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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

Book Description


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

Book Description


Neutron Cross Sections and Related Measurements

Neutron Cross Sections and Related Measurements PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 27

Book Description


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 : 572

Book Description


Neutron Cross Sections

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

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.

Neutron Cross Sections and Technology

Neutron Cross Sections and Technology PDF Author: David T. Goldman
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 670

Book Description


Assessment of the ''thermal Normalization Technique'' for Measurement of Neutron Cross Sections Vs Energy. [Above 20 KeV, Resonance, Fission Integrals, Error Minimization].

Assessment of the ''thermal Normalization Technique'' for Measurement of Neutron Cross Sections Vs Energy. [Above 20 KeV, Resonance, Fission Integrals, Error Minimization]. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Refined knowledge of the thermal neutron cross sections of the fissile nuclides and of the (n, .cap alpha.) reaction standards, together with the reasonably well known energy dependence of the latter, have permitted resonance-region and low-keV fissile nuclide cross sections to be based on these standards together with count-rate ratios observed as a function of energy using a pulsed ''white'' source. As one evaluates cross sections for energies above 20 keV, optimum results require combination of cross section shape measurements with all available absolute measurements. The assumptions of the ''thermal normalization method'' are reviewed, and an opinion is given of the status of some of the standards required for its use. The complications which may limit the accuracy of results using the method are listed and examples are given. For the 235U(n, f) cross section, the option is discussed of defining resonance-region fission integrals as standards. The area of the approximately 9 eV resonances in this nuclide may be known to one percent accuracy, but at present the fission integral from 0.1 to 1.0 keV is known to no better than about two percent. This uncertainty is based on the scatter among independent results, and has not been reduced by the most recent measurements. This uncertainty now limits the accuracy attainable for the 235U(n, f) cross section below about 50 keV. Suggestions are given to indicate how future detailed work might overcome past sources of error.

Low Energy Neutron Cross Sections of Radioactive Fission Product Nuclides

Low Energy Neutron Cross Sections of Radioactive Fission Product Nuclides PDF Author:
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 11

Book Description


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

Book Description


Tabulated Neutron Cross Sections, 0.001-14.5 Mev

Tabulated Neutron Cross Sections, 0.001-14.5 Mev PDF Author: R. J. Howerton
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 390

Book Description


Nuclear Cross Sections for 95-Mev Neutrons

Nuclear Cross Sections for 95-Mev Neutrons PDF Author: James DeJuren
Publisher:
ISBN:
Category : Bismuth
Languages : en
Pages : 24

Book Description
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.