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Review of spent-fuel photon and neutron source spectra [electronic resource].

Published
Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1986.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 25 : digital, PDF file
Additional Creators
Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The calculations of spent-fuel photon and neutron spectra have been significantly improved over the past several years. Methods for performing these computations at ORNL have been implemented in the ORIGEN2 and ORIGEN-S codes and the SAS2 control module of the SCALE system. The codes use photon data for delayed gamma rays, x-rays, spontaneous fission gamma rays, (..cap alpha..,n) reaction gamma rays, bremsstrahlung and decay constants, taken mainly from the Evaluated Nuclear Data Structure File. The data for neutron source strengths and spectral distributions of spontaneous fission and (..cap alpha..,n) reactions were compiled from several different research projects. Brief discussions of the codes, the spectral data and the range of applicability are presented. Also, several examples of spent-fuel photon and neutron spectra are included. 29 refs.
Report Numbers
E 1.99:ornl/csd/tm-205
ornl/csd/tm-205
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
01/01/1986.
"ornl/csd/tm-205"
"DE86006764"
Alexander, C.W.; Hermann, O.W.
Funding Information
AC05-84OR21400
View MARC record | catkey: 14666455