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David R. Vondy
Observed names:
D R Vondy,
D Vondy,
D. R Vondy,
D. R. Vondy,
D. Vondy,
D.R. Vondy,
Vondy, D. R.,
Vondy, D.R.
show all 8
Institution:
Oak Ridge National Laboratory
Observed institutions:
Oak Ridge National Laboratory,
United States Department of Commerce,
National Technical Information Service,
Technology for Energy Corporation (United States),
University of Tennessee at Knoxville
OpenAlex ID:
A5074069490
Nuclear Reactor Core Analysis Code: Citation.
1970
·
T.B. Fowler
, D.R. Vondy
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
339
Discussion About the Nuclear Reactor Core Analysis Code Citation.
1971
·
D.R. Vondy
, T.B. Fowler
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
56
BOLD VENTURE COMPUTATION SYSTEM for nuclear reactor core analysis, Version III
1981
·
D.R. Vondy
, T.B. Fowler
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
33
Exterminator-2: a Fortran Iv Code for Solving Multigroup Neutron Diffusion Equations in Two Dimensions.
1967
·
T.B. Fowler
, M. Tobias
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
29
VENTURE: a code block for solving multigroup neutronics problems applying the finite-difference diffusion-theory approximation to neutron transport, version II. [LMFBR]
1977
·
D Vondy
, T Fowler
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
15
PDF
DEVELOPMENT OF A GENERAL METHOD OF EXPLICIT SOLUTION TO THE NUCLIDE CHAIN EQUATIONS FOR DIGITAL MACHINE CALCULATIONS (thesis)
1962
·
D. R. Vondy
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
13
PDF
Production of Np237 and Pu238 in Thermal Power Reactors
1964
·
D. R. Vondy
, J. A. Lane
, et al.
·
Industrial & Engineering Chemistry Process Design and Development
·
12
Pebble Bed Reactor: core physics and fuel cycle analysis
1979
·
D.R. Vondy
, B.A. Worley
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
8
Exposure calculation code module for reactor core analysis: BURNER
1979
·
D.R. Vondy
, G.W. Cunningham
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
8
PDF
Solving the Uncommon Nuclear Reactor Core Neutronics Problems
1983
·
D. R. Vondy
, T. B. Fowler
·
Nuclear Science and Engineering
·
6
Exterminator--a Multigroup Code for Solving Neutron Diffusion Equations in One and Two Dimensions
1965
·
T. B. Fowler
, M. L. Tobias
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
6
PDF
Fission-product afterheat: a review of experiments pertinent to the thermal-neutron fission of $sup 235$U
1973
·
Oak Ridge National Lab., Tenn. (USA)
, A. Perry
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
5
CITATION
1969
·
T. B. Fowler
, D. R. Vondy
·
Nuclear Science and Engineering
·
5
PEBBLE: a two-dimensional steady-state pebble bed reactor thermal hydraulics code
1981
·
D.R. Vondy
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
PDF
RODMOD: a code for control rod positioning. [LMFBR]
1978
·
D.R. Vondy
, T.B. Fowler
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
PDF
Code PERTUBAT for processing neutron diffusion theory neutronics results for perturbation analyses
1978
·
D. R. Vondy
, T. B. Fowler
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
PDF
Nuclear fuel, mass balances, conversion ratio, doubling time, and uncertainty
1976
·
D.R. Vondy
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
PDF
NUCLEAR REACTOR CORE ANALYSIS CODE: CITATION. Revision 2, Supplement 3.
1972
·
T.B. Fowler
, D.R. Vondy
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
Argonne Code Center: Benchmark Problem Book
1968
·
R. Blaine
, R. Froehlich
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
PDF
Design of a Small Aqueous Homogeneous Breeder Reactor
1963
·
R. H. Chapman
, I. Spiewak
, et al.
·
Nuclear Science and Engineering
·
3
A Note on a Simple Method for Acceleration of Finite-Difference Group-Diffusion Calculations
1963
·
Melvin Tobias
, David R. Vondy
, et al.
·
Nuclear Science and Engineering
·
3
Nightmare-an Ibm 7090 Code for the Calculation of Gamma Heating in Cylindrical Geometry
1962
·
M.L. Tobias
, D.R. Vondy
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
PDF
Thermal reactor design for a neutron scattering source facility
1985
·
B.A. Worley
, F.C. Difilippo
, et al.
·
University of North Texas Digital Library (University of North Texas)
·
2
Iterative behavior of diffusion theory flux eigenvalue neutronics problems
1979
·
D. R. Vondy
, T. B. Fowler
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
2
Computation system for nuclear reactor core analysis. [LMFBR]
1977
·
D.R. Vondy
, T.B. Fowler
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
2
PDF
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Works count:
95
Citation count:
583
H-index:
8
I10-index:
7
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