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Honors and 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. The
awards, selection criteria, and past recipients are listed below for all
awards presented through at least the 2006 ANS Winter Meeting. If you are
interested in serving on the MSTD Honors and Awards Committee or in
nominating a candidate for an award, please contact Jim Stubbins, MSTD Honors and Awards
Committee Chair.
· Mishima
Award
· Special Achievement Award
· Outstanding Achievement
Award
· Literary Award
· Significant Contribution
Award
· Past Chair Award
· 25 Year Award
· Student Literary Award
· Schumar
Scholarship
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Mishima Award
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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.
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2007
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Steven J. Zinkle
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2006
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Donald R. Olander
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2005
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Everett E.
Bloom
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2004
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J. Stephen Herring
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2002
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Gerard L. Hofman
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2001
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James J. Laidler
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2000
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Gary L. Rinehart
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1998
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G. Robert Odette
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1997
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James S. Tulenko
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1996
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Ronald B. Adamson
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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.
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1995
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Ersel A. Evans
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For outstanding achievements and inspirational
leadership in the development of the nation's nuclear fuels and materials
technology.
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1994
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Leon C. Walters
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For technical contributions illustrating the viability
of metallic fuel for liquid metal cooled fast reactor applications.
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1993
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A. Burtron Johnson, Jr.
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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.
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1993
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K. Linga Murty
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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.
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Special Achievement Award
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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.
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2004
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Ronald L. Klueh and Donald
R. Harries
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High-Chromium Ferritic and Martensitic
Steels for Nuclear Applications (American Society for Testing and
Materials, West Conshohocken, PA, 2001)
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1999
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Henri Bailly, Denise Menessier and Claude Prunier
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For editing the book entitled The Nuclear Fuel of
Pressurized Water Reactors and Fast Reactors: Design and Behavior.
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1995
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Norbert E. Hoppe
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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.
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1994
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Howard Ocken
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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.
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1985
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J.T. Adrian Roberts
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For the book Structural Materials in Nuclear Power
Systems.
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1976
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Donald R. Olander
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In recognition of his book Fundamental Aspects of Nuclear
Fuel Reactor Elements.
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Outstanding Achievement Award
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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.
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2005
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Steven
J. Zinkle
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For
significant and sustained contributions to the understanding of metals
and ceramics materials behavior for fusion and advanced fission reactor
applications.
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2004
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Francis
A. Garner
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For
significant and sustained contributions to the field of structural
materials behavior for nuclear fission and fusion systems
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2003
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Gary Was
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For his significant and sustained contributions to the
understanding and modeling of the relationship between microstructure
development and Irradiation Assisted Stress Corrosion Cracking.
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2002
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Everett
Bloom
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For his significant and sustained contributions to the
development of materials for advanced nuclear fission and fusion systems.
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2001
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Arden L. Bement Jr.
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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.
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2000
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Jack Carpenter
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For his significant and sustained contributions to the
development and application of neutron sources for the understanding of
materials structure.
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1999
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James J. Laidler
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1998
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Monroe
Wechsler
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1997
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R.J. Price
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For his pioneering work in the characterization of
silicon carbide irradiation performance and behavior for advanced fission
and fusion reactors.
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1993
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Massoud T. Simnad
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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.
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1993
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G. Robert Odette
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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.
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1988
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Leon C. Walters
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For his pioneering work in irradiation creep and the
development of metallic fuels for liquid metal reactors.
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1985
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Jack Belle
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For pioneering efforts in the development of uranium
oxide and thorium oxide fuels.
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1985
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Donald E. Thomas
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For his pioneering work in the development of zircaloy.
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1983
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Peter Murray
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For pioneering work in the development of oxide fuels for
thermal and fast reactors.
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1981
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Maxwell D. Freshley
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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.
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1979
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Charles M. Walter
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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.
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1979
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J. Howard Kittel
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For redesign of EBR-II fuel pins based on experimental
observations that extended life of driver metal fuel pins to above 8%
burnup.
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1979
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W. Nelson Beck
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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.
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1979
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William G. Johnston
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For work providing the basis for developing new
swelling resistant alloys when exposed to neutron and charged particle environments.
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1979
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J. Russel Hawthorne
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For demonstration of improved irradiated pressure
vessel steel performance by removal of copper impurity.
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1979
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James A. Christensen
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For his work leading to the instructional chart Structural
Evolution in an Irradiated Oxide Fuel Pin.
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1979
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Edward A. Aitken
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For his work leading to the instructional chart Chemical
Evolution in an Irradiated Oxide Fuel Pin.
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Literary Award
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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.
