The ICRU Proposal for New Operational Quantities for External Radiation

Radiation Safety Assessment in Prostate Cancer Treatment: A Predictive Approach for I-125 Brachytherapy

This study uses Monte Carlo simulation and experimental measurements to develop a predictive model for estimating the external dose rate associated with permanent radioactive source implantation in prostate cancer patients. The objective is to estimate the accuracy of the patient's external dose rate measurement. First, I-125 radioactive sources were implanted into Mylar window water phantoms to simulate the permanent implantation of these sources in patients. Water phantom experimental measurement was combined with Monte Carlo simulation to develop predictive equations, whose performance was verified against external clinical data. The model's accuracy in predicting the external dose rate in patients with permanently implanted I-125 radioactive sources was high (R2 = 0.999). A comparative analysis of the experimental measurements and the Monte Carlo simulations revealed that the maximum discrepancy between the measured and calculated values for the water phantom was less than 5.00%. The model is practical for radiation safety assessments, enabling the evaluation of radiation exposure risks to individuals around patients with permanently implanted I-125 radioactive sources.

Response of current dosemeters to new operational quantities in rotational geometry

Recently, the ICRU released Report 95, where new operational quantities for external radiation exposure are defined. The new quantities are defined in close relation to the protection quantities. This change affects the practice use of dosemeters. That is why the instruments must be adapted to the measurement of new quantities before their implementing as legally binding. The discrepancies depend on radiation spectra-particle type, energy of particles and direction of incidence. To analyse the performance of currently used instruments, irradiations in photon and neutron fields of various energies were performed for personal and area dosemeters. In this work, the response of photon and neutron personal dosemeters in conditions of rotational geometry is presented. The difference between the responses with respect to the new or old operational quantity was not large, which corresponded to the similar reference values for this irradiation geometry. The mutual ratio depended on the specific radiation quality and geometry. The behaviour of different types of dosemeters varied too.

RESPONSE OF CURRENT AREA DOSEMETERS TO NEW OPERATIONAL QUANTITIES

New operational quantities for external radiation exposure presented by the ICRU brought changes, which can affect the use of current dosemeters. Dosemeters calibrated in the old quantities should be tested, and the results obtained should be analyzed with respect to the new quantities. The difference between the old and new quantities depends primarily on photon energy. This work concerns instruments for area monitoring, which were exposed to reference photon and neutron spectra of mean energies from 65 to 1250 keV and from 0.02 to 10 MeV, respectively. As expected, it was revealed that the current photon dosemeters overestimate the new quantity ambient dose. For the measurements within the energy interval chosen, it seems to be acceptable to implement a correction factor to optimize the response. For the purposes of measurements of photons of lower energies, further research would be needed. To adapt the response of the neutron dosemeter tested, recalibration or redesign can be considered, but no fundamental changes seem to be necessary for the investigated spectra.

Conversion coefficients from total air kerma to the newly proposed ICRU/ICRP operational quantities for radiation protection for photon reference radiation qualities

The International Commission on Radiation Units and Measurements (ICRU) has recently proposed a set of new operational quantities for radiation protection. ICRU supplied conversion coefficients for mono-energetic photons but not for photon reference radiation qualities defined by the International Organization for Standardization (ISO) in ISO 4037 and by the International Electrotechnical Commission (IEC) in IEC 61267. Therefore, in this work, conversion coefficients from total air kerma to the newly proposed operational quantities are averaged for photon reference radiation qualities. Also, parameters necessary to determine the influence of the air density on the conversion coefficients are determined. Finally, the impact of the newly proposed quantities upon the response of dosemeters is investigated.

Impact of new operational dosimetric quantities on individual monitoring services

The new operational dosimetric quantities framework, proposed in the ICRU95 report, has stimulated the scientific community to start investigations that aim to assess its impact on radiation protection practices. As part of this effort, the present study describes an inter-comparison exercise among individual monitoring services (IMSs) on passive whole-body dosimetry. The inter-comparison is performed in terms of both the existing operational dose quantityHp(10)and its proposed replacementHp, to allow an evaluation of the actions that may be necessary to adapt dosimetry systems to the proposed quantity. For two of the tested IMSs, simple modifications to the detector response function, or the dose calculation algorithm, were sufficient to obtain results within acceptable limits. However, these approaches are not sufficient to give a level of performance comparable to that achieved in terms ofHp(10). This may require a modification to dosemeter design.

