Neutron Cross Section Data for Carbon

Neutron Cross Section Data for Carbon

Author: M. Kalos

Publisher:

Published: 1956

Total Pages: 30

ISBN-13:

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A tabulation is made of total and elastic scattering cross sections together with Legendre coefficients for elastic angular distributions for neutron scattering by carbon, in the range 0.33 to 18.0 Mev.


Total Cross Sections of Nuclei for 280 Mev Neutrons

Total Cross Sections of Nuclei for 280 Mev Neutrons

Author: R. Fox

Publisher:

Published: 1950

Total Pages: 12

ISBN-13:

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The measurement of 28O-Mev neutron cross sections of various nuclei is described. The neutron beam used results from 340-Mev protons in the 184-in. cyclotron striking a 2-in. Be target. The neutron detector consists of a double coincidence anthracene scintillation counter telescope which counts recoil protons scattered at 15 deg from a paraffin cylinder placed in the collimated neutron beam. A 2-in. Cu absorber placed between the counters assures that only protons of energy greater than 250 Mev are counted. The cross sections for all nuclei measured from Li to Pb are smaller than the corresponding cross sections measured at 90 Mev by factors between 0.5 and 0.6.


High Energy Nuclear Reactions

High Energy Nuclear Reactions

Author: Jerome Hudis

Publisher:

Published: 1960

Total Pages: 46

ISBN-13:

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The literature has been searched for references pertaining to high energy reactions of interest to nuclear chemists. Nuclear Science Abstracts was the main source of references and wherever possible the complete abstract was retained.


Nuclear Cross Sections for 95-Mev Neutrons

Nuclear Cross Sections for 95-Mev Neutrons

Author: James DeJuren

Publisher:

Published: 1950

Total Pages: 24

ISBN-13:

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The total cross sections of twelve different elements were measured using the neutron beam from the 184-in. cyclotron, operating with deuterons. Bismuth fission ionization chambers were employed as both monitor and detector in conventional 'good geometry' attenuation measurements in the neutron flux emerging from the 3-in. diameter collimating port in the 10-ft-thick concrete shielding. The mean energy of detection of the neutrons in this experiment is estimated to be 95 Mev. Measurements were also made with a monitor and detector placed inside the concrete shielding where an intense neutron flux over a large area could be obtained. Attenuators of four different elements were placed in front of the detector in a 'poor geometry' arrangement so that attenuation was due essentially to inelastic collisions which degrade the neutron energy below the fission threshold. A second detector was placed outside the concrete shielding In the collimated neutron beam in line with the neutron source, absorber, and first detector. Attenuation in it is caused by both inelastic and elastic scattering. By this arrangement the ratio of inelastic to total cross section can be determined directly in one experiment. The nuclear radii as calculated from the observed cross section, using the theory of the transparent nucleus, vary as 1.38 x 10(exp-13) A(exp(1/3)) cm. In this energy range the ratios of the inelastic to total cross sections are all less than one-half.