Fission cross section

The feasibility of the synthesis of the 309,312126 isotopes via the mentioned systems is investigated based on the widths. The widths in the excitation energy range of E= 10 – 100 MeV are calculated in the scope of the statistical model, in which the level density is calculated by using the Fermi-gas model. By employing the LISE++ code, the level densities the compound nuclei, 309,312126 nuclei, are calculated to be about 105 – 1050 (MeV−1 ) in the energy range of interest

8p larachdumlanat127 02-01-2021 5 1   Download

This paper presents a Bayesian approach based on integral experiments to create correlations which do not appear with differential data. Some quantities such as the fission cross section (s), neutron multiplicity (n¯p), neutron spectra (x), etc. are usually neither modeled together nor measured in coincidence, thus there is no correlation matrices in evaluated nuclear data libraries.

8p christabelhuynh 30-05-2020 13 0   Download

The effects of nuclear data uncertainties are studied on a typical PWR fuel assembly model in the framework of the OECD Nuclear Energy Agency UAM (Uncertainty Analysis in Modeling) expert working group. The “Fast Total Monte Carlo” method is applied on a model for the Monte Carlo transport and burnup code SERPENT. Uncertainties on k∞, reaction rates, two-group cross sections, inventory and local pin power density during burnup are obtained, due to transport cross sections for the actinides and fission products, fission yields and thermal scattering data.

10p minhxaminhyeu5 30-06-2019 12 0   Download