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1.
Radiat Prot Dosimetry ; 144(1-4): 473-7, 2011 Mar.
Article in English | MEDLINE | ID: mdl-21335629

ABSTRACT

The ORAMED (Optimization of RAdiation protection for MEDical staff) project is funded by EU-EURATOM within the 7° Framework Programme. Task 2 of the project is devoted to study the dose to the eye lens. The study was subdivided into various topics, starting from a critical revision of the operational quantity H(p)(3), with the corresponding proposal of a cylindrical phantom simulating as best as possible the head in which the eyes are located, the production of a complete set of air kerma to dose equivalent conversion coefficients for photons from 10 keV to 10 MeV, and finally, the optimisation of the design of a personal dosemeter well suited to respond in terms of H(p)(3). The paper presents some preliminary results.


Subject(s)
Lens, Crystalline/radiation effects , Occupational Exposure/prevention & control , Radiation Monitoring/instrumentation , Radiation Protection/instrumentation , Radiometry/instrumentation , Air , Algorithms , Calibration , Equipment Design , Head/radiation effects , Humans , Monte Carlo Method , Phantoms, Imaging , Radiation Dosage , Radiation Monitoring/methods , Radiation Protection/methods , Radiometry/methods , Scattering, Radiation
2.
Radiat Prot Dosimetry ; 125(1-4): 145-8, 2007.
Article in English | MEDLINE | ID: mdl-17261537

ABSTRACT

Hp(3) has been defined as the operational quantity for eye lens dosimetry. Hp(3)/ka conversion coefficients were evaluated at the GSF (Germany) in a 30x30x15 cm3 4-elements ICRU slab phantom for various energies and incident angles through Monte Carlo. The ISO report 12,794 suggests to employ a PMMA water filled phantom, of the same dimensions, for dosemeter calibration in terms of Hp(3). The present paper briefly summarises the main aspects of a study carried out at ENEA-Radiation Protection Institute (Bologna, Italy) to provide practical procedures for the calibration of dosemeters in terms of Hp(3). Tabulations of a new set conversion coefficients and air kerma backscatter factors are provided as a function of energy and incident angle. The paper demonstrates that a more accurate approach to the dosimetric assessment in terms of Hp(3) could be rather simply introduced employing a reduced phantom.


Subject(s)
Models, Biological , Models, Statistical , Monte Carlo Method , Occupational Exposure/analysis , Radiation Monitoring/methods , Radiation Protection/methods , Software , Algorithms , Body Burden , Computer Simulation , Internationality , Italy , Occupational Exposure/prevention & control , Relative Biological Effectiveness , Reproducibility of Results , Risk Assessment/methods , Sensitivity and Specificity
3.
Radiat Prot Dosimetry ; 115(1-4): 612-5, 2005.
Article in English | MEDLINE | ID: mdl-16381793

ABSTRACT

The ENEA IRP Secondary Standard Dosimetry Laboratory of Bologna (Italy) has been operated for more than 30 y as a secondary standard laboratory for X rays, gamma, beta and neutron radiation metrology. For photon radiation, the instruments for radiation protection and clinical dosimetry are calibrated in agreement with the ISO standards, using remotely controlled irradiation units: two 60Co, one 137Cs and three X-ray units (160, 320 and 420 kV, respectively). The calibration procedures, approved by the National Primary Laboratory, have been recently implemented in a software package, which controls the irradiation units and acquires the reference measurements. The system, developed at the laboratory under the LabVIEW programming language, guarantees a constant surveillance of all devices and operations, avoids procedural mistakes and automates the record-keeping and reporting activities. This results in an increase in the reliability of the calibration service.


Subject(s)
Radiation, Ionizing , Radiometry/instrumentation , Radiometry/standards , Robotics/instrumentation , Robotics/standards , Guidelines as Topic , International System of Units/standards , Internationality , Italy , Radiation Dosage , Reference Standards , Reference Values
4.
Radiat Prot Dosimetry ; 110(1-4): 43-8, 2004.
Article in English | MEDLINE | ID: mdl-15353619

ABSTRACT

At the ENEA Radiation Protection Institute in Bologna a thermal neutron irradiation facility is available for the calibration of neutron dosemeters. It consists of a 1 m x 1 m x 1 m polyethylene cube containing three 241Am-Be sources of about 185 GBq. The cube contains three co-axial cylindrical calibration cavities of different dimension. Due to their limited dimensions, the cavities do not allow the calibration of thermal neutron personal dosemeters in terms of Personal Dose Equivalent Hp(d), that should be carried out on the 30 cm x 30 cm x 15 cm ISO phantom. The study herewith presented was addressed at adapting the facility for external irradiation of personal dosemeters on the ISO phantom. Extensive Monte Carlo studies were carried out to characterise the neutron fluence spatial distribution along the front face of the phantom. A satisfying neutron field homogeneity within the measurement area has been obtained by means of a pyramidal polyethylene fluence flattening filter and the selection of the proper cube to phantom distance. This new irradiation set-up was experimentally tested through measurements with activation foils, according to the spatial mapping array taken from the calculations.


