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
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.