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Stochastic fluctuations in a power reactor by Harris, D. R.
Washington, D.C. : Office of Technical Services, Department of Commerce, 1958Call Number: Loading…
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2
A lattice of slightly enriched UO₂ fuel rods partly immersed in light water by Harris, D. R.
Washington, D.C. : Office of Technical Services, Department of Commerce, 1957Call Number: Loading…
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3
Neutron bursts in a ring reactor by Harris, D. R.
Washington, D.C. : Office of Technical Services, Department of Commerce, 1958Call Number: Loading…
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4
Neutron flux mapping by large detectors by Harris, D. R.
Washington, D.C. : Office of Technical Services, Department of Commerce, 1957Call Number: Loading…
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5
Large counting losses in neutron detection channels by Harris, D. R.
Washington, D.C. : Office of Technical Services, Department of Commerce, 1957Call Number: Loading…
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6
RAM-1 : a FORTRAN program to transform and average cross sections from the ROC library tape for use in multigroup neutron transport programs by Harris, D. R.
Washington, D.C. : Office of Technical Services, Department of Commerce, 1965Call Number: Loading…
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7
ROC-1 : a FORTRAN program for storage of evaluated nuclear data by Harris, D. R.
Washington, D.C. : Office of Technical Services, Department of Commerce, 1965Call Number: Loading…
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8
MO564, a Fortran program for symmetric and asymmetric resonance integrals by Harris, D. R.
Pittsburgh, Penn. : Bettis Atomic Power Laboratory, 1964Call Number: Loading…
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9
Calculation of the background neutron source in new, uranium-fueled reactors by Harris, D. R.
Washington, D.C. : Office of Technical Services, Department of Commerce, 1960Call Number: Loading…
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10
Kinetic and buckling measurements on lattices of slightly enriched uranium or UO₂ rods in light water by Brown, J. R.
Pittsburgh, Pennsylvania. : Bettis Plant, 1958Other Authors: “…Harris, D. R.…”
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Related Subjects
Mathematical models
Measurement
Computer programs
FORTRAN (Computer program language)
Nuclear reactors
Neutrons
Nuclear energy
Nuclear fuel rods
Analysis
Buckling
Capture
Cores
Databases
Isotopes
Neutron flux
Neutron transport theory
Nuclear physics
Nuclear reactor kinetics
Numerical analysis
Radiation, Background
Resonance integral
Spontaneous fission
Testing
Thermodynamics
Uranium
Uranium as fuel
Uranium oxides