Howard Ocken | For his significant and sustained contributions to the development of cobalt-free hardfacing alloys that match or exceed the properties of equivalent materials used in nuclear plants. |
| 1985 | J.T. Adrian Roberts | For the book Structural Materials in Nuclear Power Systems. |
| 1976 | Donald R.Olander | In recognition of his book Fundamental Aspects of Nuclear Fuel Reactor Elements. |
Outstanding Achievement Award
The Outstanding Achievement Award is presented to recognize those individuals that have made unique or sustained outstanding achievements in the field of materials science and technology contributing to the development of nuclear energy.
Recent Outstanding Achievement Recipients
| 2015 | Jeremy Busby | For his leadership in addressing materials aging problems and solutions for the US Light Water Reactor fleet |
| 2014 | Stuart Maloy | For his work on structural materials development and characterization of neutron-irradiated materials |
| 2011 | Jim Stubbins | For his notable contributions in the area of understanding mechanical properties of metals under radiation |
Past Outstanding Achievement Recipients
| 2010 | Arthur Motta | For his pioneering work on oxidation of zirconium alloys including his use of synchrotron x-rays |
| 2009 | Roger E. Stoller | For his pioneering efforts to apply computational tools to the understanding of radiation damage. |
| 2008 | Randy K. Nanstad | For his contributions to the understanding of fracture mechanisms in nuclear pressure vessel steels and cladding. |
| 2007 | Nasr M. Ghoniem | For significant and sustained contributions to the modeling of materials behavior, especially for applications in advanced nuclear systems |
| 2006 | Lou Mansur | For significant and sustained contributions to the understanding and modeling of materials behavior in nuclear systems |
| 2005 | Steven J. Zinkle | For significant and sustained contributions to the understanding of metals and ceramics materials behavior for fusion and advanced fission reactor applications. |
| 2004 | Francis A. Garner | For significant and sustained contributions to the field of structural materials behavior for nuclear fission and fusion systems |
| 2003 | Gary Was | For his significant and sustained contributions to the understanding and modeling of the relationship between microstructure development and Irradiation Assisted Stress Corrosion Cracking. |
| 2002 | Everett Bloom | For his significant and sustained contributions to the development of materials for advanced nuclear fission and fusion systems. |
| 2001 | Arden L. Bement Jr. | For his significant and sustained contributions to the understanding of materials behavior in nuclear systems and contributions and leadership in the field of materials science. |
| 2000 | Jack Carpenter | For his significant and sustained contributions to the development and application of neutron sources for the understanding of materials structure. |
| 1999 | James J. Laidler | |
| 1998 | Monroe Wechsler | |
| 1997 | R.J. Price | For his pioneering work in the characterization of silicon carbide irradiation performance and behavior for advanced fission and fusion reactors. |
| 1993 | Massoud T. Simnad | For his pioneering work in the development of uranium-zirconium hydride fuels for TRIGA reactors and of coated-particle fuels for high temperature gas cooled reactors. |
| 1993 | G. Robert Odette | For his significant and sustained contributions to the understanding and modeling of the effects of irradiation on the microstructure and mechanical behavior of structural materials for fission and fusion reactors. |
| 1988 | Leon C. Walters | For his pioneering work in irradiation creep and the development of metallic fuels for liquid metal reactors. |
| 1985 | Jack Belle | For pioneering efforts in the development of uranium oxide and thorium oxide fuels. |
| 1985 | Donald E. Thomas | For his pioneering work in the development of zircaloy. |
| 1983 | Peter Murray | For pioneering work in the development of oxide fuels for thermal and fast reactors. |
| 1981 | Maxwell D.Freshley | For his work leading to establishment of performance characteristics for urania and Pu-recycle mixed oxide thermal reactor fuels, which includes the identification of means to mitigate the deleterious effects of irradiation induced fuel densification and pellet-cladding interaction and the characterization of fission gas release, fuel thermal behavior and fuel restructuring. |
| 1979 | Charles M. Walter | For application of materials technology at EBR-II to extend EBR-II driver fuel lifetime, to enable reprocessing of 42,000 driver rods, and to enable a greater than 75% capacity factor at EBR-II over the past several years. |
| 1979 | J. Howard Kittel | For redesign of EBR-II fuel pins based on experimental observations that extended life of driver metal fuel pins to above 8% burnup. |
| 1979 | W. Nelson Beck | For experimental demonstration that swelling in metal fuels is diminished after porosity becomes interconnected and 75% of fission gas is released allowing for sodium penetration to reduce temperatures. |
| 1979 | William G. Johnston | For work providing the basis for developing new swelling resistant alloys when exposed to neutron and charged particle environments. |
| 1979 | J. Russel Hawthorne | For demonstration of improved irradiated pressure vessel steel performance by removal of copper impurity. |
| 1979 | James A. Christensen | For his work leading to the instructional chart Structural Evolution in an Irradiated Oxide Fuel Pin. |
| 1979 | Edward A. Aitken | For his work leading to the instructional chart Chemical Evolution in an Irradiated Oxide Fuel Pin. |
Literary Award
The Literary Award is intended to recognize authors that have contributed the best full-length materials-oriented paper or review article in the field of materials science and technology contributing to the development of nuclear energy.