RESPONSE OF CURRENT PHOTON PERSONAL DOSEMETERS TO NEW OPERATIONAL QUANTITIES

The ICRU proposed new operational quantities, which are defined in close relation to effective dose and absorbed dose. Most of the current personal dosemeters were designed to measure personal dose equivalents. Because of differences between the new and old quantities, the existing dosemeters may not be ideal for measurements of the new quantities, personal dose, Hp, and absorbed dose in local skin, Dp local skin. For photon radiation sources, we investigated relative responses of the current personal dosemeters with respect to the measurement of the new quantities. Introduction of the new quantities into practice will require some changes in practical radiation protection. A recalibration of the current dosemeters will be essential for Hp measurements in higher photon energy region (>50 keV). For lower photon energies, a redesign of specific evaluation algorithms will be necessary. For purposes of Dp local skin measurements the dosemeters do not require any fundamental changes.

Development of a realistic 3D printed eye lens dosemeter using CAD integrated with Monte Carlo simulation

Recent epidemiological studies suggested to lower the threshold dose for radiation induced cataract in the eye lens. Therefore, eye lens radiation protection became to play a more important role in personal dosimetry. The main objective of this work is to propose a new methodology for prototyping and benchmarking of an eye lens dosimter based on the equivalent dose to the sensitive part of the eye lens, using CAD Software and Geant4 Monte Carlo simulations with mesh modelling and 3D printing. A 3D printed dosemeter was type tested based on IEC 62387:2012, in terms of energy and angular dependence for the measurements of Hp(3). The results show that the methodology employed is suitable for the development of new eye lens dosemeters.

Impact of the newly proposed ICRU/ICRP quantities on neutron calibration fields and extended range neutron rem-counters

In July 2017, the International Commission on Radiation Units and Measurements (ICRU) and the International Commission on Radiological Protection (ICRP) proposed the introduction of new operational quantities for external radiation exposure, with the aim of improving coherence between protection quantities and operational quantities within the system of radiological protection. A change in operational quantities will impact both instrumentation and reference radiation fields used for their calibration. This paper evaluates the potential impact of the new quantity ambient dose, H*, meant to replace ambient dose equivalent, H*(10), on two neutron reference fields, the Am-Be source and the CERF high-energy workplace field, and on the response of two models of extended-range neutron rem counters (LINUS and LUPIN). The conclusions are that calibration procedures should in general not be affected and that changes should only be expected in calibration coefficients. Considering the acceptable measurement uncertainties for operational radiation protection, for the extended-range rem counters changes in their design would not be required for measurements outside particle accelerators shielding and for aircrew dosimetry. One can expect that this type of instrument can still be calibrated with Am-Be source neutrons and employed in neutron fields with energy distributions spanning several decades. For uses in radiation fields with very peculiar neutron energy distribution, a specific workplace field calibration may instead be required.

Development of a detector for the measurement of ambient dose equivalent, H∗(10) at low and medium photon energies

Ionization chambers are used as secondary standards for the dosimetric measurement of photon radiation as the current generated in it are directly proportional to the conventional true value of the monitoring quantity (i.e. air kerma, dose or ambient dose equivalent). The wall thickness of ionization chamber plays an important role in the dosimetric measurement of photon energies below 200 keV. A 10 mm thick, poly methyl methacrylate walled, cylindrical ionization chamber having 225 cm³ volume was developed to study ambient dose equivalent rate based response at photon energies below 200 keV. The developed ionization chamber shows a near flat energy response for the monitoring of ambient dose equivalent in the energy range 30-200 keV. It also fulfills the ISO 4037-4 requirements concerning the quality of a secondary standard dosimeter in the energy range ∼15-200 keV.