Published 2011 | Version v1
Journal article

A comparison between Monte Carlo-calculated and -measured total efficiencies and energy resolution for large plastic scintillators used in whole-body counting

  • 1. Dept. of Radiation Physics, Inst. of Clinical Sciences, The Sahlgrenska Academy, Univ. of Gothenburg, SU/Sahlgrenska, 413 45 Gothenburg (Sweden)

Description

The measured total efficiency for several source positions has been determined for a large, plastic scintillation detector (NE 102A, 91.5 x 76.0 x 24.5 cm3) used for whole-body counting gamma spectrometry. The results have been compared with Monte Carlo-calculated total efficiencies; the code used was MCNPX 2.60. For 137Cs, there was a good agreement between the measured and calculated total efficiencies. MXNPX was also used to calculate the electron light yield for 137Cs; for the detector material NE 102A, Birks' constant kB was found to be 9.6 mg cm-2 MeV-1. The effect of light losses on spectrum resolution has been investigated for 65Zn. (authors)

Availability note (English)

Available from doi: http://dx.doi.org/10.1093/rpd/ncq340

Additional details

Identifiers

Publishing Information

Journal Title
Radiation Protection Dosimetry
Journal Volume
144
Journal Issue
1-4
Journal Page Range
p. 555-559
ISSN
0144-8420

Conference

Title
European conference on individual monitoring of ionising radiation
Acronym
IM2010
Dates
8-12 Mar 2010
Place
Athens (Greece)

Optional Information

Notes
8 refs