Recent Literary Award Recipients
| 2015 | S.A. Maloy, T.A. Saleh, O. Anderoglu, T.J. Romero, G.R. Odette, T. Yamamoto, S. Li, J.I. Cole, R. Fielding | Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at 295C to 6.5 dpa, Journal of Nuclear Materials, 468 (2016) 232. |
| 2014 | M. Teague, B. Gorman, B. Miller, et al. | EBSD and TEM characterization of high burn-up mixed oxide fuel, Journal of Nuclear Materials, 444 (2014) 475. |
| 2011 | Z. Jiao, V. Shankar, G.S. Was | Phase stability in proton and heavy ion irradiated ferritic martensitic alloys, Journal of Nuclear Materials, 419 (2011) 52. |
Past Literary Award Recipients
| 2010 | J. Gan, D.D. Keiser Jr., D.M. Wachs, A.B. Robinson, B.D. Miller, T.R. Allen | Transmission electron microscopy characterization of irradiated U-7Mo/Al-2Si dispersion fuel, Journal of Nuclear Materials 396 (2010) 234. |
| 2009 | D.E. Burkes, R.S. Fielding, D.L. Porter, D.C. Crawford, M.K. Meyer | A US Perspective on Fast Reactor Fuel Fabrication Technology and Experience Part I: Metal Fuels and Assembly Design, Journal of Nuclear Materials 389 (2009) 458. |
| 2008 | Z. Jiao, G.S. Was | Localized Deformation and IASCC Initiation in Austenitic Stainless Steels, Journal of Nuclear Materials 382 (2008) 203. |
| 2007 | L.L. Snead, T. Nozawa, Y. Katoh, T.S. Byun, S. Kondo, D.A. Petti | Handbook of SiC Properties for Fuel Performance Modeling, Journal of Nuclear Materials 371 (2007) 329. |
| 2006 | T.R. Allen, J.I. Cole, C.L. Trybus, D.L. Porter, H. Tsai, F.A. Garner, E.A. Kenik, T. Yoshitake, J. Ohta | The Effect of Dose Rate on the Response of Austenitic Stainless Steels to Neutron Radiation, Journal of Nuclear Materials 348 (2006) 148. |
| 2005 | L.L. Snead, S.J. Zinkle, D.P. White | Thermal conductivity degradation of ceramic materials due to low temperature low dose neutron irradiation, Journal of Nuclear Materials 340 (2005) 187. |
| 2004 | T.S. Byun, K. Farrell | Plastic instability in polycrystalline metals after low temperature irradiation, Acta Materialia 52 (2004) 1597. |
| 2003 | G. R. Odette, T. Yamamoto, H.J. Rathbun, M.Y. He, M.L. Hribernik, J.W. Rensman | Cleavage fracture and irradiation embrittlement of fusion reactor alloys: mechanisms, multiscale models, toughness measurements and implications to structural integrity assessment, Journal of Nuclear Materials 323 (2003) 313. |
| 2002 | J.T. Busby, G.S. Was, E.A. Kenik | Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steel, Journal of Nuclear Materials 302 (2002) 20. |
| 2001 | B.D. Wirth, M.J. Caturla, T. Diaz de la Rubia, T. Khraishi, H. Zbib | Mechanical property degradation in irradiated materials: A multiscale modeling approach, Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 180 (2001) 23. |
| 2000 | T.R. Allen, E.A. Kenik, G.S. Was | Variability of Radiation-Induced Segregation in Iron-Chromium-Nickel Alloys, Journal of Nuclear Materials 278 (2000) 149. |
| 1999 | K.E. Sickafus, H. Matzke, Th. Hartmann, K. Tasuda, J.A. Valdez, P. Chodak, M. Nastasi, R.A. Verrall | Radiation Damage Effects in Zirconia, Journal of Nuclear Materials 274 (1999) 66. |
| 1998 | T.R. Allen, et al. | On the Mechanisms of Radiation-Induced Segregation in Austenitic Fe-Cr-Ni Alloys, Journal of Nuclear Materials 255 (1998) 44. |
| 1997 | B.J. Lewis, et al. | Ion Spiking Model for Pressurized Water Reactors, Journal of Nuclear Materials 244(1997) 153. |
| 1996 | J.E. Pawel, A.F. Rowcliffe, G.E. Lucas, S.J. Zinkle | Irradiation Performance of Stainless Steels for ITER Application, Journal of Nuclear Materials 239 (1996) 126. |
