Accession Number : AD0618922

Title :   FAST-NEUTRON SCATTERING FROM SMALL CYLINDERS OF STEEL, ALUMINUM, AND GRAPHITE,

Corporate Author : OAK RIDGE NATIONAL LAB TENN

Personal Author(s) : Courtney,John C.

Report Date : JUL 1965

Pagination or Media Count : 106

Abstract : Time-of-flight methods were used to measure the spectra of fast neutrons scattered at angles of 20, 45, 70, 110, and 160 deg from the incident beam by small (2-in.-diam, 2.5-in.-high) cylinders of steel, aluminum, and graphite. The energy spectrum of the neutrons approximated a fission spectrum. Some of the neutrons struck the scattering sample, which was placed 13 in. from the source, passed through a system of collimators, down a drift tube, and into a liquid scintillator fastneutron detector. Measured source spectra were used as input for Monte Carlo calculations of the scattered neutrons, and the results were compared with measured scattered spectral intensities. The calculations and experiments, integrated over energy, agreed within 16%. These comparisons indicate that the ORNL crosssection library for these elements is adequate to handle neutron scattering calculations. (Author)

Descriptors :   (*SHIELDING, NEUTRON SCATTERING), (*FAST NEUTRONS, NEUTRON SCATTERING), (*NEUTRON SCATTERING, MEASUREMENT), (*STEEL, NEUTRON SCATTERING), (*ALUMINUM, NEUTRON SCATTERING), (*GRAPHITE, NEUTRON SCATTERING), NEUTRON SPECTRUM, NEUTRON BEAMS, BREMSSTRAHLUNG, NEUTRON DETECTORS, SCINTILLATION COUNTERS, MONTE CARLO METHOD, NEUTRON CROSS SECTIONS

Distribution Statement : APPROVED FOR PUBLIC RELEASE