Neutron Total Cross Sections Of 235u From Transmission Measurements In The Energy Range 2 Kev To 300 Kev And Statistical Model Analysis Of The Data PDF Download

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NEUTRON TOTAL CROSS SECTIONS OF 235U FROM TRANSMISSION MEASUREMENTS IN THE ENERGY RANGE 2 KeV to 300 KeV AND STATISTICAL MODEL ANALYSIS OF THE DATA.

NEUTRON TOTAL CROSS SECTIONS OF 235U FROM TRANSMISSION MEASUREMENTS IN THE ENERGY RANGE 2 KeV to 300 KeV AND STATISTICAL MODEL ANALYSIS OF THE DATA.
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Release: 2003
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The average[sup 235]U neutron total cross sections were obtained in the energy range 2 keV to 330 keV from high-resolution transmission measurements of a 0.033 atom/b sample. The experimental data were corrected for the contribution of isotope impurities and for resonance self-shielding effects in the sample. The results are in very good agreement with the experimental data of Poenitz et al. in the energy range 40 keV to 330 keV and are the only available accurate experimental data in the energy range 2 keV to 40 keV. ENDF/B-VI evaluated data are 1.7% larger. The SAMMY/FITACS code was used for a statistical model analysis of the total cross section, selected fission cross sections and[alpha] data in the energy range 2 keV to 200 keV. SAMMY/FITACS is an extended version of SAMMY which allows consistent analysis of the experimental data in the resolved and unresolved resonance region. The Reich-Moore resonance parameters were obtained from a SAMMY Bayesian fits of high resolution experimental neutron transmission and partial cross section data below 2.25 keV, and the corresponding average parameters and covariance data were used in the present work as input for the statistical model analysis of the high energy range of the experimental data. The result of the analysis shows that the average resonance parameters obtained from the analysis of the unresolved resonance region are consistent with those obtained in the resolved energy region. Another important result is that ENDF/B-VI capture cross section could be too small by more than 10% in the energy range 10 keV to 200 keV.


Neutron Total Cross Sections of 235U From Transmission Measurements in the Energy Range 2 KeV to 300 KeV and Statistical Model Analysis of the Data

Neutron Total Cross Sections of 235U From Transmission Measurements in the Energy Range 2 KeV to 300 KeV and Statistical Model Analysis of the Data
Author:
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Total Pages: 5
Release: 2000
Genre:
ISBN:

Download Neutron Total Cross Sections of 235U From Transmission Measurements in the Energy Range 2 KeV to 300 KeV and Statistical Model Analysis of the Data Book in PDF, ePub and Kindle

The average 235U neutron total cross sections were obtained in the energy range 2 keV to 330 keV from high-resolution transmission measurements of a 0.033 atom/b sample. 1 The experimental data were corrected for the contribution of isotope impurities and for resonance self-shielding effects in the sample. The results are in very good agreement with the experimental data of Poenitz et al. 4 in the energy range 40 keV to 330 keV and are the only available accurate experimental data in the energy range 2 keV to 40 keV. ENDF/B-VI evaluated data are 1.7% larger. The SAMMY/FITACS code 2 was used for a statistical model analysis of the total cross section, selected fission cross sections and data in the energy range 2 keV to 200 keV. SAMMY/FITACS is an extended version of SAMMY which allows consistent analysis of the experimental data in the resolved and unresolved resonance region. The Reich-Moore resonance parameters were obtained 3 from a SAMMY Bayesian fits of high resolution experimental neutron transmission and partial cross section data below 2.25 keV, and the corresponding average parameters and covariance data were used in the present work as input for the statistical model analysis of the high energy range of the experimental data. The result of the analysis shows that the average resonance parameters obtained from the analysis of the unresolved resonance region are consistent with those obtained in the resolved energy region. Another important result is that ENDF/B-VI capture cross section could be too small by more than 10% in the energy range 10 keV to 200 keV.


Average Total Neutron Cross Section OF 233U, 235U AND 239Pu from ORELA Transmission Measurements and Statistical Analysis of the Data

Average Total Neutron Cross Section OF 233U, 235U AND 239Pu from ORELA Transmission Measurements and Statistical Analysis of the Data
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Total Pages: 5
Release: 2001
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Download Average Total Neutron Cross Section OF 233U, 235U AND 239Pu from ORELA Transmission Measurements and Statistical Analysis of the Data Book in PDF, ePub and Kindle

The average total neutron cross sections of 233U, 235U, and 239Pu were obtained from transmission measurements in the unresolved resonance region up to several hundred keV neutron energy. The method used for the calculation of the self-shielding effect is described. A statistical model analysis of the results was performed and the s-, p- and d-wave neutron strength functions were obtained.


Nuclear Cross Sections for Technology

Nuclear Cross Sections for Technology
Author: Joseph L. Fowler
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Total Pages: 1062
Release: 1980
Genre: Cross sections (Nuclear physics)
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NBS Special Publication
Author:
Publisher:
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Release: 1980
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ISBN:

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Nuclear Science Abstracts
Author:
Publisher:
Total Pages: 1292
Release: 1976
Genre: Nuclear energy
ISBN:

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