| 1996 | S.M. McDeavitt, A.A. Solomon | HIP of U-10Zr by a Coupled Grain Boundary Diffusion and Creep Cavitation Mechanism, Journal of Nuclear Materials 228 (1996) 184. |
| 1995 | S. Uchida, E. Ibe, K. Nakata, M. Fuse, K. Ohsumi, Y. Takashima | Application of Hydrogen Water Chemistry to Moderate Corrosive Circumstances Around the Reactor Pressure Vessel Bottom of Boiling Water Reactors, Nuclear Technology 110 (1995) 250. |
| 1994 | D.A. Petti, R.R. Hobbins, D.L. Hagerman | The Composition of Aerosols Generated During a Severe Reactor Accident: Experimental Results from the Power Burst Facility Severe Fuel Damage Test 1-4, Nuclear Technology 105 (1994) 334. |
| 1993 | D.T. Peters, K.J.A. Kundig, D.F. Medley, P.A. Enders | Multibarrier Copper-Base Containers for High-Level Waste Disposal, Nuclear Technology 104 (1993) 219. |
| 1993 | W. Goll, H.P. Fuchs, R. Manzel, F.U. Schlemmer | Irradiation Behavior of UO2/PuO2 Fuel in Light Water Reactors, Nuclear Technology 102 (1993) 29. |
| 1992 | J.H. Kittel, B.R.T. Frost, J.P. Mustelier, K.Q. Bagley, C.C. Crittenden, J. van Dievot | History of Fast Reactor Fuel Development, Journal of Nuclear Materials, 204 (1993) 1. |
| 1991 | A.A. Strasser, D.R. O’Boyle, K. Otoha, T. Kishida, S. Sandklef | Fuel for the 90’s – A Utility Perspective, Proceedings of ANS/ENS International Topical Meeting on LWR Fuel Performance, Avignon, France (1991). |
| 1990 | T.H. Bauer, A.E. Wright, W. R. Robinson, J.W. Holland, E.A. Rhodes | Behavior of Modern Metallic Fuel in TREAT Transient Overpower Tests, Nuclear Technology 92 (1990) 325. |
| 1990 | B.J. Lewis, F.C. Iglesias, D.S. Cox, E. Gheorghiu | A Model for Fission Gas Release and Fuel Oxidation Behavior for Defected UO2 Fuel Elements, Nuclear Technology 92 (1990) 353. |
| 1989 | D.A. Petti, J.P. Adams, J.L. Anderson, R.R. Hobbins | Analysis of Fission Product Release Behavior from the Three-Mile Island Unit 2 Core, Nuclear Technology 87 (1989) 243. |
| 1988 | J.L. Collins, M.F. Osborne, R.A. Lorenz, A.P. Malinauskas | Fission Product Iodine and Cesium Release Behavior Under Light Water Reactor Accident Conditions, Nuclear Technology 81 (1988) 78. |
| 1987 | M.F. Osborne, J.L. Collins, R.A. Lorenz | Experimental Studies of Fission Product Release from Commercial Light Water Reactor Fuel Under Accident Conditions, Nuclear Technology 78 (1987) 157. |
| 1987 | M.G. Adamson, W.H. Reineking, M. Kangilaski, S. Vaidyanathan | Screening Alternative LMFBR Cladding Alloys for Fission-Product Induced LME and FCCI, Proceedings of the International Conference on Fast Breeder Reactor Fuel Performance, Tucson, Arizona (1987). |
| 1986 | P.M. Scott | Stress Corrosion and Corrosion Fatigue in Water Reactor Environments – Chemical Viewpoint, Proceedings of the 2nd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, Monterey, California (1985). |
| 1986 | R.E. Einziger, R.V. Strain | Behavior of Breached Pressurized Water Reactor Spent-Fuel Rods in an Air Atmosphere Between 250 and 360C, Nuclear Technology 75 (1986) 82. |
| 1985 | J.H. Davies | Fission Product Release from Artificially Perforated Fuel Rods Operating in a Test Reactor Loop, Proceedings of Fission Product Behavior and Source Term Research Conference, Park City, Utah (1984). |
| 1985 | D.J. Osetek, A.W. Cronenberg, R.R. Hobbins, K. Vinjamuri | Fission Product Behavior During the First Two PBF Severe Fuel Damage Tests, Proceedings of Fission Product Behavior and Source Term Research Conference, Park City, Utah (1984). |
