Retrospective dosimetry using synthesized nano-structure hydroxyapatite

Micro and nano-structure hydroxyapatite samples were synthesized via several different methods. The samples were characterised utilising the Fourier transmission infra-red, scanning electron microscope and X-ray diffraction methods, to find out the structure most similar to human tooth enamel, and the best method was found. The electron paramagnetic resonance (EPR) signals of the gamma-irradiated samples were measured using an EPR spectrometer system. A calibration curve was established by irradiation of the samples at four doses of 50-500 mGy. The parameters of the calibration curve, slope and intercept with dose axis are determined by linear regression analysis. This calibration curve can be used for human tooth enamel for retrospective dosimetry purposes.     

Retrospective dosimetry for Latvian workers at Chernobyl

Between 1986 and 1991 approximately 6500 Latvian inhabitants were recruited for clean-up work at the Chernobyl nuclear power plant. Their absorbed doses are usually unknown, because less than half of them had their external exposure officially documented. Clinical investigations show a high morbidity rate for these clean-up workers when compared with that of the general population. In order to understand the causes of their diseases and the impact of ionising radiation, electron spin resonance (ESR) has been used to measure the absorbed doses in human tooth enamel. The doses estimated by ESR were between two and three times higher than previously documented and are in accord with the results of immunological and biological tests. The results may be explained by considering the effects of irradiation caused by long-lived incorporated radionuclides.     

International intercomparison for criticality dosimetry: the case of biological dosimetry

The Institute of Radiation Protection and Nuclear Safety (IRSN) organized a biological dosimetry international intercomparison with the purpose of comparing (i) dicentrics yield produced in human lymphocytes; (ii) the gamma and neutron dose estimate according to the corresponding laboratory calibration curve. The experimental reactor SILENE was used with different configurations: bare source 4 Gy, lead shield 1 and 2 Gy and a 60Co source 2 Gy. An increasing variation of dicentric yield per cell was observed between participants when there were more damages in the samples. Doses were derived from the observed dicentric rates according to the dose-effect relationship provided by each laboratory. Differences in dicentric rate values are more important than those in the corresponding dose values. The doses obtained by the participants were found to be in agreement with the given physical dose within 20%. The evaluation of the respective gamma and neutron dose was achieved only by four laboratories, with some small variations among them.     

Retrospective dosimetry with alumina substrate from electronic components

Alumina substrate can be found in electronic components used in portable electronic devices. The material is radiation sensitive and can be applied in dosimetry using thermally or optically stimulated luminescence. Electronic portable devices such as mobile phones, USB flash discs, mp3 players, etc., which are worn close to the body, can represent personal dosemeters for members of the general public in situations of large-scale radiation accidents or malevolent acts with radioactive materials. This study investigated dosimetric properties of alumina substrates and aspects of using mobile phones as personal dosemeters. The alumina substrates exhibited favourable dosimetry characteristics. However, anomalous fading had to be properly corrected in order to achieve sufficient precision in dose estimate. Trial dose reconstruction performed by means of two mobile phones proved that mobile phones can be used for reconstruction of personal doses.     

Retrospective dosimetry related to chronic environmental exposure.

Radioactive contamination of the environment occurred in the early fifties as a result of the releases from the Mayak plutonium production complex (Southern Urals, Russia). The releases of liquid wastes into the Techa river resulted in chronic exposure of 30,000 residents of the riverside communities. Since 1951 90Sr body burdens have been measured for over half of this cohort. This paper presents the analysis of data on 90Sr in humans and describes the reconstruction of internal doses for these people.     

Biological weighting of absorbed dose in radiation therapy

Absorbed dose is a quantity which is scientifically rigorously defined and used to quantify the exposure of biological objects, including humans, to ionising radiation. There is, however, no unique relationship between absorbed dose and induced biological effects. The effects induced by a given absorbed dose to a given biological object depend also on radiation quality and temporal distribution of the irradiation. In radiation therapy, empirical approaches are still used today to account for these dependencies in practice. In hadron therapy (neutrons, protons, ions), radiation quality is accounted for with a diversity of (almost hospital specific) methods. The necessity to account for temporal aspects is well known in external beam therapy and in high dose rate brachytherapy. The paper reviews the approaches for weighting the absorbed dose in radiation therapy, and focusses on the clinical aspects of these approaches, in particular the accuracy requirements.     

