Energy-averaged neutron cross sections of fast-reactor structural materials

Energy-averaged neutron cross sections of fast-reactor structural materials [electronic resource]

The status of energy-averaged cross sections of fast-reactor structural materials is outlined with emphasis on U.S. data programs in the neutron-energy range 1-10 MeV. Areas of outstanding accomplishment and significant uncertainty are noted with recommendations for future efforts. Attention is prim...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Argonne, Ill. : Oak Ridge, Tenn. : Argonne National Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1978.
Subjects:
Cross Sections.
Neutrons.
Nuclear Reactions.
Reactor Materials.
Document Types.
Elementary Particles.
Reactors.
Fast Neutrons.
Baryon Reactions.
Nucleon Reactions.
Nucleons.
Hadrons.
Hadron Reactions.
Neutron Reactions.
Reviews.
Baryons.
Fermions.
Nuclear Physics And Radiation Physics.

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Call Number: E 1.99: conf-771233-1
E 1.99: conf-771233-1 Available

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