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A two-group reactor card program for a small digital computer

A review of the methods for computing thermal neutron spectra

ENDF/B :specifications for an evaluated nuclear data file for reactor applications

N0AH

Published Year

• 1950-1959 (1)
• 1960-1969 (3)

Subject

• Nuclear reactors--Computer programs (4) *
• FORTRAN IV (Computer program language) (1)
• Neutron flux (1)
• Neutron flux--Measurement--Computer programs (1)
• Neutron tranport theory (1)
• Neutrons--Spectra (1)
• Nuclear reactors--Data processing (1)
• Thermal neutrons (1)

Author

• Honeck, Henry C. (2)
• Lamarsh, John R. (1)
• Lellouche, Gerald S. (1)
• Pearlstein, S. (1)
• Rideout, Stuart S. (1)

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