Evaluation of Re-185 and Re-187 Neutron Cross Sections for the ENDF
Author : W. B. Henderson
Publisher :
Page : 32 pages
File Size : 48,22 MB
Release : 1968
Category : Neutron cross sections
ISBN :
Author : W. B. Henderson
Publisher :
Page : 32 pages
File Size : 48,22 MB
Release : 1968
Category : Neutron cross sections
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Author : M. R. Bhat
Publisher :
Page : 60 pages
File Size : 13,95 MB
Release : 1973
Category : Neutron cross sections
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Author : David T. Goldman
Publisher :
Page : 732 pages
File Size : 22,20 MB
Release : 1968
Category : Neutron cross sections
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Author : Dermott Edward Cullen
Publisher :
Page : 44 pages
File Size : 31,88 MB
Release : 1979
Category : Capture
ISBN :
Author :
Publisher :
Page : 1216 pages
File Size : 36,68 MB
Release : 1976-06
Category : Nuclear energy
ISBN :
Author :
Publisher :
Page : pages
File Size : 26,67 MB
Release : 2007
Category :
ISBN :
Neutron cross sections for a complete set of Nd isotopes, {sup 142,143,144,145,146,147,148,150}Nd, were evaluated in the incident energy range from 10−5 eV to 20 MeV. In the low energy region, including thermal and resolved resonances, our evaluations are based on the latest data published in the Atlas of Neutron Resonances. In the unresolved resonance region we performed additional evaluation by using the averages of the resolved resonances and adjusting them to the experimental data. In the fast neutron region, we used the nuclear reaction model code EMPIRE-2.19 validated against the experimental data. The results are compared to the existing nuclear data libraries, including ENDF/B-VI. 8, JENDL-3.3 and JEFF-3.1, and to the available experimental data. The new evaluations are suitable for neutron transport calculations and they were adopted by the new evaluated nuclear data file of the United States, ENDF/B-VII.0, released in December 2006.
Author :
Publisher :
Page : 1162 pages
File Size : 47,40 MB
Release : 1973
Category : Nuclear energy
ISBN :
Author :
Publisher :
Page : pages
File Size : 44,20 MB
Release : 2001
Category :
ISBN :
Separate evaluations have been done for the three stable isotopes of silicon for ENDF/B-VI. The evaluations are based on analysis of experimental data, supplemented by results of nuclear model calculations. The computational methods and the parameters required as input to the nuclear model codes are reviewed. Discussion of the evaluated data given for resonance parameters, neutron induced reaction cross sections, associated angular and energy distributions, and gamma-ray production cross sections is included. Extensive comparisons of the evaluated cross sections to measured data are shown in this report. The evaluations include all necessary data to allow KERMA (Kinetic Energy Released in MAterials) and displacement cross sections to be calculated directly. These quantities are fundamental to studies of neutron heating and radiation damage.
Author : Alan Prince
Publisher :
Page : 0 pages
File Size : 35,9 MB
Release : 1979
Category : Krypton
ISBN :
Author :
Publisher :
Page : pages
File Size : 48,28 MB
Release : 1976
Category :
ISBN :
A re-evaluation has been made of neutron and gamma production cross sections for reactions of neutrons with 5°, 52, 53, 54Cr and natural Cr. In addition, energy level schemes and Q values are presented. 97 references. (SDF).