Occupational radiation protection dosimetry in Nigeria

The general features of occupational radiation protection dosimetry in Nigeria within the period 1990-1999 have been summarised. About 640 personnel, representing about 25% of the estimated number of radiation workers in Nigeria, were monitored by the TL dosimetry technique during the period, with the majority being the personnel of the teaching hospitals across the country. Most private establishments, especially the X ray diagnostic centres, operate without dosimetry coverage or supervision by a regulatory authority. The weighted mean of the annual effective dose ranged between 0 and 28.97 mSv with the upper limit of collective effective dose being 18.47 man.Sv per year. The individual risk estimate due to this is about 1.5 x 10(-3) per year and this was among the medical personnel. The value could be more if all radiation workers in the country were monitored.     

Retrospective dosimetry using unheated quartz: a feasibility study

Most attempts to apply retrospective dosimetry to building materials have made use of heated (sensitised) items such as brick or tile ceramic. Unfired materials, such as concrete, are far more widespread in the industrial environment, but unfortunately these cannot be assumed to contain a negligible dose at the time of construction. This paper reports on preliminary attempts to measure, using optically stimulated luminescence (OSL), a dose-depth profile in a new concrete brick which had been given a known dose in the laboratory. The dose distribution in individual samples was measured before and after irradiation using small aliquots each of 65 quartz grains, and also using single grains, extracted from the concrete. Despite the material being very poorly zeroed prior to irradiation, both approaches gave satisfactory results and it is concluded that measurement of individual grains from poorly zeroed building materials can provide useful information on accident doses.     

Measurement quality assurance for ionising radiation dosimetry

The preface of the new ICRU report 76 on ‘MeasurementQuality Assurance for Ionising Radiation Dosimetry’ almostsounds like ‘we have published 75 reports on radiationmeasurements and now, finally, here is one on the quality ofthese measurements’. Over the past decade, meetings likethe Solid State Dosimetry conferences and the Individual Monitoringworkshops in Villigen (1993), Helsinki (2000) and Vienna (2005),whose proceedings have appeared in this journal, dedicated sessionsto the quality assurance     

Biological and physical dosimetry for radiation protection

In the 5^th Framework Programme (5FP) of the European Commission(EC), the European Late Effects Project Group (EULEP) and theEuropean Radiation Dosimetry Group (EURADOS) were funded toco-ordinate research in radiation protection based on theirwell-established experience. This was termed ‘clustering’and was intended to encompass research funded by National Agenciesand that funded directly by     

MOSFET dosimetry on modern radiation oncology modalities

The development of MOSFET dosimetry is presented with an emphasis on the development of a scanning MOSFET dosimetry system for modern radiation oncology modalities. Fundamental aspects of MOSFETs in relation to their use as dosemeters are briefly discussed. The performance of MOSFET dosemeters in conformal radiotherapy, hadron therapy, intensity-modulated radiotherapy and microbeam radiation therapy is compared with other dosimetric techniques. In particular the application of MOSFET dosemeters in the characterisation and quality assurance of the steep dose gradients associated with the penumbra of some modern radiation oncology modalities is investigated. A new in vivo, on-line, scanning MOSFET readout system is also presented. The system has the ability to read out multiple MOSFET dosemeters with excellent spatial resolution and temperature stability and minimal slow border trapping effects.     

Space radiation dosimetry by combination of integrating dosemeters

Generally, individual monitoring is performed with a small personal dosemeter which responds to radiation by giving a necessary operational quantity such as personal dose equivalent. In space, however, such a personal dosemeter has not yet been available and a dose equivalent is estimated through elaborate work using etched track detectors. It would be advantageous if we could simply measure the personal dose of an astronaut using conventional integrating dosemeters only. This possibility is discussed based on the concept of efficiency combination.     