| 1983 | F. Tinti | Uniaxial In-Reactor Creep of Zircaloy-2: Stress, Flux, and Temperature Dependence, Nuclear Technology 60 (1983) 109. |
| 1983 | F.A. Garner | Recent Insights on the Swelling and Creep of Irradiated Austenitic Alloys, Journal of Nuclear Materials 122-123 (1984) 459. |
| 1982 | J.H. Davies, H.S. Rosenbaum, J.S. Armijo, E. Rosicky, E.L. Esch, S.B. Wisner | Irradiation Tests on Barrier Fuel in Support of a Large-Scale Demonstration, Proceedings of LWR Extended Burnup Fuel Performance and Utilities, Williamsburg, Virginia (1982). |
| 1981 | P.Berge, J.R. Donati | Materials Requirements for Pressurized Water Reactor Steam Generator Tubing, Nuclear Technology 55 (1981) 88. |
| 1980 | H.A. Ocken | An Improved Evaluation Model for Zircaloy Oxidation, Nuclear Technology 47 (1980) 343. |
| 1980 | W.H. Yunker | Silicon Mass Transfer in Sodium Loops and the Resulting Thermal/Hydraulic Effects, Proceedings of the 2nd International Conference on Liquid Metal Technology in Energy Production (1980). |
| 1979 | R.S. Ondrejcin, S.R. Rideout, J.A. Donovan | Control of Stress Corrosion Cracking in Storage Tanks Containing Radioactive Waste, Nuclear Technology 44 (1979) 297. |
| 1979 | J.H. Davies, J.S. Armijo, R.A. Proebstle, G.R. Parkos, R.L. Schreck, W.L. Esch, J.M. Isaacson, L.D. Noble, H.S. Rosenbaum | Power Ramp Tests of Potential PCI Remedies, Proceedings of LWR Fuel Performance, Portland, Oregon (1979). |
| 1978 | T.A. Whipple, D.L. Olson, W.L. Bradley, D.K. Matlock | Corrosion and Mechanical Behavior of Iron in Liquid Lithium, Nuclear Technology 39 (1978) 75. |
| 1977 | B.J. Wrona, J.T.A. Roberts, T.M. Galvin, G.T. Higgins | Mechanical Response of UO2 Subjected to Transient Heating, Nuclear Technology 32 (1977) 376. |
Significant Contribution Award
The Significant Contribution Award recognizes the authors that have presented the best materials-oriented paper at either the Annual or Winter ANS Meetings in the field of materials science and technology contributing to the development of nuclear energy.
Recent Significant Achievement Recipients
| 2015 | K.G. Field, Y. Yamamoto, B. Pint, R. Howard, L.L. Snead, K.A. Terrani | Current status of FeCrAl alloys as an accident tolerant cladding alloy class for commercial light water reactors, presented at the ANS Winter Meeting, November 2015 |
| 2014 | Y. Le Pape, K.G. Field, J. Busby | Degradation of concrete for nuclear structures: Identified mechanisms and knowledge gaps, presented at the ANS Annual Meeting NFSM Embedded Topical, June 2014 |
| 2011 | V.V. Rondinella, D. Staicu, C. T. Walker, S. Bremier, D. Papaioannou, T. Wiss, R.J.M. Konings | Advanced Microanalytical and Thermophysical Investigations of Irradiated Nuclear Fuel, presented at the ANS Annual Meeting, June 2011 |
Past Significant Achievement Recipients
| 2010 | Sean M. McDeavitt, M. Naramore, R. Miller, J.C. Ragusa, S.T. Revankar, A.A. Solomon, J. Malone | Introducing a High Thermal Conductivity UO2-BeO Nuclear Fuel Concept, presented at the ANS Annual Meeting, November 2010 |
| 2009 | V.V. Rondinella, H. Ohta, D. Papioannou, T. Ogata, R. Nasyrow, T. Koyama, J.-P. Glatz | Characterization of Metallic Fuel for the Transmutation of Minor Actinides in Fast Reactor, presented at the ANS Winter Meeting, November 2009 |
| 2008 | L.K. Mansur | Perspectives on Radiation Effects in High-Nickel Alloys for Applications in Advanced Reactors, presented at the ANS Annual Meeting NFSM Embedded Topical, June 2008 |
| 2007 | D. Warin, P. Brossard, J. Nabot | French R&D Program for Minor Actinide Bearing Fuel Developments, presented at GLOBAL 2007 |
