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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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2010
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Theodore M. Besmann
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2009
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Louis K. Mansur
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2008
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Robert E. Einziger
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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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2009
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David A. Petti
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For his leadership in the US TRISO fuel performance
project that led to greater burnups than ever previously achieved
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2007
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Gary Was
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For book entitled,
Fundamentals of Radiation Materials Science, Metals and Alloys
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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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2009
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Roger
E. Stoller
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For
his pioneering efforts to apply computational tools to the understanding
of radiation damage.
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2008
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Randy
K. Nanstad
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For
his contributions to the understanding of fracture mechanisms in nuclear
pressure vessel steels and cladding.
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2007
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Nasr M. Ghoniem
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For significant and
sustained contributions to the modeling of materials behavior, especially
for applications in advanced nuclear systems
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2006
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Lou Mansur
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For significant and
sustained contributions to the understanding and modeling of materials
behavior in nuclear systems
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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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2009
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Douglas E. Burkes, Randall S. Fielding, Douglas L.
Porter, Douglas C. Crawford, Mitchell K. Meyer
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“A US Perspective on Fast Reactor Fuel Fabrication
Technology and Experience Part I: Metal Fuels and Assembly Design,” Journal of Nuclear Materials 389,
Issue 3 (1 June 2009) Pages 458-469.
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2008
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Z. Jiao, G.S. Was
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“Localized Deformation and IASCC Initiation in
Austenitic Stainless Steels,” Journal
of Nuclear Materials 382, Issues 2-3, (1 December 2008) Pages 203-209
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2007
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Lance L. Snead
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“Handbook of SiC
Properties for Fuel Performance Modeling,” Lance L. Snead, Takashi
Nozawa, Yutai Katoh, Thak-Sang Byun, Sosuke Kondo, and David A. Petti, Journal of Nuclear Materials 371,
1-3 (2007) 329-377
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2006
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Todd R. Allen
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“The Effect of Dose Rate
on the Response of Austenitic Stainless Steels to Neutron Radiation,” T.
R. Allen, J. I. Cole, CL. Trybus, D. L. Porter, H. Tsai, F. A. Garner, E.
A. Kenik, T. Yoshitake, and J. Ohta, Journal
of Nuclear Materials 348, 1-2 (2006) 148-164
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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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2009
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Vincenzo V. Rondinella (ITU)
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for the presentation, “Characterization of Metallic
Fuel for the Transmutation of Minor Actinides in Fast Reactor,” V.V.
Rondinella (Institute for Transuranium Elements), H. Ohta (CRIEPI-Japan),
D. Papaioannou (Institute for Transuranium Elements), T. Ogata
(CRIEPI-Japan), R. Nasyrow (Institute for Transuranium Elements), T.
Koyama (CRIEPI-Japan), J.-P. Glatz (Institute for Transuranium Elements),
presented at the ANS 2009 Winter Meeting.
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2008
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Lou K. Mansur (ORNL)
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for the presentation, “Perspectives on Radiation
Effects in High-Nickel Alloys for Applications in Advanced Reactors,”
presented at NFSM 2008.
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2007
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Dominique Warin
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“French R&D Program
for Minor Actinide Bearing Fuel Developments,” D. Warin, P. Brossard, and
J. Nabot, presented at GLOBAL 2007
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2006
|
Douglas C. Crawford
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“Fuels for
Sodium-Cooled Fast Reactors,” D. C. Crawford, D. L. Porter, S. L. Hayes
(INL), presented at the 2006 Embedded Topical on Fuels and Structural Materials
for Advanced Reactor Systems
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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
|
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
|
M.A. Pouchon,
C. Degueldre, P. Tissot
|
Properties of Zirconia-Based Fuels for Plutonium
Utilization in Reactors
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1999
|
B.A. Hilton, R.T. Klann
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Hydrogen Measurement in Cladding Material by
Neutron Transmission Analysis
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1998
|
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
|
Interaction Layers Between Metal Alloy Fuel and
Stainless Steel Cladding in Irradiated Fuel Elements
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1994
|
S.K. Iskander, M.A. Sokolov, R.K. Nansted
|
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
|
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
|
Melting Temperature and Thermal Conductivity of
Irradiated (U,Pu)O2 Fuel
|
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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
|
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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
|
M.R. Elmore, E.D. Waters
|
Erosion-Corrosion of Waste Storage Tanks During Waste
Retrieval
|
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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
|
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1989
|
P.J. Maziasz
|
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
|
|
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 in Switzerland
|
|
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 TiC
Precipitation 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 and Intergranular
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
|
|
|
|
|
|
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.
|
|
|
|
|
|
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 in Journal 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
AccApp Proc 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.
|
|
|
|
|
|
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
|
|
|
|
|
|
|
|
|