Thermal neutron cross sections and diffusion parameters of Plexiglass

The neutron total cross section of Plexiglass has been measured for energies between 10⁻³ and 10³ eV by the transmission method with pulsed-neutron time-of-flight techniques. A calculation based on a synthetic scattering function shows a very good agreement with the measured values over the entire energy range. This model has been used to evaluate other quantities of interest in moderator design problems, including energy-transfer kernels and thermal neutron diffusion parameters. These experimental and theoretical results are compared with available data for Plexiglass.