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2005
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Lance L. Snead
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L.L. Snead, S. J. Zinkle,
and D. P. White, “Thermal conductivity degradation of ceramic materials
due to low temperature low dose neutron irradiation”, Journal of Nuclear Materials, 340
(2005) 187-202
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2004
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Thak Sang Byun
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T. S. Byun and K. Farrell, “Plastic
instability in polycrystalline metals after low temperature irradiation,”
Acta Materialia,
52 (2004) 1597-1608
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2003
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G. R. Odette, T. Yamamotoa,
H. J. Rathbuna, M. Y. Hea,
M. L. Hribernika and J. W. Rensman
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“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
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2002
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Jeremy T. Busby, G. S. Was, E. A. Kenik
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“Isolating the effect of radiation-induced segregation
in irradiation-assisted stress corrosion cracking of austenitic stainless
steel”, Journal of Nuclear
Materials, 302 (2002) 20
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2001
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Brian Wirth, M. J. Caturla,
T. Diaz de la Rubia, T. Khraishi
and H. Zbib
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“Mechanical property degradation in irradiated
materials: A multiscale modeling approach” in
Nuclear Instruments and Methods in Physics Research Section B: Beam
Interactions with Materials and Atoms Volume 180, Issues 1-4(2001) 23-31
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2000
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Todd R. Allen, E. A. Kenik, and G.S. Was
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"Variability of
Radiation-Induced Segregation in Iron-Chromium-Nickel Alloys," J. Nucl.
Mater. 278 (2000) 149-163.
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1999
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K.E. Sickafus, Hj. Matzke, Th. Hartmann,
K. Tasuda, J.A. Valdez, P. Chodak,
M. Natasi, R.A. Verrall
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"Radiation Damage Effects in Zirconia," J.
Nucl. Mater. 274:66 (1999)
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1998
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T.R. Allen,
et al.
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"On the Mechanisms of Radiation-Induced
Segregation in Austenitic Fe-Cr-Ni Alloys," J. Nucl. Mater., 255:44 (1998)
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1997
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B.J. Lewis,
et al.
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"Ion Spiking Model for Pressurized Water
Reactors," J. Nucl. Mater., 244:153
(1997)
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1996
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J.E. Pawel, A.F. Rowcliffe, G.E. Lucas, S.J. Zinkle
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"Irradiation Performance of Stainless Steels for
ITER Application," J. Nucl. Mater.,
239:126 (1996)
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1996
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S.M. McDeavitt, A.A. Solomon
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"HIP of U-10Zr by a Coupled Grain Boundary
Diffusion and Creep Cavitation Mechanism," J. Nucl.
Mater., 228:184 (1996)
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1995
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S. Uchida,
E. Ibe, K. Nakata, M. Fuse, K. Ohsumi, Y. Takashima
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"Application of Hydrogen Water Chemistry to
Moderate Corrosive Circumstances Around the Reactor Pressure Vessel
Bottom of Boiling Water Reactors," Nucl.
Tech., 110, 2 (1995) 250-257
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1994
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D.A. Petti, R.R. Hobbins, D.L. Hagrman
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"The Composition of Aerosols Generated During a
Severe Reactor Accident: Experimental Results from the Power Burst
Facility Severe Fuel Damage Test 1-4," Nucl.
Tech., 105, (1994) 334-345
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1993
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D.T. Peters, K.J. A. Kundig,
D.F. Medley, P.A. Enders
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"Multibarrier
Copper-Base Containers for High-Level Waste Disposal," Nucl. Tech., 104, 2 (1993) 219-232
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1993
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W. Goll, H.P. Fuchs, R. Manzel, F.U. Schlemmer
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"Irradiation Behavior of UO2/PuO2
Fuel in Light Water Reactors," Nucl.
Tech., 102, 1 (1993) 29-46
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1992
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J.H. Kittel, B.R.T. Frost,
J.P. Mustelier, K.Q. Bagley, C.C. Crittenden,
J. van Dievot
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"History of Fast Reactor Fuel Development," J.
Nucl. Mater., 204:1 (1993)
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1991
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A.A. Strasser, D.R. O'Boyle,
K. Otoha, T. Kishida,
S. Sandklef
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"Fuel for the 90's--A Utility Perspective," Proc.
ANS/ENS International Topical Meeting on LWR Fuel Performance, Avignon,
France (1991)
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1990
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T.H. Bauer, A.E. Wright, W. R. Robinson, J.W. Holland,
E.A. Rhodes
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"Behavior of Modern Metallic Fuel in TREAT
Transient Overpower Tests," Nucl.
Tech., 92:325 (1990)
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1990
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B.J. Lewis, F.C. Iglesias,
D.S. Cox, E. Gheorghiu
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"A Model for Fission Gas Release and Fuel
Oxidation Behavior for Defected UO2
Fuel Elements," Nucl. Tech.,
92:353 (1990)
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1989
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D.A. Petti, J.P. Adams, J.L.
