The Measurement of Neutron Total Cross Sections in the Resonance Energy Region and

The Measurement of Neutron Total Cross Sections in the Resonance Energy Region and PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 34

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The Measurement of Neutron Total Cross Sections in the Resonance Energy Region and

The Measurement of Neutron Total Cross Sections in the Resonance Energy Region and PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 34

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Neutron Cross Sections and Technology

Neutron Cross Sections and Technology PDF Author: David T. Goldman
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 736

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Neutron Cross Sections in the Energy Range 100 Ev It E/sub N /It 100 Kev

Neutron Cross Sections in the Energy Range 100 Ev It E/sub N /It 100 Kev PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 41

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Neutron Cross Sections

Neutron Cross Sections PDF Author: Donald J. Hughes
Publisher: Elsevier
ISBN: 1483282759
Category : Science
Languages : en
Pages : 193

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Book Description
Neutron Cross Sections presents the principles of cross-section measurement and use, as well as sufficient theory so that the general behavior of cross sections is made understandable. This compilation is a direct result of experiences connected with the collection and evaluation of cross-section data during the past eight years at ""Sigma Centre"", Brookhaven National Laboratory. Here, experimental results received from laboratories throughout the world are carefully evaluated and compiled in the curves and tables of the large volume Neutron Cross Sections, The most recent version of the compilation, known as BNL 325, appeared 1 July 1955, and Supplement 1 to BNL 325 was published on 1 January 1957. The compilation itself consists almost completely of cross sections at specific energies, shown in the form of curves or tables, with only brief explanatory texts. The text opens with discussions of the general properties of cross sections and principles of nuclear structure that are important to the understanding of cross-section behavior. Separate chapters follow that describe specific techniques for measuring cross sections along with experimental results involving fast neutrons, resonance neutrons, resonances in fissionable materials, and thermal neutrons.

Atlas of Neutron Resonances

Atlas of Neutron Resonances PDF Author: Said F. Mughabghab
Publisher: Elsevier
ISBN: 044463780X
Category : Science
Languages : en
Pages : 698

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Book Description
Atlas of Neutron Resonances: Resonance Properties and Thermal Cross Sections Z=61-102, Sixth Edition, contains an extensive list of detailed individual neutron resonance parameters for Z=61-102, thermal cross sections, capture and fission resonance integrals, average resonance parameters, and a short survey of the physics of thermal and resonance neutrons. The long introduction contains: nuclear physics formulas aimed at neutron physicists; topics of special interest such as valence neutron capture, nuclear level density parameters, and s-, p-, and d-wave neutron strength functions; and various comparisons of measured quantities with the predictions of nuclear models, such as the optical model neutron-induced fission. As in the last edition, additional features have been added to appeal to a wider spectrum of users. These include: spin-dependent scattering lengths that are of interest to solid-state physicists, nuclear physicists and neutron evaluators; calculated and measured Maxwellian average 5-keV and 30-keV capture cross sections of importance to astrophysicists involved in nucleosynthesis modeling; s-, p-, and d- wave average radiative widths; nuclear level density parameters; and average fission widths derived from average fission cross sections. Provides a comparison of average resonance parameters with optical model calculations and with the generalized Landau-Fermi model Presents scattering radii for various partial waves from the analysis of total neutron cross sections in the keV to MeV energy region Includes a brief review of sub-threshold fission Features consistent treatment of average neutron parameters with values from the resolved resonance region

Measurements of Low Energy Neutron Cross Sections of Non-fissile Nuclides and Their

Measurements of Low Energy Neutron Cross Sections of Non-fissile Nuclides and Their PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 38

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Conference on Neutron Cross Section Technology

Conference on Neutron Cross Section Technology PDF Author: P. B. Hemmig
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 582

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Measurement of Neutron Cross Sections with a Crystal Spectrometer

Measurement of Neutron Cross Sections with a Crystal Spectrometer PDF Author: William J. Sturm
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 40

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Reports to the AEC Nuclear Cross Sections Advisory Group

Reports to the AEC Nuclear Cross Sections Advisory Group PDF Author:
Publisher:
ISBN:
Category : Nuclear physics
Languages : en
Pages : 44

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Average Neutron Total Cross Sections in the Unresolved Energy Range From ORELA High Resolutio Transmission Measurements

Average Neutron Total Cross Sections in the Unresolved Energy Range From ORELA High Resolutio Transmission Measurements PDF Author: H. Derrien
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Average values of the neutron total cross sections of {sup 233}U, {sup 235}U, {sup 238}U, and {sup 239}Pu have been obtained in the unresolved resonance energy range from high-resolution transmission measurements performed at ORELA in the past two decades. The cross sections were generated by correcting the effective total cross sections for the self-shielding effects due to the resonance structure of the data. The self-shielding factors were found by calculating the effective and true cross sections with the computer code SAMMY for the same Doppler and resolution conditions as for the transmission measurements, using an appropriate set of resonance parameters. Our results are compared to results of previous measurements and to the current ENDF/B-VI data.