| 2006 | D.C. Crawford, D.L. Porter, S.L. Hayes | Fuels for Sodium-Cooled Fast Reactors, presented at the ANS Annual Meeting NFSM Embedded Topical, June 2006 |
| 2005 | P.A. Demkowicz, D.A. Petti, J.A. Kopp | Fission Product Corrosion of Carbide and Nitride Materials, presented at the ANS Winter Meeting, November 2005 |
| 2004 | P.G. Medvedev, S.M. Frank, M.J. Lambregts, A.P. Maddison, T.P. O’Holleran, M.K. Meyer | Dual Phase Magnesia-Zirconia Ceramics for Light Water Reactor Inert Matrix Fuel, presented at the ANS Winter Meeting, November 2004 |
| 2003 | J.H. Kim, S.H. Oh, I.S. Hwang | Mitigation of primary water stress corrosion cracking by nickel-plating methodology, presented at the ANS Winter Meeting, November 2003 |
| 2002 | S.M. McDeavitt, T.J. Downar, A.A. Solomon | Cermet Fuel for the Thorium Fuel Cycle, presented at the ANS Annual Meeting, June 2002 |
| 2001 | T.W. Knight, S. Anghaie | Tri-Carbide Nuclear Fuel Processing and Characterization for Space Nuclear Applications, presented at the ANS Winter Meeting, November 2001 |
| 1999 | M.A. Pouchon, C. Degueldre, P. Tissot | Properties of Zirconia-Based Fuels for Plutonium Utilization in Reactors |
| 1999 | B.A. Hilton, R.T. Klann | Hydrogen Measurement in Cladding Material by Neutron Transmission Analysis |
| 1998 | K. Katsuyama, T. Mitsugi, T. Asaga | Evaluation of Helium Gas Release Behavior in MOX Fuel |
| 1997 | A. Cohen, D.D. Keiser | Interaction Layers Between Metal Alloy Fuel and Stainless Steel Cladding in Irradiated Fuel Elements |
| 1994 | S.K. Iskander, M.A. Sokolov, R.K.Nansted | Some Aspects of the Role of Annealing in Plant Life Extension |
| 1992 | Y.Y. Liu, H. Tsai, M.C. Billone, J.M. Kramer | Behavior of EBR-II Mk-V-Type Fuel Elements in Simulated Loss of Flow Tests |
| 1992 | K. Yamamoto, T. Hirosawa, K. Morozumi, S. Nomura | Melting Temperature and Thermal Conductivity of Irradiated (U,Pu)O2 Fuel |
| 1991 | T.C. Rowland, H.S. Rosenbaum, R. Iwasaki, M. Nakasuka, Y. Iwano, A. Maru, T. Matsumato, A.Yoshizawa | Power Cycling Operation Tests of Zr-Barrier Fuel |
| 1991 | G.E. Lucas, G.R. Odette, E. Mader | Low Temperature Hardening andEmbrittlement of Nuclear Structural Steels |
| 1990 | M.R. Elmore, E.D. Waters | Erosion-Corrosion of Waste Storage Tanks During Waste Retrieval |
| 1990 | M.S. Nagorka, C.G. Levi, G.E. Lucas | Dispersion Strengthened Cu-Y2O3 Alloys for High-Heat-Flux Applications |
| 1989 | W. Meyer and W.H. Miller | Nondestructive Analysis for Hydrogen in Steel Using Neutron Scattering |
| 1989 | P.J. Maziasz | Microstructural Evolution of Martensitic Steels During Fast Neutron Irradiation |
| 1989 | T. Nakagawa, T. Ogata, M. Tokiwai | Simulation of the Injection Casting of Metallic Fuels |
| 1988 | J.H. Bottcher, J.D.B. Lambert, R.V. Strain, S. Ukai, S. Shibahara | Fuel/Sodium Reaction Product Formation in Breached Mixed-Oxide Fuel |
| 1987 | C.J. McHargue | The Effects of Ion Implantation on the Mechanical Properties of Ceramics |
| 1987 | M.L. Grossbeck, J.A. Horak | Effect of Helium on the Irradiation Creep in an Austenitic Stainless Steel |
| 1986 | L.A. Lawrence | Fuel/Cladding Chemical Interaction Correlation for Mixed-Oxide Fuel Pins |
| 1986 | R.J. Reda, S.L. Akers, J.L. Kelly | Radiation-Enhanced Corrosion of Mild Steel |
| 1985 | M.G. Adamson, W.H. Reineking, S.Vaidyanathan | Evidence for Liquid Cesium and Tellurium-Induced Fatigue Embrittlement of Cold-Worked AISI Type 316 Stainless Steel |
| 1985 | Z. Tomczuk, D.S. Poa, W.E. Miller, R.K. Steunenberg | Electrorefining of Uranium and Plutonium from Liquid Cadmium |
