Evaluation of p235sU neutron cross section and gamma ray production for ENDF/B-V
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Evaluation of p235sU neutron cross section and gamma ray production for ENDF/B-V

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Published by National Nuclear Data Center, Brookhaven National Laboratory, available from National Technical Information Service in Upton, N.Y, Springfield, Va .
Written in English

Book details:

Edition Notes

StatementM.R. Bhat
SeriesInformation Analysis Center report
ContributionsNational Nuclear Data Center
The Physical Object
Paginationvi, 65 p. :
Number of Pages65
ID Numbers
Open LibraryOL15476270M

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Prompt-gamma neutron activation analysis (PGAA) is a very widely applicable technique for determining the presence and amount of many elements simultaneously in samples ranging in size from micrograms to many is a non-destructive method, and the chemical form and shape of the sample are relatively unimportant. A review of the nuclear data of /sup /U was conducted. Primary emphasis was placed on the neutron capture and fission cross sections, neutron yield per fission, and the fission neutron emission spectrum. The result of this review is an ENDF/B type compilation of nuclear data which is given in the Appendix.   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 natFe(n,n1′γ) cross section for the ‐keV gamma Cited by: 6. ENDF/B-V The movement towards more objective evaluations led to a simultaneous evaluation of the U(n,f) cross section by Poenitz [POE81]. It was composed of an evaluation of the shape of the cross section and a separate evaluation of the normalization for the shape of the cross section.

produce any alarms when exposed to a 10 mR/h gamma-ray exposure rate. Additionally, three quantitative requirements are specified with minimum values that are: 1) Absolute neutron detection efficiency, єabs n ≥ cps/ng Cf at 2m for a source in a defined moderated form 2) Intrinsic gamma-neutron detection efficiency, єint γn ≤   Neutron total and capture cross sections of Am have been measured with a new data acquisition system and a new neutron transmission measurement system installed in Accurate Neutron Nucleus Reaction measurement Instrument at Materials and Life Science Experimental Facility of Japan Proton Accelerator Research Complex. The neutron total cross sections of Am were Cited by: 2. Neutron Cross Sections, Volume 1: Neutron Resonance Parameters and Thermal Cross Sections, Part A represents the fourth edition of what was previously known as BNL, Neutron Cross Sections, Volume 1. This three-chapter book provides the extensive list of detailed individual resonance parameters for each isotope. For example, the thermal neutron cross section for U, which is the neutron cross section at eV neutron energy corresponding to a neutron velocity of m/s at room temperature, can be given as σ c = 95 barns for the neutron capture cross section, σ f = barns for the fission cross section, and σ α = barns for the.

by the symbol. Neutron cross sections are related to the geometric cross section of the target nucleus. Therefore, cross sections are typically expressed in cm2 or barns(b) = cm2. The cross section for a given nuclear interaction is also dependent on other factors, such as the speed of the neutron, the type of interaction, and the stability of the target Size: KB. ENDF/B-VII.1 U Principal cross sections 2 4 6 8 10 12 14 16 18 20 Energy (MeV) 0 5 10 15 20 25 30 35 Cross section (barns) total absorption elastic gamma production.   Separation of gamma-ray and neutron events with CsI(Tl) pulse shape analysis Y Ashida with O(10) MeV kinetic energies are incident on a water target surrounded by detectors to measure the subsequent gamma-ray production, cross section and m thickness situated just behind the target. During beam operations the CsI(Tl) detector is Cited by: 2. The production of radioactive nuclides depends on the cross sections of the specific elements. Also important is the number of gamma rays that are emitted by a radionuclide. In some cases, only a small fraction of the total emissions from a specific nuclide is in the form of gamma rays.