Systematics of Neutron-induced Fisson Cross Sections Over the Energy Range 0. 1 MeV to 15 MeV and at 0. 0253 EV.
Systematics of Neutron-induced Fisson Cross Sections Over the Energy Range 0. 1 MeV to 15 MeV and at 0. 0253 EV.

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Published: 1977

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Previous studies by Behrens have provided evidence of systematic behavior in neutron-induced fission cross sections in the incident neutron energy range 3 to 5 MeV. Recently measured fission cross-section ratios revealed this behavior. In this report, these measurements and those of others are used to illustrate the behavior of fission cross sections over the neutron energy range 0.1 MeV to 15 MeV. Similar trends are seen at 0.0253 eV, as revealed by thermal cross-section measurements. 12 figures.

Systematics of Neutron-induced Fission Cross Sections Over the Energy Range 0. 1 Through 15 MeV, and at 0. 0253 EV.
Systematics of Neutron-induced Fission Cross Sections Over the Energy Range 0. 1 Through 15 MeV, and at 0. 0253 EV.

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Published: 1977

Total Pages:

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Recent studies have shown straightforward systematic behavior as a function of constant proton and neutron number for neutron-induced fission cross sections of the actinide elements in the incident-neutron energy range 3 to 5 MeV. In this report, the second in a series, fission cross-section values are studied over the MeV incident-neutron energy range, and at 0.0253 eV. Fission-barrier heights and neutron-binding energies are correlated by constant proton and neutron number; however, these systematic behaviors alone do not explain the trends observed in the fission cross-section values.

Neutron Cross Sections
Neutron Cross Sections

Author: Victoria McLane

Publisher: Elsevier

Published: 2012-12-02

Total Pages: 850

ISBN-13: 0323142222

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Neutron Cross Sections, Volume 2: Neutron Cross Section Curves presents data for total reaction cross sections and related fission parameters as a function of incident-neutron energy. This book covers energy range from 0.01 eV to 200 MeV to exclude crystalline and magnetic effects for slow neutrons and relativistic effects for high energy neutrons. The data in this volume are grouped into sections corresponding to the element of the target nucleus in the neutron-induced reaction. These sections are ordered in increasing atomic number. Within a section, graphical data are presented for the natural element followed by the isotopes of that element in order of increasing atomic mass. A list of the reaction types is provided at the end of each section. This book also provides graphical section, wherein each graphical page is annotated on the outer edge with a symbol for an element or isotope followed by the list of the cross section data for that element or isotope. The data plotted in the graphical section are tagged by a mnemonic consisting of year, laboratory, and author's last name. This tag can be used to find the corresponding reference on the bibliographic pages.

Nuclear Fission and Neutron-Induced Fission Cross-Sections
Nuclear Fission and Neutron-Induced Fission Cross-Sections

Author: G. D. James

Publisher: Elsevier

Published: 2013-10-22

Total Pages: 294

ISBN-13: 1483189767

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Nuclear Fission and Neutron-Induced Fission Cross-Sections is the first volume in a series on Neutron Physics and Nuclear Data in Science and Technology. This volume serves the purpose of providing a thorough description of the many facets of neutron physics in different fields of nuclear applications. This book also attempts to bridge the communication gap between experts involved in the experimental and theoretical studies of nuclear properties and those involved in the technological applications of nuclear data. This publication will be invaluable to those interested in studying nuclear fission and neutron-induced fission cross-sections, as well as other relevant concepts.

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.

Scientific and Technical Aerospace Reports
Scientific and Technical Aerospace Reports

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Publisher:

Published: 1968

Total Pages: 1252

ISBN-13:

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Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.