AN EVALUATION OF 235U NEUTRON CROSS SECTION DATA FOR ENERGIES ABOVE 15 KeV.

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Book Synopsis AN EVALUATION OF 235U NEUTRON CROSS SECTION DATA FOR ENERGIES ABOVE 15 KeV. by :

Download or read book AN EVALUATION OF 235U NEUTRON CROSS SECTION DATA FOR ENERGIES ABOVE 15 KeV. written by and published by . This book was released on 1970 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

An Evaluation of Uranium-235 Neutron Cross Section Data for Energies Above 15 Kev

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Total Pages : 20 pages
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Book Synopsis An Evaluation of Uranium-235 Neutron Cross Section Data for Energies Above 15 Kev by :

Download or read book An Evaluation of Uranium-235 Neutron Cross Section Data for Energies Above 15 Kev written by and published by . This book was released on 1970 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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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Book Synopsis 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. by :

Download or read book 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. written by and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Evaluation of the 235U Fission Cross-section from 100 EV to 20 MeV. [Cross Sections, Error Estimates].

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Book Synopsis Evaluation of the 235U Fission Cross-section from 100 EV to 20 MeV. [Cross Sections, Error Estimates]. by :

Download or read book Evaluation of the 235U Fission Cross-section from 100 EV to 20 MeV. [Cross Sections, Error Estimates]. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The evaluation of the 235U fission cross section from 100 eV to 20 MeV for ENDF/B-V is described. The evaluated average cross sections from 100 eV to 200 keV are given, and it is proposed to include structure in the cross section in this energy region. Above 200 keV, the cross section is given as a smooth curve, and is recommended as a standard. Preliminary error estimates in the cross section are also given.

Agenda

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Total Pages : 1 pages
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Download or read book Agenda written by and published by . This book was released on 1985 with total page 1 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Neutron Cross-sections of U235and U238 in the Energy Range 1 KeV - 15 MeV

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Total Pages : 127 pages
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Book Synopsis Neutron Cross-sections of U235and U238 in the Energy Range 1 KeV - 15 MeV by : K. Parker

Download or read book Neutron Cross-sections of U235and U238 in the Energy Range 1 KeV - 15 MeV written by K. Parker and published by . This book was released on 1964 with total page 127 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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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Total Pages : 5 pages
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Book Synopsis 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 by :

Download or read book 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 written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Evaluation of 235U Neutron Cross Section and Gamma Ray Production Data for ENDF

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Book Synopsis Evaluation of 235U Neutron Cross Section and Gamma Ray Production Data for ENDF by :

Download or read book Evaluation of 235U Neutron Cross Section and Gamma Ray Production Data for ENDF written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A discussion is given of the evaluation of neutron and gamma ray production cross sections of 235U from 10−5 eV to 20 MeV and the parts contributed by the author. All available new data are included in this evaluation, and the procedures adopted to assess the experimental data and adopt a set of recommended values are described. 22 figures, 10 tables.

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

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

Download or read book Assessment of the ''thermal Normalization Technique'' for Measurement of Neutron Cross Sections Vs Energy. [Above 20 KeV, Resonance, Fission Integrals, Error Minimization]. written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Evaluation of the 238U Neutron Cross Sections for Incident Neutron Energies Up to 4 KeV

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Total Pages : 93 pages
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Book Synopsis Evaluation of the 238U Neutron Cross Sections for Incident Neutron Energies Up to 4 KeV by :

Download or read book Evaluation of the 238U Neutron Cross Sections for Incident Neutron Energies Up to 4 KeV written by and published by . This book was released on 1978 with total page 93 pages. Available in PDF, EPUB and Kindle. Book excerpt:

A New Resonance-region Evaluation of Neutron Cross Sections for U-235. [60-100, 450-500 EV].

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Book Synopsis A New Resonance-region Evaluation of Neutron Cross Sections for U-235. [60-100, 450-500 EV]. by :

Download or read book A New Resonance-region Evaluation of Neutron Cross Sections for U-235. [60-100, 450-500 EV]. written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes a multilevel resonance analysis of the 235U neutron cross sections in the resolved resonance energy region. 15 refs., 3 figs., 2 tabs.

Evaluation of 235u Neutron Cross Section and Gamma Ray Production Data for Endf

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Book Synopsis Evaluation of 235u Neutron Cross Section and Gamma Ray Production Data for Endf by : M.R. Bhat

Download or read book Evaluation of 235u Neutron Cross Section and Gamma Ray Production Data for Endf written by M.R. Bhat and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 1216 pages
Book Rating : 4.0/5 ( download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976-06 with total page 1216 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Neutron Cross-sections of U235and U238 in the Energy Range 1 KeV - 15 MeV

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ISBN 13 :
Total Pages : 106 pages
Book Rating : 4.:/5 (94 download)

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Book Synopsis Neutron Cross-sections of U235and U238 in the Energy Range 1 KeV - 15 MeV by : K. Parker

Download or read book Neutron Cross-sections of U235and U238 in the Energy Range 1 KeV - 15 MeV written by K. Parker and published by . This book was released on 1963 with total page 106 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Evaluation of the Neutron Cross Sections of 235U in the Thermal Energy Region

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Book Synopsis Evaluation of the Neutron Cross Sections of 235U in the Thermal Energy Region by : B. R. Leonard

Download or read book Evaluation of the Neutron Cross Sections of 235U in the Thermal Energy Region written by B. R. Leonard and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

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

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

Download or read book Average Total Neutron Cross Section OF 233U, 235U AND 239Pu from ORELA Transmission Measurements and Statistical Analysis of the Data written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Evaluation of 235U neutron cross section and gamma ray production data for ENDF/B-V

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Book Synopsis Evaluation of 235U neutron cross section and gamma ray production data for ENDF/B-V by :

Download or read book Evaluation of 235U neutron cross section and gamma ray production data for ENDF/B-V written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: