ENDF/B-5 fission product cross section evaluations

ENDF/B-5 fission product cross section evaluations [electronic resource]

Cross section evaluations were made for the 196 fission product nuclides on the ENDF/B-5 data files. Most of the evaluations involve updating the capture cross sections of the important absorbers for fast and thermal reactor systems. This included updating thermal values, resonance integrals, resona...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Hanford Engineering Development Laboratory (Researcher), Hanford Site (Wash.) (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Richland, Wash. : Oak Ridge, Tenn. : Hanford Site (Wash.) ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1979.
Subjects:
Information.
Neutrons.
Elementary Particles.
Least Square Fit.
Numerical Solution.
Fast Neutrons.
Baryon Reactions.
Nucleons.
Integrals.
Isotopes.
Hadron Reactions.
Evaluated Data.
Neutron Reactions.
Baryons.
Fermions.
Tables.
Data Forms.
Cross Sections.
Nuclear Reactions.
Numerical Data.
Thermal Neutrons.
Graphs.
Nucleon Reactions.
Burnup.
Hadrons.
Capture.
Resonance Integrals.
Data.
Radioactive Materials.
Nuclear Data Collections.
Maximum-likelihood Fit.
Fission Products.
Nuclear Physics And Radiation Physics.

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Call Number: E 1.99: conf-791223-3
E 1.99: conf-791223-3 Available

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