Neutron Induced Sup 238 U Subthreshold Fission Cross Section For Neutron Energies Between 5 Ev And 3 5 Mev Resonance Resonance Clusters Fission Widths 5 Ev To 3 5 Mev PDF Download

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Neutron Induced /sup 238/U Subthreshold Fission Cross Section for Neutron Energies Between 5 EV and 3. 5 MeV. [Resonance, Resonance Clusters, Fission Widths, 5 EV to 3. 5 MeV].

Neutron Induced /sup 238/U Subthreshold Fission Cross Section for Neutron Energies Between 5 EV and 3. 5 MeV. [Resonance, Resonance Clusters, Fission Widths, 5 EV to 3. 5 MeV].
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Release: 1978
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Download Neutron Induced /sup 238/U Subthreshold Fission Cross Section for Neutron Energies Between 5 EV and 3. 5 MeV. [Resonance, Resonance Clusters, Fission Widths, 5 EV to 3. 5 MeV]. Book in PDF, ePub and Kindle

A measurement of the /sup 238/U fission cross section between 5 eV and 3.5 MeV was performed. Included is the identification of 85 resonances or clusters of resonances below 200 keV. Also the fission widths for the 27 resolved class I levels were computed from their fission areas, and a neutron width of 0.005 MeV was estimated for the quasi-class II level in the 721 eV fission cluster. The fission level spacing and cross sections are discussed. 9 references. (JFP).


Energy Research Abstracts

Energy Research Abstracts
Author:
Publisher:
Total Pages: 1180
Release: 1979
Genre: Power resources
ISBN:

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ERDA Energy Research Abstracts

ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
Total Pages: 772
Release: 1976
Genre: Medicine
ISBN:

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Fission Cross Section for

Fission Cross Section for
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Release: 1978
Genre:
ISBN:

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The neutron-induced fission cross section for /sup 242m/Am(152y) was measured at the Livermore 100-MeV electron linac in the neutron energy range of 0.01 eV to 20 MeV. Fission fragments were detected using a hemispherical fission chamber. The neutron flux was measured below 10 keV using lithium glass scintillators. Above 10 keV, the /sup 242m/Am fission cross section was measured relative to the 235U fission cross section. Below 20 eV, the data were fit with a sum of single-level Breit-Wigner resonances. Results for the distribution of fission widths, the average fission width, and the average level spacing are presented. The fission cross section in the 100 MeV range is compared with previous measurements. 11 references.


The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy

The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy
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Release: 1986
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Download The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy Book in PDF, ePub and Kindle

The measurement of the fission cross section ratios of nine isotopes relative to 235U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for 235U are: 23°Th - 0.290 +- 1.9%; 232Th - 0.191 +- 1.9%; 233U - 1.132 +- 0.7%; 234U - 0.998 +- 1.0%; 236U - 0.791 +- 1.1%; 238U - 0.587 +- 1.1%; 237Np - 1.060 +- 1.4%; 239Pu - 1.152 +- 1.1%; 242Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs.


INIS Atomindeks

INIS Atomindeks
Author:
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Total Pages: 584
Release: 1988
Genre: Nuclear energy
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Evaluation of the Fission and Capture Cross Sections of [sup]240[/sup]Pu; and [sup]241[/sup]Pu for ENDF/B-V. [10/sup -5/ EV to 20 MeV].

Evaluation of the Fission and Capture Cross Sections of [sup]240[/sup]Pu; and [sup]241[/sup]Pu for ENDF/B-V. [10/sup -5/ EV to 20 MeV].
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Release: 1979
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Download Evaluation of the Fission and Capture Cross Sections of [sup]240[/sup]Pu; and [sup]241[/sup]Pu for ENDF/B-V. [10/sup -5/ EV to 20 MeV]. Book in PDF, ePub and Kindle

Since there were appreciable new data which were not available for ENDF/B-IV, new evaluations for /sup 240/Pu and /sup 241/Pu were carried out for ENDF/B-V. The evaluation of the fission and capture cross sections is reviewed and problem areas are discussed. The neutron energy range of concern was from 10/sup -5/ eV to 20 MeV. Significant changes were made over the entire neutron energy region because of the new experimental data available. The problems in the evaluations due to discrepancies in the nuclear data are emphasized, particularly the 1-eV resonance in /sup 240/Pu and the 0.3-eV resonance in /sup 241/Pu. The evaluation of the fission and capture cross sections for ENDF/B-V represents an improvement over the previous evaluation; however, there continues to be a need for accurate experimental data. 7 figures.