Evaluation of Gamma-ray Production Cross Sections from Neutron-induced Reactions on Tungsten
Title | Evaluation of Gamma-ray Production Cross Sections from Neutron-induced Reactions on Tungsten PDF eBook |
Author | |
Publisher | |
Pages | |
Release | 1974 |
Genre | |
ISBN |
Neutron-induced Gamma-ray Production Cross Sections for Silicon and Tungsten
Title | Neutron-induced Gamma-ray Production Cross Sections for Silicon and Tungsten PDF eBook |
Author | W. E. Tucker |
Publisher | |
Pages | 122 |
Release | 1969 |
Genre | Neutron cross sections |
ISBN |
Experimental measurements of the differential cross sections for the production of gamma rays in natural silicon and tungsten in the energy range from 5.0 to 11.0 MeV are presented. Theoretical calculations of the production cross sections for silicon, based on statistical theory and the Satchler formalism, with modifications by Moldauer, have been made, and comparisons of these calculations and other nuclear model calculations with experiment are discussed.
Evaluation of 235U Neutron Cross Section and Gamma Ray Production for ENDF/B-V
Title | Evaluation of 235U Neutron Cross Section and Gamma Ray Production for ENDF/B-V PDF eBook |
Author | M. R. Bhat |
Publisher | |
Pages | 80 |
Release | 1980 |
Genre | Gamma rays |
ISBN |
Calculation of Neutron Cross Sections for Tungsten Isotopes. [Pre-equilibrium Statistical Model, 1 to 20 MeV Preliminary Calculations].
Title | Calculation of Neutron Cross Sections for Tungsten Isotopes. [Pre-equilibrium Statistical Model, 1 to 20 MeV Preliminary Calculations]. PDF eBook |
Author | |
Publisher | |
Pages | |
Release | 1979 |
Genre | |
ISBN |
Neutron-induced cross sections on tungsten isotopes were calculated in the energy range between 1 and 20 MeV using preequilibrium-statistical model techniques. The success of these calculations, which form part of an effort to improve the evaluated neutron and gamma-ray production cross sections for tungsten appearing in ENDF/B, depends strongly on the determination of consistent input parameter sets applicable over the entire range of interest. For example, neutron optical model parameters were derived through a simultaneous analysis of total cross sections, resonance data, and angular distributions. These parameters, when used in multistep Hauser-Feshbach calculations, produce good agreement with varied experimental data such as neutron inelastic scattering excitation functions and (n, 2n) cross sections. Likewise, gamma-ray strength functions were determined through fits to neutron capture data that produce calculated results that compare well to measured gamma-ray production cross sections. A description of the techniques used in such parameter determinations as well as comparison of calculated results to experimental data will be presented.
Measurement of Gamma-ray Production Cross Sections in Neutron-induced Reactions for Al and Pb
Title | Measurement of Gamma-ray Production Cross Sections in Neutron-induced Reactions for Al and Pb PDF eBook |
Author | |
Publisher | |
Pages | 0 |
Release | 1995 |
Genre | |
ISBN |
Nuclear Science Abstracts
Title | Nuclear Science Abstracts PDF eBook |
Author | |
Publisher | |
Pages | 658 |
Release | 1976 |
Genre | Nuclear energy |
ISBN |
Cross Section Standards for Neutron-induced Gamma-ray Production in the MeV Energy Range
Title | Cross Section Standards for Neutron-induced Gamma-ray Production in the MeV Energy Range PDF eBook |
Author | |
Publisher | |
Pages | 5 |
Release | 2004 |
Genre | |
ISBN |
Gamma-ray cross section standards for neutron-induced reactions are important in enabling the accurate determination of absolute cross sections from relative measurements of gamma-ray production. In our work we observed a need for improvement in these standards. In particular there are large discrepancies between evaluations of the {sup nat}Fe(n, n1'[gamma]) cross section for the 847-keV gamma ray. We have performed (1) absolute cross section measurements, (2) measurements relative to the {sup nat}Cr(n, n1'[gamma]) 1434-keV gamma ray, and (3) comparisons using measured total and elastic scattering cross sections to refine our knowledge of the Fe cross section and the closely linked inelastic channel cross section for Fe. Calculation of integral tests of the cross section libraries may indicate that adjustment of the angular distributions of the neutron elastic and inelastic scattering may be needed.