| 1984 | K.T. Gillian, R.L. Clough | Kinetic Model for Extrapolation of Combined Radiation-Thermal Accelerated Aging Experiments |
| 1984 | B.R. Seidel, L.C. Walters, J.H.Kittel | Performance of Metallic Fuels in Liquid-Metal Fast Reactors |
| 1984 | T.M. Bessman, T.B. Lindemer | Thermochemical Modeling of the Plutonium and Uranium-Plutonium Dioxides |
| 1983 | H.M. Chung | Structure of High-Burnup Fuel Zircaloy Cladding |
| 1982 | S. Vaidyanathan, M.G. Adamson | Mechanisms of Fuel Adjacency Effect in LMFBR Oxide Fuel Pins |
| 1982 | E.L. Burley, T.L. Wong, R.J. Law, R.L. Cowan | Oxygen Suppression in BWR Reactor Water by Hydrogen Additions |
| 1982 | R.W. Stratton | Development of Advanced Fuels inSwitzerland |
| 1981 | R.W. Stratton, M. Nicolet, J. Reindl, K.L. Peddicord | Sphere-Pac Carbide Fuel Pin Thermal Calculations Compared with Post-Irradiation Observations |
| 1981 | F.M. Haggag, G.E. Lucas | Determination of Flow Properties of Steel from an Instrumented Hardness Test |
| 1981 | S. Vaidyanathan, M.G. Adamson | Preliminary Model for Fission Product Assisted Crack Growth in LMFBR Oxide Fuel Pin Cladding |
| 1980 | C.A. Calder, E.C. Draney, W.W. Wilcox | Noncontact Measurement of the Elastic Constants of Plutonium at Elevated Temperatures |
| 1980 | N.S. DeMuth, T.W. Latimer, R.L. Petty | Short-Term Irradiation of Carbide Fuel Elements After Sodium Bond Loss |
| 1980 | P.J. Fehrenbach, P.A. Morel, R.D. Sage | In-Reactor Measurement of Cladding Strain: Fuel Density and Relocation Effects |
| 1980 | R.P. Colburn, H.P. Maffei | Contamination Transport in the Primary Coolant System During a Breached Fuel Pin Test in EBR-II |
| 1980 | B.Z. Hyatt | Corrosion Behavior of AM-350 Stainless Steel in Light Water Reactor Coolant |
| 1979 | W. Kesternich | Helium Cavitation and Its Relation to TiCPrecipitation in an Alpha-Irradiated Stainless Steel |
| 1979 | E.R. Bradley, M.E. Cunningham, C.R. Hann, D.D. Lanning, R.E.Williford | Burnup-Dependent Fission Gas Release |
| 1979 | J.M. McKee, F.A. Smith, E.R.Koehl | Sodium Hydroxide Injections into Sodium |
| 1978 | R.J. DiMelfi, L.W. Deitrich | Modeling of the Effects of Grain-Boundary Fission Gas on Transient Fuel Behavior |
| 1978 | M. Tetenbaum, R.J. Ackerman | High-Temperature Vaporization Behavior of the ThO Phase |
| 1978 | R.L. Klueh | Microstructural Effects on Creep-Rupture Behavior of Annealed 2-Cr-1Mo Steel |
| 1978 | K.R. Thomas, T.H. van der Kaa, V.C. Dodd, D.O. Hobson | An Irradiated Capsule Design Capable of Continuously Monitoring the Creepdown of Zircaloy Fuel Cladding |
| 1978 | R.L. Klueh, J.F. King | Strain-Rate Effects on the Elevated-Temperature Behavior of ERNiCr3 Weld Metal |
| 1977 | P.J. Maziasz, E.E. Bloom | Comparison of 316 + Ti with 316 Stainless Steel Irradiated in a Simulated Fusion Environment |
| 1976 | D.S. Dutt, J.W. Weber | Fuel Column Stability in Mixed-Oxide Fuel |
| 1976 | E.C. Breahm, C.A. Culpepper | Basic Chemical Compatibility of Thorium Carbides in Cr-Fe-Ni Alloys |
| 1976 | J.T.A. Roberts, E. Smith, N. Fuhrman, D. Cubicciotti | On the Pellet-Cladding Interaction Phenomenon |
| 1975 | J.M. McKee | A Calibration System for Hydrogen Meters in Sodium |
| 1974 | T.C. Rowlan, M.O. Marlowe, R.B. Elkins | Fission Product Swelling in BWR Fuel |
| 1973 | J.A. Horak, T.H. Blewitt | Some Implications of Fast vs. Thermal Neutron Irradiation of Metals |
| 1972 | K. Farrell, R.T. King | Radiation Induced Strengthening andIntergranular Fracture in Aluminum |
