A comparison between Monte Carlo-calculated and -measured total efficiencies and energy resolution for large plastic scintillators used in whole-body counting.
The measured total efficiency for several source positions has been determined for a large, plastic scintillation detector (NE 102A, 91.5 × 76.0 × 24.5 cm(3)) 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 (137)Cs, there was a good agreement between the measured and calculated total efficiencies. MXNPX was also used to calculate the electron light yield for (137)Cs; 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 (65)Zn.
Department of Radiation Physics, Institute of Clinical Sciences, The Sahlgrenska Academy, University of Gothenburg, SU/Sahlgrenska, 413 45 Gothenburg, Sweden.
J
J
Nilsson
M
M
Isaksson
D002138:Calibration; D002588:Cesium Radioisotopes / Q000032:analysis; D004583:Electrons; D006801:Humans; D008027:Light; D015233:Models, Statistical; D009010:Monte Carlo Method; D016011:Normal Distribution; D010969:Plastics / Q000032:analysis*; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000295:instrumentation* / Q000379:methods; D011835:Radiation Protection / Q000295:instrumentation* / Q000379:methods; D011874:Radiometry / Q000295:instrumentation* / Q000379:methods; D012588:Scintillation Counting / Q000295:instrumentation* / Q000379:methods; D014915:Whole-Body Counting; D015037:Zinc Radioisotopes / Q000032:analysis
D002588:Cesium Radioisotopes; D010969:Plastics; D015037:Zinc Radioisotopes