Thermal Neutron Cross Section and Diffusion Parameters for Plexiglass

G.J. SIBONA; R.E. MAYER; V.H. GILLETTE; C. BONETTO

ANNALS OF NUCLEAR ENERGY

PERGAMON-ELSEVIER SCIENCE LTD

Lugar: Amsterdam; Año: 1991 vol. 18 p. 689 - 696

0306-4549

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 designproblems, including energy-transfer kernels and thermal neutron diffusion parameters. These experimental and theoretical results are compared with available data for Plexiglass.