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C.N. Spalaris
Observed names:
C Spalaris,
C. N. Spalaris,
C. Spalaris,
Spalaris, C N; Ring, P J; Wright, E A,
Spalaris, C. N.,
Spalaris, C.N.
show all 6
Observed institutions:
Oregon State University,
General Electric (United States)
OpenAlex ID:
A5038371872
Surface Properties of Irradiated Graphite
1957
·
C. N. Spalaris
, L. P. Bupp
, et al.
·
The Journal of Physical Chemistry
·
31
Irradiation temperature dependence of void formation in type-304 stainless steel
1972
·
D.W. Sandusky
, C.N. Spalaris
, et al.
·
Journal of Nuclear Materials
·
17
The Micropore Structure of Artificial Graphite
1956
·
C. N. Spalaris
·
The Journal of Physical Chemistry
·
16
Design of the Clinch River Breeder Reactor Plant steam generators
1976
·
J.C. Whipple
, C.N. Spalaris
·
Nuclear Technology
·
9
Sourcebook for chemical decontamination of nuclear power plants
1989
·
C.J. Wood
, C.N. Spalaris
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
8
Fuel Irradiations in the Esade-vbwr Nuclear Superheat Loop
1965
·
V.E. Hazel
, R.F. Boyle
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
7
Effect of Temperature and Burnup on Fission Gas Release in Mixed Oxide Fuel.
1969
·
W.E. Baily
, C.N. Spalaris
, et al.
·
5
Finding a Corrosion-resistant Cladding for Superheater Fuels
1963
·
C.N. Spalaris
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
5
Fabrication and inspection development for Clinch River Breeder Reactor Plant steam generators
1976
·
R.W. McClung
, G.M. Slaughter
, et al.
·
Nuclear Technology
·
4
Comparison of Radiation Damage Studies and Fuel Cladding Performance for lncoloy-800
1969
·
F. A. Comprelli
, H. J. Busboom
, et al.
·
4
Tensile Properties of Fuel Clad Materials Irradiated in Superheat Environments
1964
·
F.A. Comprelli
, B.C. Beaudreau
, et al.
·
Transactions of the American Nuclear Society
·
4
Oxide Fuel Fabrication and Performance
1964
·
S. Naymark
, C.N. Spalaris
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
Residual and Fission Gas Release From Uranium Dioxide
1963
·
C Spalaris
, F Megerth
·
3
PDF
Design, Fabrication, and Irradiation of Superheat Fuel Element SH-4B in VBWR
1961
·
C.N. Spalaris
, R. F. Boyle
, et al.
·
3
Mechanical Behavior of Cold-worked Nuclear Grade Zircaloy-2 Tubing
1960
·
H.H. Klepfer
, C.N. Spalaris
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
Adsorption of water vapor by unsupported organic films
1959
·
W. H. Slabaugh
, C. N. Spalaris
, et al.
·
Journal of Applied Polymer Science
·
3
Some Aspects of Materials Development for Sodium-Heated Steam Generators
1981
·
Prodyot Roy
, C. N. Spalaris
·
Nuclear Technology
·
2
PDF
Materials selection and expected performance in near term LMFBR steam generators
1974
·
J. S. Armijo
, J. L. Krankota
, et al.
·
Emerald Group Publishing Limited eBooks
·
2
Radiation Damage in Incoloy-800
1966
·
H. J. Busboom
, F. A. Comprelli
, et al.
·
Nuclear Applications
·
2
Hydrogen Movement in Zircaloy-2 Under Thermal Gradients
1960
·
C. N. Spalaris
, A. E. Pickett
, et al.
·
Nuclear Science and Engineering
·
2
Electropolishing process development for PWR steam generator channel heads
1991
·
R.H. Asay
, P. Graves
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
1
Fabrication Technology–Liquid-Metal Fast Breeder Reactor Steam Generators
1981
·
C. N. Spalaris
, P. J. Ring
, et al.
·
Nuclear Technology
·
1
Water Chemistry of Breeder Reactor Steam Generators
1981
·
J. L. Simpson
, M. N. Robles
, et al.
·
Nuclear Technology
·
1
Carbon transport in a bimetallic sodium loop simulating the intermediate heat transport system of a liquid metal fast breeder reactor
1980
·
L. V. Hampton
, C.N. Spalaris
, et al.
·
University of North Texas Digital Library (University of North Texas)
·
1
3. Welding for the CRBRP steam generators
1979
·
C. N. Spalaris
, P. J. Ring
, et al.
·
1
PDF
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Works count:
90
Citation count:
150
H-index:
6
I10-index:
3
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