Comprehensive sets of ${}^{124}\mathrm{Xe}(n,\gamma ){}^{125}\mathrm{Xe}$ and ${}^{124}\mathrm{Xe}(n,2n){}^{123}\mathrm{Xe}$ cross-section data for assessment of inertial-confinement deuterium-tritium fusion plasma

Measurements of the neutron radiative-capture cross section of ${}^{124}\mathrm{Xe}$ have been performed for the first time for neutron energies above 100 keV. In addition, data for the ${}^{124}\mathrm{Xe}\left(n,2n\right){}^{123}\mathrm{Xe}$ reaction cross section have been obtained from threshold to 14.8 MeV to cover the entire energy range of interest, while previous data existed only at around 14 MeV. The results of these measurements provide the basis for an alternative and sensitive diagnostic tool for investigating properties of the inertial confinement fusion plasma in deuterium-tritium (DT) capsules at the National Ignition Facility located at Lawrence Livermore National Laboratory. Here, areal density $\rho R$ (density $\times$ radius) of the fuel, burn asymmetry, and fuel-ablator mix are of special interest. The ${}^{124}\mathrm{Xe}\left(n,\gamma \right){}^{125}\mathrm{Xe}$ reaction probes the down-scattered neutrons, while the ${}^{124}\mathrm{Xe}\left(n,2n\right){}^{123}\mathrm{Xe}$ reaction provides a measure of the 14 MeV direct neutrons.

Figure 1

Schematic of deuterium-tritium capsule used in laser shots at the National Ignition Facility.

Figure 2

Schematic of experimental setup consisting of neutron production target, ${}^{124}\mathrm{Xe}$ high-pressure sphere with monitor foils, and neutron flux detector.

Figure 3

Partial level scheme relevant to the ${}^{124}\mathrm{Xe}\left(n,\gamma \right){}^{125}\mathrm{Xe}$ reaction. All energies are given in keV. Data taken from [18].

Figure 4

Partial level scheme relevant to the ${}^{124}\mathrm{Xe}\left(n,2n\right){}^{123}\mathrm{Xe}$ reaction. All energies are given in keV. Data taken from [18].

Figure 5

${}^{124}\mathrm{Xe}\left(n,\gamma \right){}^{125}\mathrm{Xe}$ cross-section data obtained in the present work in comparison to the evaluations ENDF-B/VII.1 [8] and JENDL-4.0 [24], and the model calculation TENDL-2012 [25].

Figure 6

${}^{124}\mathrm{Xe}\left(n,2n\right){}^{123}\mathrm{Xe}$ cross-section data in comparison to evaluations [8, 24, 25] and previous data [11, 12, 13]. The calculations of TENDL-2012 and TENDL-2013 are identical.