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

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The average total neutron cross sections of {sup 233}U, {sup 235}U, and {sup 239}Pu 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.

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Derrien, H. August 24, 2001.

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The average total neutron cross sections of {sup 233}U, {sup 235}U, and {sup 239}Pu 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.

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  • International Conference on Nuclear Data for Science and Technology, Tsukuba (JP), 10/07/2001--10/12/2001

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  • Report No.: P01-111578
  • Grant Number: AC05-00OR22725
  • Office of Scientific & Technical Information Report Number: 788687
  • Archival Resource Key: ark:/67531/metadc725432

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Office of Scientific & Technical Information Technical Reports

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  • August 24, 2001

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  • Sept. 29, 2015, 5:31 a.m.

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  • March 11, 2016, 1:34 p.m.

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Derrien, H. Average Total Neutron Cross Section OF 233U, 235U AND 239Pu from ORELA Transmission Measurements and Statistical Analysis of the Data, article, August 24, 2001; Tennessee. (digital.library.unt.edu/ark:/67531/metadc725432/: accessed November 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.