NEUTRON SPECTROMETRY AND DOSIMETRY IN SPECIFIC LOCATIONS AT 2 CANDU(R) POWER-PLANTS

Citation
Jc. Nunes et al., NEUTRON SPECTROMETRY AND DOSIMETRY IN SPECIFIC LOCATIONS AT 2 CANDU(R) POWER-PLANTS, Radiation protection dosimetry, 63(2), 1996, pp. 87-104
Citations number
28
Categorie Soggetti
Radiology,Nuclear Medicine & Medical Imaging","Nuclear Sciences & Tecnology
ISSN journal
01448420
Volume
63
Issue
2
Year of publication
1996
Pages
87 - 104
Database
ISI
SICI code
0144-8420(1996)63:2<87:NSADIS>2.0.ZU;2-2
Abstract
Neutron monitoring was carried out in locations of interest to the hea lth physics staff at two CANDU(R) power plants in Ontario, Canada. Spe ctrometry and dosimetry were performed using Bonner sphere and TEPC sy stems, a moderator-type dose equivalent meter (a SNOOPY) and a damage track dosemeter (CR-39). The purposes of this investigation were to co mpare dose equivalent estimates from different measuring systems and t o determine neutron fluence spectra for evaluation of instrument dose equivalent response. The fluence spectra were found to be fairly soft in general, with at least 50% of the total fluence falling below 200 k eV. Relative to ambient dose equivalents derived from the Bonner spher e system, SNOOPY readings were typically 1 to 2 times larger, measured CR-39 values were within a factor of around 2 and measured TEPC data were 0.4 to 0.8 times as large.