You need JavaScript to view this

Monte Carlo computed field parameters for design of photon personal dosemeters

Technical Report:

Abstract

The computed field parameters, collision kerma backscatter factor, backscattered radiation mean energy and their dependence on radiation incident angle, as well as, the ICRU operational quantity directional dose equivalents H`(0.07, omega) H`(3, omega) and H`(10, omega) were computed for a spherical phantom composed of the tissue substitute material RS-1, which demonstrated its characteristics very similar to the ICRU theoretical material. The calculations were carried out with the Monte Carlo code MCNP (Monte Carlo for Neutrons and Photons). These data together with energy response experimental data allowed the optimization of the design procedure of personal dosemeters in terms of the new operational quantities as defined by ICRU 39-43 in the energy range from 20 to 1250 keV. The relationship between the dosemeter response and the quantity directional dose equivalent H`(d, omega), (where d is the depth in the phantom and omega is the incident angle) was expressed by a semi-empirical formula, based on the theoretically expected interaction of the dosemeter when placed on a suitable phantom with a photon beam of known spectrum, as well as, on the experimental energy response of the bare detector when irradiated in free air with reference photon beams. Moreover, the presence of filtration, could be  More>>
Authors:
Fantuzzi, E; Gualdrini, G F; Morelli, B; Monteventi, F [1] 
  1. ENEA, Bologna (Italy)
Publication Date:
Dec 01, 1993
Product Type:
Technical Report
Report Number:
ETDE-IT-93-247; CONF-9304196-2
Reference Number:
SCA: 440102; 560101; PA: ITA-93:001396; NTS-94:008005; EDB-94:020903; ERA-19:007313; SN: 93001118002
Resource Relation:
Conference: Austrian-Italian-Hungarian radiation protection symposium,Obergurgl (Austria),28-30 Apr 1993; Other Information: PBD: 1993
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 61 RADIATION PROTECTION AND DOSIMETRY; TISSUE-EQUIVALENT MATERIALS; DOSE EQUIVALENTS; DEPTH DOSE DISTRIBUTIONS; THERMOLUMINESCENT DOSEMETERS; COMPUTER-AIDED DESIGN; MONTE CARLO METHOD; PHOTON TRANSPORT; PERSONNEL DOSIMETRY; ICRU; EXPERIMENTAL DATA; VALIDATION; 440102; 560101; RADIATION DOSEMETERS; DOSIMETRY AND MONITORING
OSTI ID:
10115120
Research Organizations:
No corporate text available (Country unknown/Code not available)
Country of Origin:
Italy
Language:
English
Other Identifying Numbers:
Other: ON: DE94727314; TRN: IT9301396
Availability:
OSTI; NTIS (US Sales Only)
Submitting Site:
ITA
Size:
4 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Fantuzzi, E, Gualdrini, G F, Morelli, B, and Monteventi, F. Monte Carlo computed field parameters for design of photon personal dosemeters. Italy: N. p., 1993. Web.
Fantuzzi, E, Gualdrini, G F, Morelli, B, & Monteventi, F. Monte Carlo computed field parameters for design of photon personal dosemeters. Italy.
Fantuzzi, E, Gualdrini, G F, Morelli, B, and Monteventi, F. 1993. "Monte Carlo computed field parameters for design of photon personal dosemeters." Italy.
@misc{etde_10115120,
title = {Monte Carlo computed field parameters for design of photon personal dosemeters}
author = {Fantuzzi, E, Gualdrini, G F, Morelli, B, and Monteventi, F}
abstractNote = {The computed field parameters, collision kerma backscatter factor, backscattered radiation mean energy and their dependence on radiation incident angle, as well as, the ICRU operational quantity directional dose equivalents H`(0.07, omega) H`(3, omega) and H`(10, omega) were computed for a spherical phantom composed of the tissue substitute material RS-1, which demonstrated its characteristics very similar to the ICRU theoretical material. The calculations were carried out with the Monte Carlo code MCNP (Monte Carlo for Neutrons and Photons). These data together with energy response experimental data allowed the optimization of the design procedure of personal dosemeters in terms of the new operational quantities as defined by ICRU 39-43 in the energy range from 20 to 1250 keV. The relationship between the dosemeter response and the quantity directional dose equivalent H`(d, omega), (where d is the depth in the phantom and omega is the incident angle) was expressed by a semi-empirical formula, based on the theoretically expected interaction of the dosemeter when placed on a suitable phantom with a photon beam of known spectrum, as well as, on the experimental energy response of the bare detector when irradiated in free air with reference photon beams. Moreover, the presence of filtration, could be taken into account to improve its performance through a term allowing for the beam attenuation. The Monte Carlo computed parameters allowed the solution of the semi-empirical formula and therefore the simulation of dosemeter response for each value of incidence angle and energy radiation in terms of H`(0.07, omega) or H`(10, omega) in the energy domain of interest.}
place = {Italy}
year = {1993}
month = {Dec}
}