Spectra and dosimetry of neutrons from various sources shielded by iron

Journal Article · Mon Dec 01 04:00:00 EST 1975 · Nucl. Sci. Eng., v. 58, no. 4, pp. 420-430

OSTI ID:4082288

Ing, H; Cross, W G

Spectra, calculated by Monte Carlo, are presented for neutrons transmitted through various thicknesses of iron from sources of fission neutrons, H$sub 2$O-moderated fission neutrons, D$sub 2$O-moderated fission neutrons, and 14.7-MeV neutrons. The sources were located at the center of iron spheres or were in the form of beams incident normally on slabs. Variations in spectral shapes are discussed from the viewpoint of effects on the response of neutron dosimeters. Effective cross sections (sigma-bar) for threshold detectors $sup 103$Rh, $sup 115$In, $sup 32$S, $sup 237$Np, $sup 232$Th, and $sup 238$U were obtained by averaging the cross sections over the calculated spectra. Average kerma (K-bar), dose equivalent, and maximum dose per n/cm$sup 2$ were also calculated. Curves of sigma-bar/K-bar show the sensitivity of these detectors to spectral changes and permit the computation of correction factors to dosimeter readings. 15 figures. (auth)

• Research Organization: Atomic Energy of Canada Ltd., Chalk River, Ont.
• NSA Number: NSA-33-021584
• OSTI ID: 4082288
• Journal Information: Nucl. Sci. Eng., v. 58, no. 4, pp. 420-430, Journal Name: Nucl. Sci. Eng., v. 58, no. 4, pp. 420-430; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

*INDIUM 115-- NEUTRON REACTIONS
*IRON-- NEUTRON TRANSPORT
*NEPTUNIUM 237-- NEUTRON REACTIONS
*NEUTRON SOURCES-- NEUTRON SPECTRA
*RHODIUM 103-- NEUTRON REACTIONS
*SULFUR 32-- NEUTRON REACTIONS
*THORIUM 232-- NEUTRON REACTIONS
*URANIUM 238-- NEUTRON REACTIONS
641600*
CROSS SECTIONS
MONTE CARLO METHOD
N68100* --Physics (Nuclear)--Neutron Interactions with Matter
SHIELDING