Subject(s)
Equipment Failure Analysis/instrumentation , Equipment Failure Analysis/standards , Neutrons , Radiation Protection/instrumentation , Radiation Protection/standards , Radiometry/instrumentation , Radiometry/standards , Body Burden , Calibration/standards , Equipment Design , Equipment Failure Analysis/methods , Humans , Internationality , Italy , Occupational Exposure/analysis , Occupational Exposure/standards , Radiation Dosage , Radiation Protection/methods , Radiometry/methods , Reference Standards , Relative Biological Effectiveness , Reproducibility of Results , Sensitivity and Specificity
5.
Radiat Prot Dosimetry ; 100(1-4): 381-4, 2002.
Article in English | MEDLINE | ID: mdl-12382903

ABSTRACT

The energy dependence of the response function S(E), of CaF2:Tm (TLD-300) thermoluminescent material (3.2 x 3.2 x 0.90 mm3 ribbons) was measured from 6 keV up to 1250 keV (60Co) using 55Fe, 137Cs and 60Co gamma ray sources as well as X ray ISO reference beams. To the best knowledge of the authors the data for energies below 45 keV are reported for the first time. The S(E) function was also calculated in the energy range from 1 keV up to 20 MeV and compared with the experimental data relative to the total glow curve. The comparison shows good agreement from 1250 keV down to 40 keV. At lower energy the discrepancy increases. This is interpreted in terms of the X ray attenuation within the thickness of TLD-300. Finally, measurements point out the effects of different reading and annealing treatments on the measured function S(E).


Subject(s)
Thermoluminescent Dosimetry/methods , Calcium Fluoride/chemistry , Calcium Fluoride/radiation effects , Gamma Rays , Luminescent Measurements , Radiochemistry , Sensitivity and Specificity , Thermoluminescent Dosimetry/statistics & numerical data , Thulium/chemistry , X-Rays
6.
Radiat Prot Dosimetry ; 96(1-3): 187-90, 2001.
Article in English | MEDLINE | ID: mdl-11586726

ABSTRACT

Although, at present, neither Italian legislation nor technical protocols require that personal dosimetry is performed to assess Hp(d), the ENEA Individual Monitoring Service (IMS) is able to supply thermoluminescence (TL) whole-body and extremity dosemeters for photon and beta fields, based on LiF(Mg,Cu,P) detectors and these have been fully developed at the ENEA Institute for Radiation Protection (IRP). All irradiation tests have been performed with ISO phantoms and ISO recommended reference radiations at the ENEA-IRP Secondary Standard Dosimetry Laboratory. The whole-body dosemeter contains two LiF(Mg,Cu,P) (GR200) detectors that are filtered differently. One is filtered on both sides by 290 mg.cm-2 mass per area (270 mg.cm-2 Al + 20 mg.cm-2 plastic protective layer); the other is filtered on both sides by a plastic layer of 20 mg.cm-2 mass per area. In photon radiation fields, the maximum uncertainty due to the energy dependence of the response, is +/- 4% for Hp(0.07) in the energy range 13 keV to 202 keV, and +/- 15% for Hp(10) in the range 13 keV to 1.25 MeV. The dosemeter response in terms of Hp(d,alpha) in beta fields has been investigated recently. The results of a EURADOS trial performance test for photon and beta fields are reported and discussed in this paper. The extremity dosemeter currently used at ENEA IMS consists of a GR200 detector glued on a kapton strip identified by a bar code. Its response in terms of Hp(0.07,alpha) has been measured recently and the results are given. Moreover, different dosemeter assemblies have been tested to compare the performances in photon and beta fields. Therefore, the following three constructions have been prepared: (1) an MCP-Ns (8.5 mg.cm-2 mass per area) detector with a Mylar filter of 0.5 mg.cm-2 mass per area; (2) a polyethylene filter of 12 mg.cm-2 mass per area; and (3) a GR200 (210 mg.cm-2 mass per area) detector with a Mylar filter of 0.5 mg.cm-2. Finally, a brief discussion on international and Italian requirements for personal monitoring is given.


Subject(s)
Occupational Exposure/analysis , Radiation Monitoring/instrumentation , Whole-Body Counting/instrumentation , European Union , Italy , Occupational Exposure/prevention & control , Radiation Dosage , Radiation Monitoring/standards , Radiation Protection , Sensitivity and Specificity
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