On-the-Fly Sampling of Temperature-Dependent Thermal Neutron Scattering Data for Monte

Le résumé fourni par la source

Temperature can strongly affect the probabilities of certain neutron interactions (fission, capture, scattering, etc.) with materials. These probabilities are referred to in the nuclear community as ‘cross sections’ and are used as inputs for computer simulations. During the lifetime of a nuclear reactor, the core and its surrounding materials will experience a wide range of temperatures. To simulate the neutronic behavior in a realistic core, it is required to pre-store a large amount of cross section data to encompass the entire temperature range a neutron may experience. In recent years, methods have been developed to reduce data storage and obtain the cross section at the desired temperature ‘on-thefly’ during radiation transport simulations using Monte Carlo codes. These methods, however, are not applicable for bound scatterers at thermal energies because of the complicated nature of chemical and binding effects. This work focuses on developing methods to temperature correct the thermal neutron differential scattering cross section ‘on-the-fly’ for incorporation into current online Monte Carlo methods.

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