Abstract
The $^{241}\mathrm{Am}(n,2n)^{240}\mathrm{Am}$ reaction cross section has been measured at four energies, 10.0, 10.4, 10.8, and 17.1 MeV, by means of the activation technique, relative to the $^{27}\mathrm{Al}(n,\ensuremath{\alpha})^{24}\mathrm{Na}$ reaction reference cross section. Quasi-monoenergetic neutron beams were produced via the $^{2}\mathrm{H}(d,n)^{3}\mathrm{He}$ and the $^{3}\mathrm{H}(d,n)^{4}\mathrm{He}$ reactions at the 5.5 MV Tandem T11/25 accelerator laboratory of NCSR ``Demokritos''. The high purity $^{241}\mathrm{Am}$ targets were provided by JRC-IRMM, Geel, Belgium. The induced $\ensuremath{\gamma}$-ray activity of $^{240}\mathrm{Am}$ was measured with high-resolution high-purity germanium (HPGe) detectors. Auxiliary Monte Carlo simulations were performed with the mcnp code. The present results are in agreement with data obtained earlier and predictions obtained with the empire code.
Highlights
The determination of (n,xn) reaction cross sections is important for the development of fast reactors, since the neutron balance in the core of the reactor is affected by the neutron multiplication caused by such reactions
The 241Am(n,2n) 240Am reaction cross section has been measured at four energies, 10.0, 10.4, 10.8, and 17.1 MeV, by means of the activation technique, relative to the 27Al(n,α) 24Na reaction reference cross section
The 241Am(n,2n) 240Am reaction cross section has been measured at four energies in the range between 10.0 and 17.1 MeV, by means of the activation technique, relative to the 27Al(n,α) 24Na reaction reference cross section, while results were cross-checked using the 197Au(n,2n) 196Au and 93Nb(n,2n) 92mNb reference reactions
Summary
The determination of (n,xn) reaction cross sections is important for the development of fast reactors, since the neutron balance in the core of the reactor is affected by the neutron multiplication caused by such reactions. The study of the 241Am(n,2n) reaction is important, as Am is one of the most radiotoxic isotopes among the actinides and one of the most abundant components of spent nuclear fuel. Accurate cross section data are needed for many practical applications, especially in the field of nuclear energy and transmutation of radioactive waste. The data of Lougheed et al [2] and Tonchev et al [4] around 14 MeV, are in good agreement, while the data by Filatenkov et al [1] are systematically lower by approximately two standard deviations. The data by Perdikakis et al [3], which have been measured at NCSR “Demokritos”, agree well with the data of both Tonchev et al [4] and Sage et al [5] below 10 MeV. There are, severe discrepancies between the measurements of Refs. [3] and [4] in the energy region between 10 to 12 MeV
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