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Fission cross-sections of 235U and 239Pu averaged over 252Cf neutron spectrum

dc.contributor.authorDavis, M. C.en_US
dc.contributor.authorKnoll, Glenn F.en_US
dc.date.accessioned2006-04-07T17:06:19Z
dc.date.available2006-04-07T17:06:19Z
dc.date.issued1978en_US
dc.identifier.citationDavis, M. C., Knoll, G. F. (1978)."Fission cross-sections of 235U and 239Pu averaged over 252Cf neutron spectrum." Annals of Nuclear Energy 5(11-12): 583-588. <http://hdl.handle.net/2027.42/22759>en_US
dc.identifier.urihttp://www.sciencedirect.com/science/article/B6V1R-498VXY0-71/2/ef35861ecd19841d6d766c928fe862dden_US
dc.identifier.urihttps://hdl.handle.net/2027.42/22759
dc.description.abstractA series of measurements have been carried out to derive values for the spectrum-averaged fission cross-section of 235U and 239Pu for 252Cf fission neutrons. Two nearly identical target foils were mounted on either side of a Cf source (107 neutron/sec) in a compensated beam geometry. Fission fragments passing through limited solid angle apertures were recorded from each foil by solid-state track-etch techniques. The Cf neutron source strength was calibrated in manganese bath relative to the standard source NBS-II. Values of 1.215 +/- 0.022 barn for 235U and 1.790 +/- 0.041 barn for 239Pu were obtained for the fission cross-sections, corresponding to a ratio value of 1.473 +/- 0.041.en_US
dc.format.extent344132 bytes
dc.format.extent3118 bytes
dc.format.mimetypeapplication/pdf
dc.format.mimetypetext/plain
dc.language.isoen_US
dc.publisherElsevieren_US
dc.titleFission cross-sections of 235U and 239Pu averaged over 252Cf neutron spectrumen_US
dc.typeArticleen_US
dc.rights.robotsIndexNoFollowen_US
dc.subject.hlbsecondlevelNuclear Engineering and Radiological Sciencesen_US
dc.subject.hlbtoplevelEngineeringen_US
dc.description.peerreviewedPeer Revieweden_US
dc.contributor.affiliationumThe University of Michigan, Ann Arbor, U.S.A.en_US
dc.contributor.affiliationumThe University of Michigan, Ann Arbor, U.S.A.en_US
dc.description.bitstreamurlhttp://deepblue.lib.umich.edu/bitstream/2027.42/22759/1/0000314.pdfen_US
dc.identifier.doihttp://dx.doi.org/10.1016/0306-4549(78)90032-4en_US
dc.identifier.sourceAnnals of Nuclear Energyen_US
dc.owningcollnameInterdisciplinary and Peer-Reviewed


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