[en] Neutron energy of deuterium-tritium (D-T) generator plays an important role for the application of nuclear energy and nuclear technology. Based on the deuterium energy losing in tritiated titanium (T-Ti) target and differential cross sections of D-T reaction, an improved theoretical formula for calculating the mean neutron energy irradiating a large solid angle sample was proposed. Besides that, the mean neutron energy was discussed under the actual experimental conditions. The results were compared to the reported ratio values of ⁹⁰Zr(n,2 n)^89m+gZr to ⁹³Nb(n,2 n)^92mNb reaction cross sections ('Zr/Nb' ratio methods) and published theoretical calculated results, respectively. The relative deviations between present work and the 'Zr/Nb' ratio methods are below 0.5% and a higher precision was obtained compared with previous published theoretical method. The present work lays a foundation for the application of D-T neutron source in nuclear technology such as nuclear reaction cross section measurement, calibration of neutron detector, and neutron irradiation tests, etc. (author)

[en] The half-life of ${}^{95m}$Tc and the cross-sections of the ${}^{96}$Ru (n, x) ${}^{95m}$Tc reaction induced by D-T neutrons were measured through the neutron activation technique in combination with off-line γ-ray spectrometry. The neutron beam was generated from the T (d, n) ${}^4$He reaction using the K-400 neutron generator at the Chinese Academy of Engineering Physics (CAEP). Through exponential function fitting and a detailed discussion of the uncertainty evaluation, the measured half-life of ${}^{95m}$Tc was 61.88 ± 0.22 days, which uncertainty is reduced greatly compared with the currently recommended value. Based on the determination of the ${}^{95m}$Tc half-life, the cross-sections of ${}^{96}$Ru (n, x) ${}^{95m}$Tc reaction at the 13.85 ± 0.2, 14.30 ± 0.2 and 14.72 ± 0.2 MeV neutron energies were measured relative to the ${}^{93}$Nb (n, 2n) ${}^{92m}$Nb monitor reaction. Considering the correlations between different attributes, detailed uncertainty propagation was performed by the covariance analysis and the cross-sections were reported with their uncertainties and correlation matrix. Then, experimentally determined cross-sections were analyzed by comparing with the literature data available in the EXFOR database and theoretically calculated values using the TALYS-1.95 and EMPIRE-3.2.3 codes. The accuracy of current experimental results with the thorough uncertainties and covariance information is greatly improved, which is critical for verifying the reliability of the theoretical model and improving the quality of the nuclear database.