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Antunes, L.J.; Borker, G.; Klein, H.; Bulski, G.
Nuclear data for basic and applied science. Volume 21985
Nuclear data for basic and applied science. Volume 21985
AbstractAbstract
[en] The energy distribution of a ''monoenergetic'' and a ''white'' neutron source were determined with an NE 213 detector system by neutron time-of-flight spectroscopy and by the unfolding of the simultaneously measured scintillation pulse height spectra. Both the neutron detection efficiency necessary for the normalization of the TOF spectra and the set of reference spectra used in the matrix inversion procedure were calculated by Monte Carlo simulations based on identical data sets. The fluence distributions resulting from these different methods agreed reasonably well over the entire energy range. In particular, the integrated fluence of well isolated peaks agreed within the 2% uncertainty estimated for this ratio
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Young, P.G.; Brown, R.E.; Auchampaugh, G.E.; Lisowski, P.W.; Stewart, L; p. 1375-1378; ISBN 0-677-21340-9;
; 1985; p. 1375-1378; Gordon and Breach; New York, NY (USA); International conference on nuclear data for basic and applied science; Santa Fe, NM (USA); 13-17 May 1985

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