Actions for Calculation of Thermal Neutron Flux-Spectra and Nuclear-Constants for Reactor Design. Berechnung thermischer neutronenfluss-spektren und gruppenkonstanten fuer kernreaktoren

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Calculation of Thermal Neutron Flux-Spectra and Nuclear-Constants for Reactor Design. Berechnung thermischer neutronenfluss-spektren und gruppenkonstanten fuer kernreaktoren

Author
Rasch, W.
Published
Germany : [publisher not identified], 1966.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1966.
Physical Description
microfiche : negative ; 11 x 15 cm

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Summary
The computer program THERMOGRUP 6 is a dimensionless reactor code to calculate the flux of thermal neutrons in the energy range of 0 <= E <= 1.68 eV. It contains an extensive collection of thermal neutron cross-sections (84 elements). Tests with the new program showed better results that with the older codes. this is caused by improvements in the theory and the numerical technique.
Report Numbers
DLR-FB-66-91
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
NSA number: NSA-22-035661
OSTI Identifier 4520629
Research organization: Deutsche Forschungsanstalt fuer Luft- und Raumfahrt, Brunswick (West Germany)). Institut fuer Strahlantriebe.
View MARC record | catkey: 44538864