Anderson, R.R. Hobbins
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"Analysis of Fission Product Release Behavior
from the Three-Mile Island
Unit 2 Core," Nucl. Tech.,
87:243 (1989)
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1988
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J.L. Collins, M.F. Osborne, R.A. Lorenz, A.P. Malinauskas
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"Fission Product Iodine and Cesium Release
Behavior Under Light Water Reactor Accident Conditions," Nucl. Tech., 81:78 (1988)
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1987
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M.F. Osborne, J.L. Collins, R.A. Lorenz
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"Experimental Studies of Fission Product Release
from Commercial Light Water Reactor Fuel Under Accident Conditions,"
Nucl. Tech. 78:157 (1987)
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1987
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M.G. Adamson, W.H. Reineking,
M. Kangilaski, S. Vaidyanathan
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"Screening Alternative LMFBR Cladding Alloys for
Fission-Product Induced LME and FCCI," Proc. Intl. Conf. on Fast
Breeder Reactor Fuel Performance, Tucson,
Arizona (1987)
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1986
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P.M. Scott
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"Stress Corrosion and Corrosion Fatigue in Water
Reactor Environments - Chemical Viewpoint," Proc. Second Intl. Symp. Environmental Degradation of Materials in
Nuclear Power Systems, Monterey, CA
(1985)
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1986
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R.E. Einziger, R.V. Strain
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"Behavior of Breached Pressurized Water Reactor
Spent-Fuel Rods in an Air Atmosphere Between 250 and 360 C," Nucl. Tech., 75:82 (1986)
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1985
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J.H. Davies
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"Fission Product Release from Artificially
Perforated Fuel Rods Operating in a Test Reactor Loop,"
Proc. Fission Product Behavior and Source Term Research Conference,
Park City, UT
(1984)
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1985
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D.J. Osetek, A.W. Cronenberg, R.R. Hobbins,
K. Vinjamuri
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"Fission Product Behavior During the First Two
PBF Severe Fuel Damage Tests," Proc. Fission Product Behavior and
Source Term Research Conference, Park City,
UT (1984)
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1983
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F. Tinti
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"Uniaxial In-Reactor
Creep of Zircaloy-2: Stress, Flux, and Temperature Dependence," Nucl. Tech., 60:109 (1983)
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1983
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F.A. Garner
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"Recent Insights on the Swelling and Creep of
Irradiated Austenitic Alloys," J. Nucl.
Mater., 122-123:459 (1984)
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1982
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J.H. Davies, H.S. Rosenbaum, J.S. Armijo, E. Rosicky, E.L. Esch, S.B.
Wisner
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"Irradiation Tests on Barrier Fuel in Support of
a Large-Scale Demonstration," Proc. LWR Extended Burnup Fuel
Performance and Utilities, Williamsburg,
VA (1982)
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1981
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P.Berge,
J.R. Donati
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"Materials Requirements for Pressurized Water
Reactor Steam Generator Tubing," Nucl.
Tech., 55:88 (1981)
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1980
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H.A. Ocken
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"An Improved Evaluation Model for Zircaloy
Oxidation," Nucl. Tech.,
47:343 (1980)
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1980
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W.H. Yunker
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"Silicon Mass Transfer in Sodium Loops and the
Resulting Thermal/Hydraulic Effects," Proc. Second Intl. Conf.
Liquid Metal Technology in Energy Production (1980)
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1979
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R.S. Ondrejcin, S.R.
Rideout, J.A. Donovan
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"Control of Stress Corrosion Cracking in Storage
Tanks Containing Radioactive Waste," Nucl.
Tech., 44:297 (1979)
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1979
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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
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"Power Ramp Tests of Potential PCI
Remedies," Proc. LWR Fuel Performance, Portland,
OR (1979)
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1978
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T.A. Whipple, D.L. Olson, W.L. Bradley, D.K. Matlock
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"Corrosion and Mechanical Behavior of Iron in
Liquid Lithium," Nucl. Tech.,
39:75 (1978)
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1977
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B.J. Wrona, J.T.A. Roberts,
T.M. Galvin, G.T. Higgins
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"Mechanical Response of UO2 Subjected to Transient Heating," Nucl. Tech., 32:376 (1977)
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Significant Contribution Award
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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.
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2005
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Paul A. Demkowicz
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P. A. Demkowicz, D. A. Petti, J. A. Kopp, “Fission Product Corrosion of
Carbide and Nitride Materials”, ANS
2005 Winter Meeting
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2004
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Pavel G. Medvedev
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P. G. Medvedv, S. M. Frank,
M. J. Lambregts, A. P. Maddison,
T. P. O’Holleran, and M. K. Meyer, “Dual Phase Magnesia-Zirconia
Ceramics for Light Water Reactor Inert Matrix Fuel”, ANS 2004 Winter Meeting
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2003
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Ji Hyun Kim, Si-hyoung
Oh and Il Soon Hwang
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“Mitigation
of primary water stress corrosion cracking by nickel-plating methodology”
at the ANS Winter Meeting in 2003 (ANS Trans Vol
89 )
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2002
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Sean M. McDeavitt, T.