| 1971 | E.A. Aitken, S.K. Evans, H.S. Rosenbaum, B.F. Rubin | Transport and Reaction of Fission Products with Stainless Steel Cladding: Out of the Pile Thermal Gradient Testing |
Past Chair Award
The Past Chair Award is presented to recognize the contributions of the past MSTD Chairs to the Division and the American Nuclear Society
Recent Past Chair Award Recipients
| 2014-2015 | Heng Ban | Utah State University |
| 2013-2014 | Bryan Chen | Auburn University |
| 2011-2012 | Heather MacLean Chichester | Idaho National Laboratory |
Past Chair Award Recipients
| 2010-2011 | Jeremy T. Busby | Oak Ridge National Laboratory |
| 2009-2010 | J. Rory Kennedy | Idaho National Laboratory |
| 2008-2009 | Jim I. Cole | Idaho National Laboratory |
| 2007-2008 | Travis W. Knight | University of South Carolina |
| 2006-2007 | Robert J. Hanrahan, Jr. | Los Alamos National Laboratory |
| 2005-2006 | Ron Ballinger | Massachusetts Institute of Technology |
| 2004-2005 | Todd Allen | University of Wisconsin |
| 2003-2004 | Ken Chidester | Los Alamos National Laboratory |
| 2002-2003 | Jim Stubbins | University of Illinois-Urbana-Champaign |
| 2001-2002 | Carl Beyer | Pacific Northwest National Laboratory |
| 2000-2001 | Samim Anghaie | University of Florida |
| 1999-2000 | David J. Senor | Pacific Northwest National Laboratory |
| 1998-99 | James Tulenko | University of Florida |
| 1997-98 | Doug C. Crawford | Argonne National Laboratory-West |
| 1996-97 | Mitch E. Cunningham | Pacific Northwest National Laboratory |
| 1995-96 | John D. Lambert | Argonne National Laboratory |
| 1994-95 | Jerry L. Ethridge | Pacific Northwest National Laboratory |
| 1993-94 | Thomas T. Claudson | Pacific Northwest National Laboratory |
| 1992-93 | Glenn E. Lucas | |
| 1991-92 | Bobby R. Seidel | Argonne National Laboratory-West |
| 1990-91 | Anthony J. Romano | |
| 1989-90 | J.T. Adrian Roberts | |
| 1988-89 | Martin L. Grossbeck | Oak Ridge National Laboratory |
| 1987-88 | K.L. Peddicord | Texas A&M University |
| 1986-87 | Leo A. Lawrence | |
| 1985-86 | Martyn G. Adamson | |
| 1984-85 | Leon C. Walters | Argonne National Laboratory-West |
| 1983-84 | J. Read Holland | |
| 1982-83 | Sidney Langer | |
| 1981-82 | Edward A. Aitken | |
| 1980-81 | Robert D. Leggett | |
| 1979-80 | Donald E. Thomas | |
| 1978-79 | James A. Horak | Oak Ridge National Laboratory |
| 1977-78 | Owen L. Kruger | |
| 1976-77 | James L. Scott | |
| 1975-76 | Harry Pearlman | |
| 1974-75 | Richard E. Skavdahl | |
| 1973-74 | John E. Cunningham | |
| 1972-73 | Melvin L. Bleiberg | |
| 1971-72 | J. Howard Kittel | |
| 1970-71 | Jack G. Conner | |
| 1969-70 | Don R. DeHalas | |
| 1968-69 | Thomas J. Pashos | |
| 1967-68 | Warren R. Grimes | |
| 1966-67 | Stan J. Paprocki | |
| 1965-66 | Merrill J. Whitman | |
| 1964-65 | Walter G. Baxter | |
| 1963-64 | James F. Schumar |
25 Year Award
The 25 Year Award is presented to recognize MSTD members that have been ANS members for 25 years and have served in the field of materials science and technology contributing to the development of nuclear energy
| 1995 | D.R. Olander | |
| 1994 | E.E. Bloom | |
| 1993 | James F. Schumar | |
| 1993 | J. Howard Kittel | |
| 1993 | Ersel A. Evans |
Student Literary Award
The Student Literary Award is presented to recognize the student that has presented the best full-length materials-oriented paper contributing to the development of nuclear energy at the Annual or Winter ANS Meeting, and subsequently submitted a full paper for publication in Nuclear Technology or other ANS journal.
