Actions for Theoretical analyses of (n,xn) reactions on sup 235 U, sup 238 U, sup 237 Np, and sup 239 Pu for ENDF
Theoretical analyses of (n,xn) reactions on sup 235 U, sup 238 U, sup 237 Np, and sup 239 Pu for ENDF/B-VI [electronic resource].
- Published
- Washington, D.C. : United States. Dept. of Energy, 1991.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (4 pages) : digital, PDF file
- Additional Creators
- Los Alamos National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Theoretical analyses were performed of neutron-induced reactions on ²³⁵U, ²³⁸U, ²³⁷Np, and ²³⁹Pu between 0.01 and 20 MeV in order to calculate neutron emission cross sections and spectra for ENDF/B-VI evaluations. Coupled-channel optical model potentials were obtained for each target nucleus by fitting total, elastic, and inelastic scattering cross section data, as well as low-energy average resonance data. The resulting deformed optical model potentials were used to calculate direct (n,n′) cross sections and transmission coefficients for use in Hauser-Feshbach statistical theory analyses. A fission model with multiple barrier representation, width fluctuation corrections, and preequilibrium corrections were included in the analyses. Direct cross sections for higher-lying vibrational states were calculated using DWBA theory, normalized using B(Eℓ) values determined from (d,d′) and Coulomb excitation data, where available, and from systematics otherwise. Initial fission barrier parameters and transition state density enhancements appropriate to the compound systems involved were obtained from previous analyses, especially fits to charged-particle fission probability data. The parameters for the fission model were adjusted for each target system to obtain optimum agreement with direct (n,f) cross section measurements, taking account of the various multichance fission channels, that is, the different compound systems involved. The results from these analyses were used to calculate most of the neutron (n,n), (n,n′), and (n,xn) cross section data in the ENDF/B/VI evaluations for the above nuclei, and all of the energy-angle correlated spectra. The deformed optical model and fission model parameterizations are described. Comparisons are given between the results of these analyses and the previous ENDF/B-V evaluations as well as with the available experimental data. 14 refs., 3 figs., 1 tab.
- Report Numbers
- E 1.99:la-ur-91-1424
E 1.99: conf-910503--2
conf-910503--2
la-ur-91-1424 - Subject(s)
- Other Subject(s)
- Neptunium 237 Target
- Neutron Reactions
- Plutonium 239 Target
- Uranium 235 Target
- Uranium 238 Target
- Angular Distribution
- Coupled Channel Theory
- Cross Sections
- Fission
- Nuclear Data Collections
- Nuclear Models
- Optical Models
- Scattering
- Baryon Reactions
- Distribution
- Hadron Reactions
- Mathematical Models
- Nuclear Reactions
- Nucleon Reactions
- Targets
- Note
- Published through SciTech Connect.
01/01/1991.
"la-ur-91-1424"
" conf-910503--2"
"DE91011410"
International conference on nuclear data for science and technology, Juelich (Germany, F.R.), 13-17 May 1991.
Young, P.G.; Arthur, E.D. - Funding Information
- W-7405-ENG-36
View MARC record | catkey: 14670755