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A.C. Peterson
Observed names:
A Peterson,
A. C. Peterson,
Peterson, A.C. Jr.
Observed institution:
Westinghouse Electric (United States)
OpenAlex ID:
A5000405305
Two-Phase Flow Patterns with High-Pressure Water in a Heated Four-Rod Bundle
1978
·
C. L. Williams
, A. C. Peterson
·
Nuclear Science and Engineering
·
29
Preliminary comparison with 40 CFR Part 191, Subpart B for the Waste Isolation Pilot Plant, December 1991
1991
·
R.P. Rechard
, A.C. Peterson
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
13
Preliminary comparison with 40 CFR Part 191, Subpart B for the Waste Isolation Pilot Plant, December 1991. Volume 3: Reference data
1991
·
R.P. Rechard
, A.C. Peterson
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
7
Critical heat flux and pressure drop tests with parallel upflow of high pressure water in bundles of twenty 0.25- and 0.28-inch diameter rods (LWBR development program)
1975
·
B.W. LeTourneau
, A.C. Peterson
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
Hydrogen transport in a large, dry containment for selected arrested sequences
1985
·
D.B. King
, A.C. Peterson
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
1
Heat Transfer from Wires to Gases - Maximum Flow Rates in Thermal Conductivity Measurements
1954
·
A. C. Peterson
, A. J. Madden
, et al.
·
Industrial & Engineering Chemistry
·
1
Containment Loading Resulting from Severe Accident Analyses
1985
·
A.C. Peterson
, S.A. Hodge
, et al.
·
NCSU Libraries Repository (North Carolina State University Libraries)
TRAC-PF1/MOD1 independent assessment at Sandia National Laboratories
1984
·
L.D. Buxton
, L.N. Kmetyk
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Posttest analysis of international standard problem 10 using RELAP4/MOD7. [PWR]
1981
·
Hsu, M.
, Davis, C.B.
, et al.
·
University of North Texas Digital Library (University of North Texas)
PDF
TRAC pre-test calculations of LOFT nuclear test L2-3. [PWR]
1979
·
D.A. Mandell
, A.C. Peterson
, et al.
·
Transactions of the American Nuclear Society
Rod thermal response during isothermal loss-of-coolant experiments. [PWR]
1978
·
A.C. Peterson
, Idaho Falls G Idaho
, et al.
·
Transactions of the American Nuclear Society
Investigation of alternate ECC injection concepts in the semiscale Mod-1 system. [PWR]
1977
·
E. A. Harvego
, A. C. Peterson
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Reflood heat transfer in the Semiscale Mod-1 core during forced feed reflood tests
1977
·
A.C. Peterson
, G.G. Loomis
Thermal and hydraulic response of the Semiscale Mod-1 core during forced feed reflood tests. [PWR]
1976
·
A.C. Peterson
, G.G. Loomis
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, January--March 1976
1976
·
J. O. Zane
, R. F. Farman
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Flow patterns in high pressure two-phase flow: a visual study of water in a uniformly heated 4-rod bundle (LWBR Development Program)
1975
·
C. L. Williams
, A.C. Peterson
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Thermal and Hydraulic Effects of Crud Deposited on Electrically Heated Rod Bundles (lwbr Development Program).
1970
·
S.J. Green
, B.W. LeTourneau
, et al.
Brief-Heat Transfer from Wires to Gases
1954
·
A Peterson
, A Madden, Jr.
, et al.
·
Industrial & Engineering Chemistry
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Works count:
18
Citation count:
54
H-index:
3
I10-index:
2
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