Recent Student Literary Award Recipients
| 2015 | David Frazer | Localized mechanical property assessment of SiC/SiC composite materials (Composites A 70 (2015) 93) |
| 2015 | Elizabeth Getto | Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys (J Nucl Mater 465 (2015) 116) |
| 2014 | Yinbin Miao | The evolution mechanism of the dislocation loops in irradiated lanthanum doped cerium oxide (J Nucl Mater 445 (2014) 209) |
Past Student Literary Award Recipients
| 2010 | Elaine A. West | Influence of Microstructural Parameters on the Intergranular Cracking of Irradiated 316L Stainless Steel in Supercritical Water |
| 2009 | Elaine A. West | Influence of Taylor Factor on IASCC in SCW and Simulated BWR Environments, E.A. West, Z. Jiao, G.S. Was (University of Michigan), presented at Env Deg 2009. |
| 2008 | Peter Hosemann | Micro Mechanic Testing and Local Electrode Atom Probe Microscope (LEAP) Measurements on Oxide Dispersed Strengthened (ODS) Alloys, P. Hosemann (LANL, University of Leoben), E. Stergar(University of Leoben), C. Vieh (LANL/University of Leoben), R.R. Greco, M.J. Cappiello, S.A. Maloy(LANL), NSFM 2008. |
| 2007 | Gokul Vasudevamurthy | Production of ZrC Matrix for Use in Gas Fast Reactor Composite Fuels, Gokul Vasudevamurthy, Travis W. Knight, Elwyn Roberts, and Thad Adams, presented at GLOBAL 2007 and subsequently published in the Journal of Nuclear Materials, 347, 1-2 (2008) 241-247 |
| 2006 | Xianglin Wu | An EBSD Investigation on Flow Localization of 316L Stainless Steel, X. Wu, X. Pan, J. C. Mabon, M. Li, and J. F. Stubbins, presented at the Embedded Topical on Fuels and Structural Materials for Advanced Reactor Systems at the ANS Annual Meeting, June 2006, and subsequently published in the Journal of Nuclear Materials, 371, 1-3 (2007) 90-97 |
| 2004 | Xianglin Wu | X. Wu, X. Pan, M. Li, and J. Stubbins, Flow localization modeling for face-centered cubic (FCC) metals after exposure to radiation, presented at the ANS 2004 Winter Meeting followed by full papers inJournal Nuclear Materials and ASTM JAI |
| 2003 | Alan M. Bolind, J. F. Stubbins | The use of impedance spectroscopy to measure corrosion in lead-bismuth systems in ANS AccAppProc 2003 p.849 |
| 1999 | M. Barnett, R.K. Corzine | Calculations of Radiation Damage at SNS |
| 1992 | P.C. Tortorici, M.A. Dayananda | Interdiffusion of Cerium in Fe-Ni-Cr Alloys |
| 1985 | D. Sherman | Hydrogen Retention and Release from UO2 |
| 1982 | M.P. Manahan | A New Post-Irradiation Mechanical Behavior Test – The Miniaturized Disk Bend Test |
| 1981 | K.C. Kim | Oxygen Diffusion in UO2-x |
Schumar Scholarship
The Schumar Scholarship is named in honor of the first Chair of the MSTD, and comprises a minimum award of $1000 presented to encourage graduate students to pursue academic excellence and make significant contributions to the field of materials science and technology advancing the development of nuclear energy. More information and application materials may be obtained at the American Nuclear Society Scholarship web site.
Recent Schumar Scholarship Award Recipients
| 2022 | William Searight | Pennsylvania State University |
| 2020 | Pierre-Clément A. Simon | Pennsylvania State University |
| 2012 | William Sames | Texas A&M University |
Past Schumar Scholarship Award Recipients
| 2011 | Lindsey Anne Gilman | Massachusetts Institute of Technology |
| 2010 | Jeffrey Powers | University of California, Berkeley |
| 2009 | Azaree Tresong Lintereur | University of Florida |
| 2008 | Sarah Khalil | University of Wisconsin |
| 2007 | Kurt Terrani | University of California |
| 2006 | Maria A. Okuniewski | University of Illinois-Urbana-Champaign |
| 2005 | Micah Hackett | University of Michigan |
| 2004 | Candice C. Scheffing | North Carolina State |
| 2003 | Julie Dehn Tucker | University of Wisconsin |
| 2002 | Jason Dirk Haverkamp | North Carolina State University |
| 2001 | Heather Jean MacLean | Massachusetts Institute of Technology |
| 2000 | Heather Jean MacLean | Massachusetts Institute of Technology |
| 1999 | Robert M. Miller | Purdue University |
| 1998 | Brent Matthew Capell | University of Michigan |
| 1997 | Grayden S. Uyeda Jr. | Oregon State University |
| 1996 | Ehsan Samei | University of Michigan |
| 1995 | Piero U. Simoni | University of Virginia |
| 1994 | Ian S. Hamilton | Texas A&M University |
| 1993 | Shara S. Shoup | University of Tennessee |
| 1992 | Abdul R. Dulloo | Pennsylvania State University |
| 1991 | Paula D. Freyer | Pennsylvania State University |
| 1990 | James M. Adams | Pennsylvania State University |
| 1989 | William S.L. Boyer | University of Michigan |
| 1988 | Douglas C. Crawford | University of Michigan |
| 1987 | John D. Demaree | University of Michigan |
| 1986 | Dale E. Alexander | University of Michigan |
| 1985 | Mark C. Petri | Purdue University |
| 1984 | Richard W. Smith | University of Michigan |