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Single rod fast effects and related measurements

N0AH

Published Year

• 1960-1969 (2) *

Subject

• Neutron flux (2) *
• FORTRAN IV (Computer program language) (1)
• Neutron tranport theory (1)
• Nuclear fission--Measurement (1)
• Nuclear fuel rods--Thermal properties (1)
• Nuclear reactors--Computer programs (1)
• Nuclear reactors--Measurement (1)

Author

• Lellouche, Gerald S. (1)
• Price, Glenn A. (1)

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