Measured and calculated differential and total yield cross-section data of Ni-58(n,x alpha) and Cu-63(n,xp) in the neutron energy range from 2.0 to 15.6 MeV

Tsabaris, C; Wattecamps, E; Rollin, G; Papadopoulos, C

dc.contributor.author	Tsabaris, C	en
dc.contributor.author	Wattecamps, E	en
dc.contributor.author	Rollin, G	en
dc.contributor.author	Papadopoulos, C	en
dc.date.accessioned	2014-03-01T01:47:37Z
dc.date.available	2014-03-01T01:47:37Z
dc.date.issued	1998	en
dc.identifier.issn	0029-5639	en
dc.identifier.uri	https://dspace.lib.ntua.gr/xmlui/handle/123456789/25275
dc.subject.classification	Nuclear Science & Technology	en
dc.subject.other	NICKEL	en
dc.subject.other	IRON	en
dc.subject.other	N,P	en
dc.title	Measured and calculated differential and total yield cross-section data of Ni-58(n,x alpha) and Cu-63(n,xp) in the neutron energy range from 2.0 to 15.6 MeV	en
heal.type	journalArticle	en
heal.language	English	en
heal.publicationDate	1998	en
heal.abstract	Double-differential (n, xp) and (n, x alpha) cross-section ratio measurements are performed at the 7-MV Van de Graaff accelerator laboratory for neutron energies between 2.0 and 15.6 MeV.: The following reaction rate ratios are measured: Ni-58(n, x alpha) to Al-27(n, x alpha), Ni-58(n, x alpha) to Ni-58(n,p), Cu-63(n, xp) to Al-27(n, x alpha), and Cu-63(n, xp) to Ni-58(n,p). Protons or alphas are detected by Delta E-Delta E-E telescopes under 14, 51, 79, 109, and 141 deg. The energy spectrum of the emitted particles and the angular yield distribution are measured. First, the measurements provide double-differential cross-section data for Al-27(n, alpha) and Ni-58(n,p) by normalization to the known total yield reference cross-section values. Subsequently, the reaction rate ratios of Ni-58(n, x alpha) and Cu-63(n, xp) to Al-27(n, alpha) or Ni-58(n,p) provide double-differential cross sections of Ni-58(n, x alpha) and Cu-63(n, xp) in b/(MeV. sr). The measured double-differential cross-section data, the particle energy spectra, the angular distributions, and the total yield cross-section data are compared with measured data from literature and with nuclear reaction model calculations performed at the Institute for Reference Materials and Measurements with the computer codes STAPRE-H and EXIFON.	en
heal.publisher	AMER NUCLEAR SOCIETY	en
heal.journalName	NUCLEAR SCIENCE AND ENGINEERING	en
dc.identifier.isi	ISI:000071200500004	en
dc.identifier.volume	128	en
dc.identifier.issue	1	en
dc.identifier.spage	47	en
dc.identifier.epage	60	en