Excess radiation absorbed doses from non-optimised radioiodine treatment of hyperthyroidism

Radioiodine therapy is often the method of choice for treatment of hyperthyroidism because it is considered safe, is relatively inexpensive, and is convenient for the patient and except for occasional hypothyroidism, almost without side effects. Even though radioiodine treatment has been performed for over 50 years, the method of treatment differs from country to country and even from hospital to hospital within the same country. To illuminate such differences 187 radioiodine treatments for Graves' disease at Malm? University Hospital in Sweden have been analysed. Comparative dose calculations were carried out assuming that the individual patients had also been treated according to a number of other protocols in current use. The results show that the protocol used for calculating the administered activity in radioiodine therapy is far from optimised in many hospitals. Following the protocols where the absorbed dose to the thyroid is calculated without any uptake measurements after administration of a test activity, most of the patients were treated with an unnecessarily high activity, as a mean factor of 2.5 times too high and in individual patients up to eight times too high, leading to an unnecessary radiation exposure both for the patient, the family and the public. This is not in accordance with generally accepted radiation protection principles. Using higher activity than necessary will also prolong the patient's stay at the hospital and thus increase the costs for the care. Unnecessarily high activity will also necessitate more long-lasting radiation protection restriction relative to family members when the patient is back home.     

Conversion of absorbed thermal radiation into visible using europium thenoyltrifluoroacetonate

We evaluate the sensitivity and thermal resolution of the fluorescence of europium (III) thenoyltrifluoroacetonate (EuTTA) in order to convert absorbed thermal radiation into visible. We analyze the variation of the fluorescence properties of EuTTA (specifically, amplitude power and lifetime) after absorbed thermal radiation has caused a change in the local temperature of the material. We propose to analyze the thermal dependence of the fluorescence decay with an integral functional. Such operation correlates the variations of lifetime and amplitude in a single value. With this method of analysis, we study one parameter with increased thermal resolution and linear temperature dependence. The thermal resolution achieved with amplitude power is 0.11 K and with lifetime is 0.83 K at 305 K. The sensitivity of the integral functional is 25 nJ/K, yielding an increased thermal resolution of 0.07 K.     

Thermoluminescence dosimetry for quality assurance in radiation therapy

A methodology based on thermoluminescence dosimetry was developed to check the output of teletherapy units and the given doses. It was applied in a hospital as a part of an extemal quality audit programme. Over a 7 year period the mean ratios of the output doses measured by TLDs calibrated free-in-air to the doses measured at the hospital in a 6 MV X ray and in a 60Co unit were 1.000 +/- 0.024 (n = 86) and 0.997 +/- 0.027 (n=61), respectively. TLDs in capsules were attached to the patient's body or to a phantom to assess entrance, exit and midline doses and transmission. Factors were determined experimentally to relate the doses measured with TLDs in capsules and inside the body. The accuracy in given doses with pelvic and tangential breast fields and assessed via 752 in vivo measurements, was considered to be adequately good, taking into account the limitations of the equipment available in the hospital.     

Calibration measurements and standards for radiation protection dosimetry

The safe use of ionising radiation for applications in medicine, electric power production and industrial processes requires accurate measurements that are traceable to national standards. Radiological calibration laboratories provide measurements that may be used to determine the calibration coefficients for personal dosemeters and survey meters. The wide range of ionising radiation applications results in the need for a wide range of reference radiation types and intensities to be available in the calibration laboratory. The methods used and the problems encountered while developing reference radiations are discussed.     

Classical microdosimetry in radiation protection dosimetry and monitoring

Classical microdosimetry concerns the measurement and analysis of the spectrum of radiation energy deposition events in simulated microscopic tissue-equivalent sites. Over the past three decades, classical microdosimetry has been extensively applied for the direct measurement of dosimetric quantities, such as the ambient dose equivalent, and for the spectroscopic properties of tissue-equivalent proportional counters that have led to methods of mixed-field analysis and particle identification. This paper reviews some of the special applications of classical microdosimetry such as the determination of kerma coefficients, differential dosimetry and aviation dosimetry. Also reviewed are some of the technological innovations related to the application of microdosimetry in operational health physics and in particular the development of multi-element proportional counters and detectors based on gas microstrip technology.