J. Downar, A. A. Solomon
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“Cermet Fuel for the Thorium Fuel Cycle” at the ANS
Annual Meeting in
2002 (ANS Trans Vol 86)
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2001
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Travis W. Knight, Samim
Anghaie
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“Tri-Carbide Nuclear
Fuel Processing and Characterization for Space Nuclear Applications” at
the ANS Winter Meeting in 2001 (ANS Trans Vol
85)
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1999
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M.A. Pouchon, C. Degueldre, P.
Tissot
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Properties of Zirconia-Based Fuels for Plutonium
Utilization in Reactors
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1999
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B.A. Hilton, R.T. Klann
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Hydrogen Measurement in Cladding Material by
Neutron Transmission Analysis
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1998
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K.
Katsuyama, T. Mitsugi, T. Asaga
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Evaluation of Helium Gas Release Behavior in MOX
Fuel
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1997
|
A. Cohen, D.D. Keiser
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Interaction Layers Between Metal Alloy Fuel and
Stainless Steel Cladding in Irradiated Fuel Elements
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1994
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S.K. Iskander, M.A. Sokolov, R.K. Nansted
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Some Aspects of the Role of Annealing
in Plant Life Extension
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1992
|
Y.Y. Liu, H. Tsai, M.C. Billone,
J.M. Kramer
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Behavior of EBR-II Mk-V-Type Fuel Elements in
Simulated Loss of Flow Tests
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1992
|
K.
Yamamoto, T. Hirosawa, K. Morozumi, S. Nomura
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Melting Temperature and Thermal Conductivity of
Irradiated (U,Pu)O2 Fuel
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1991
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T.C. Rowland, H.S. Rosenbaum, R. Iwasaki, M. Nakasuka, Y. Iwano, A. Maru, T. Matsumato, A. Yoshizawa
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Power Cycling Operation Tests of Zr-Barrier Fuel
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1991
|
G.E. Lucas, G.R. Odette, E. Mader
|
Low Temperature Hardening and Embrittlement of Nuclear
Structural Steels
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1990
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M.R. Elmore, E.D. Waters
|
Erosion-Corrosion of Waste Storage Tanks During
Waste Retrieval
|
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1990
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M.S.
Nagorka, C.G. Levi, G.E. Lucas
|
Dispersion Strengthened Cu-Y2O3 Alloys
for High-Heat-Flux Applications
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1989
|
W. Meyer and W.H. Miller
|
Nondestructive Analysis for Hydrogen in Steel
Using Neutron Scattering
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1989
|
P.J. Maziasz
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Microstructural Evolution of Martensitic
Steels During Fast Neutron Irradiation
|
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1989
|
T.
Nakagawa, T. Ogata, M. Tokiwai
|
Simulation of the Injection Casting of Metallic
Fuels
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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
|
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1987
|
C.J. McHargue
|
The Effects of Ion Implantation on the Mechanical
Properties of Ceramics
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1987
|
M.L. Grossbeck, J.A. Horak
|
Effect of Helium on the Irradiation Creep in an
Austenitic Stainless Steel
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1986
|
L.A. Lawrence
|
Fuel/Cladding Chemical Interaction Correlation for
Mixed-Oxide Fuel Pins
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1986
|
R.J. Reda, S.L. Akers, J.L.
Kelly
|
Radiation-Enhanced Corrosion of Mild Steel
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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
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1985
|
Z. Tomczuk, D.S. Poa, W.E. Miller, R.K. Steunenberg
|
Electrorefining of
Uranium and Plutonium from Liquid Cadmium
|
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1984
|
K.T. Gillian, R.L. Clough
|
Kinetic Model for Extrapolation of Combined
Radiation-Thermal Accelerated Aging Experiments
|
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1984
|
B.R. Seidel, L.C. Walters,
J.H. Kittel
|
Performance of Metallic Fuels in Liquid-Metal Fast
Reactors
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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
|
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1982
|
S. Vaidyanathan, M.G.
Adamson
|
Mechanisms of Fuel Adjacency Effect in LMFBR Oxide
Fuel Pins
|
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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 in Switzerland
|
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1981
|
R.W. Stratton,
M. Nicolet, J. Reindl, K.L. Peddicord
|
Sphere-Pac Carbide Fuel Pin Thermal Calculations
Compared with Post-Irradiation Observations
|
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1981
|
F.M.
Haggag, G.E. Lucas
|
Determination of Flow Properties of Steel from an
Instrumented Hardness Test
|
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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
|
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1980 | | |