Personal monitor glass badge: theoretical dosemeter response calculated with the Monte Carlo transport code MCNPX

Radiat Prot Dosimetry. 2011 Mar;144(1-4):231-3. doi: 10.1093/rpd/ncr009. Epub 2011 Feb 17.

Abstract

This paper describes the results of the simulation of a radiophotoluminescent (RPL) dosemeter with the Monte Carlo transport code MCNPX. The aim of this study is to calculate the response with MCNPX of the RPL dosemeter in terms of equivalent doses H(p) (0.07) and H(p)(10) using X-ray photon radiation qualities N series, together with S-Cs and S-Co nuclide radiation qualities, specified in ISO 4037-1. After comparison with reference values versus experimental results, the deviation of the theoretical responses of the RPL dosemeter proved to be lower than 5 % for reference values and lower than 10 % for experimental results. This good correlation validates the model over the energy range studied.

MeSH terms

  • Cesium Radioisotopes / analysis
  • Cobalt Radioisotopes / analysis
  • Computer Simulation
  • Equipment Design
  • Glass
  • Humans
  • Materials Testing
  • Models, Statistical
  • Monte Carlo Method
  • Photons
  • Radiation Dosage
  • Radiation Monitoring / instrumentation*
  • Radiation Monitoring / methods
  • Radiation Protection / instrumentation*
  • Radiation Protection / methods
  • Reference Values
  • Thermoluminescent Dosimetry / instrumentation*
  • Thermoluminescent Dosimetry / methods

Substances

  • Cesium Radioisotopes
  • Cobalt Radioisotopes