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Neutron cross sections for uranium-235 (ENDF/B-IV Release 3) [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 1996.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
75 unnumbered pages : digital, PDF file
Additional Creators
Knolls Atomic Power Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The resonance parameters in ENDF6 (Release 2) U235 were adjusted to make the average capture and fission cross sections below 900 eV agree with selected differential capture and fission measurements. The measurements chosen were the higher of the credible capture measurements and the lower of the fission results, yielding a higher epithermal alpha. In addition, the 2200 m/s cross sections were adjusted to obtain agreement with the integral value of K1. As a result, criticality calculations for thermal benchmarks, and agreement with a variety of integral parameters, are improved.
Report Numbers
E 1.99:kapl-p--000229
E 1.99: k--96111
k--96111
kapl-p--000229
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
09/01/1996.
"kapl-p--000229"
" k--96111"
"DE99002619"
Lubitz, C.R.
Funding Information
AC12-76SN00052
View MARC record | catkey: 14355414