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Study of the 241Am(n,2n)240Am reaction cross section in the energy range of En = 8.8-11.1 MeV

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dc.contributor.author Perdikakis, G en
dc.contributor.author Papadopoulos, CT en
dc.contributor.author Kokkoris, M en
dc.contributor.author Vlastou, R en
dc.contributor.author Galanopoulos, S en
dc.contributor.author Lagoyannis, A en
dc.contributor.author Spyrou, A en
dc.contributor.author Kalyva, G en
dc.contributor.author Patronis, N en
dc.date.accessioned 2014-03-01T02:44:58Z
dc.date.available 2014-03-01T02:44:58Z
dc.date.issued 2007 en
dc.identifier.issn 02365731 en
dc.identifier.uri https://dspace.lib.ntua.gr/xmlui/handle/123456789/32055
dc.subject Activity Techniques en
dc.subject Cross Section en
dc.subject Reference Material en
dc.subject.other aluminum en
dc.subject.other americium en
dc.subject.other gold en
dc.subject.other lead en
dc.subject.other niobium en
dc.subject.other aluminum foil en
dc.subject.other chemical reaction en
dc.subject.other conference paper en
dc.subject.other electric potential en
dc.subject.other electron accelerator en
dc.subject.other foil en
dc.subject.other measurement en
dc.subject.other monitoring en
dc.subject.other neutron en
dc.subject.other neutron activation analysis en
dc.subject.other nuclear energy en
dc.subject.other radioactivity en
dc.subject.other sensor en
dc.subject.other target variable en
dc.title Study of the 241Am(n,2n)240Am reaction cross section in the energy range of En = 8.8-11.1 MeV en
heal.type conferenceItem en
heal.identifier.primary 10.1007/s10967-007-0504-7 en
heal.identifier.secondary http://dx.doi.org/10.1007/s10967-007-0504-7 en
heal.publicationDate 2007 en
heal.abstract The measurement of the cross section of the reaction 241Am(n,2n) 240Am has been performed at neutron energies from 8.8 to 11.1 MeV, implementing the activation technique. The neutron beam was produced at the TANDEM accelerator of NCSR ""Demokritos"" by the 2H(d,n) 3He reaction, using a deuterium gas target. During the 5-day long irradiation, the neutron beam fluctuations were monitored in 100 seconds intervals by a BF3 counter connected with a multiscaling unit. The radioactive target consisted of a 37 GBq 241Am source enclosed in a Pb container. A natural Au foil, a 27Al foil and a 93Nb foil were used as reference materials for the neutron flux determination. After the end of the irradiation the activity induced at the target and the reference foils, was measured off-line by a 56% HPGe detector. © 2007 Akadémiai Kiadó. en
heal.journalName Journal of Radioanalytical and Nuclear Chemistry en
dc.identifier.doi 10.1007/s10967-007-0504-7 en
dc.identifier.volume 272 en
dc.identifier.issue 2 en
dc.identifier.spage 223 en
dc.identifier.epage 226 en


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