Monte Carlo simulations of the pulsed thermal neutron flux in two-region hydrogenous systems (using standard MCNP data libraries)
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Date
2005
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Institute of Nuclear Physics Polish Academy of Sciences
Abstract
Monte Carlo simulations of the pulsed neutron experiment in two- region systems (two
concentric spheres and two coaxial finite cylinders) are presented. The MCNP code is used. Aqueous solutions of H3BO3 or KCl are used in the inner region. The outer region is the moderator of Plexiglas. Standard data libraries of the thermal neutron scattering cross-sections of hydrogen in hydrogenous substances are used. The time-dependent thermal neutron transport is simulated when the inner region has a constant size and the external size of the surrounding outer region is variable. The time decay constant of the thermal neutron flux in the system is found in each simulation. The results of the simulations are compared with results of real pulsed neutron experiments on the corresponding systems.