Study on the response of indigenously developed CaSO4:Dy phosphor-based neutron dosemeter.

In the present paper, we report the indigenous development of a neutron-sensitive thermoluminescent dosemeter (TLD) based on CaSO4:Dy Teflon TL disc. The study includes indigenous development of a neutron dosemeter and its response in terms of operational quantity to different energies of neutrons under various irradiation conditions. It was found that the thermal neutron sensitivity of the CaSO4:Dy Teflon neutron disc is about one-third of TLD-600. However, the thermal neutron sensitivity with respect to CaSO4:Dy Teflon gamma disc is about 42 times for in-air irradiation and about 84 times for on-phantom irradiation condition. This newly developed neutron dosemeter can be used as a routine TLD with a slight change in the design of the TLD badge system in the mixed fields of gamma and neutrons of energy up to 500 keV for radiation workers engaged in nuclear fuel cycle operation and other applications.

The role, responsibilities and status of the clinical medical physicist in AFOMP.

This document is the first of a series of policy statements being issued by the Asia-Oceania Federation of Organizations for Medical Physics (AFOMP). The document was developed by the AFOMP Professional Development Committee (PDC) and was endorsed for official release by AFOMP Council in 2006. The main purpose of the document was to give guidance to AFOMP member organizations on the role and responsibilities of clinical medical physicists. A definition of clinical medical physicist has also been provided. This document discusses the following topics: professional aspects of education and training; responsibilities of the clinical medical physicist; status and organization of the clinical medical physics service and the need for clinical medical physics service.

Development of an algorithm for TLD badge system for dosimetry in the field of X and gamma radiation in terms of Hp(10).

In view of the introduction of International Commission on Radiation Units and Measurements operational quantities Hp(10) and Hp(0.07), defined for individual monitoring, it became necessary to develop an algorithm that gives direct response of the dosemeter in terms of the operational quantities. Hence, for this purpose and also to improve the accuracy in dose estimation especially in the mixed fields of X ray and gamma, an algorithm was developed based on higher-order polynomial fit of the data points generated from the dose-response of discs under different filter regions of the present TL dosemeter system for known delivered doses. Study on the response of the BARC TL dosemeter system based on CaSO(4):Dy Teflon thermoluminescence dosemeter discs in the mixed fields of X and gamma radiation was carried out to ensure that the accuracies are within the prescribed limits recommended by the international organisations. The prevalent algorithm, based on the ratios of the disc response under various filters regions of the dosemeter to pure photons, was tested for different proportion of two radiations in case of mixed field dosimetry. It was found that the accuracy for few fields is beyond the acceptable limit in case of prevalent algorithm. The new proposed algorithm was also tested in mixed fields of photon fields and to pure photon fields of varied angles. It was found that the response of the dosemeter in mixed fields of photons and its angular response are satisfactory. The new algorithm can be used to record and report the personal dose in terms of Hp(10) as per the international recommendation for the present TL dosemeter.

Glow peak temperature, supralinearity and LET dependence of TLDs--correlation studies.

The study of the well separated low and high temperature glow peaks in CaSO4:Dy and CaF2:Tm was undertaken to develop comparative data on supralinearity of low and high temperature glow peaks for their use in the estimation of elapsed time of exposure and to analyse their responses to low and high-linear energy transfer (LET) radiation. In CaSO4:Dy, unlike its dosimetric peak, the structure of glow peaks at approximately 140 and 400 degrees C remains unchanged (peak position changes within 4 degrees C) with 60Co gamma-ray exposure up to 1 kGy air kerma. The glow peaks at 140 degrees C exhibited higher supralinearity than that of the peaks at 240 and 400 degrees C. In CaF2:Tm, 110 degrees C glow peak exhibited higher supralinearity and higher response to high-LET radiation as compared with 150 degrees C glow peak. No correlation between glow peak temperature and supralinearity or the LET response was observed.

Correlation of phase transition with the change in TL characteristics in CaSO4:Dy phosphor--effect of thermal treatment.

The study is aimed at optimising the glow curve structure of CaSO4:Dy phosphor for dosimetric purpose and also to understand the observed changes owing to thermal treatment in the thermoluminescence (TL) sensitivity and glow curve structure. The reversible changes in the intensities of the lower temperature satellite peak and the main dosimetric glow peak with temperature of thermal treatment in the temperature range 400-700 degrees C indicates the interconversion of defect complexes responsible for the glow peaks in CaSO4:Dy. Phosphor samples subjected to thermal treatment in temperature range beyond 800 degrees C, showed irreversible changes in the intensities of the lower temperature and dosimetric peaks. The changes in TL characteristics of the phosphor for thermal treatments >800 degrees C are attributed to the partial phase transition in the phosphor as confirmed by the XRD and TG/DTA analysis of the phosphor.

Comparison of observed skeleton retention of strontium in average indian adult with the value predicted by the ICRP biokinetic model.

The daily dietary intake of strontium and its content in skeleton, for an Indian adult population group were estimated by experimentally measuring its concentration in total cooked diet and autopsy skeleton samples using radiochemical neutron activation analysis. The data on daily dietary intake of strontium were used to compute its contents in skeleton using ICRP Publication 67 biokinetic model for strontium. The theoretically computed value of strontium (213.8 mg) compared favourably with the measured values (GM 181.2 mg) in an urban population group living in Mumbai representing an average Indian adult (Reference Indian Man).

A concave tray with divergent block for desired dose distribution around shielded region in megavoltage radiation therapy.

In clinical situations large numbers of rectangular divergent blocks are required at different off-axis positions from central axis to shield sensitive organs. Superiority of divergent blocks over non-divergent blocks on a flat tray lies in improving the dose homogeneity. A method has been developed to minimize the number of divergent shielding blocks by using a concave tray at the collimator. The results of use of a single divergent block are similar to that of the use of several divergent blocks, each to match at different off-axis positions in the radiation beam. This type of single concave tray thus provides a considerable ease of handling divergent blocks in a busy radiotherapy centre.

Dosimetry of intracavitary applications in carcinoma of the cervix: rectal dose analysis.

The International Commission on Radiation Units and Measurements (ICRU), in its Report-38, has given certain recommendations regarding the specifications of bladder and rectal reference points in the intracavitary treatment of carcinoma of the cervix. Conforming to this report, 182 intracavitary applications performed in stage I and II cervix cases were analyzed. In 113 applications, the maximum rectal dose was found to be in a point on the anteroposterior line drawn through the centre of colpostat sources. However, for our type of applications, the point on the anteroposterior line drawn through the lower end of the uterine tube seldom gets maximum dose. In addition, it was observed that there are other dose points than the ICRU reference point receiving doses close to maximum dose. It was concluded that doses to multiple rectal reference points should be recorded, in addition to the ICRU-defined rectal reference point.

In-phantom response of LiF TLD-100 for dosimetry of 192Ir HDR source.

An experiment was carried out to reevaluate the response of LiF TLD-100 rods (1 mmx1 mmx6 mm) at different depths in a water substituting phantom to provide an answer to a prevailing controversy about the over-response of LiF to the softened photon spectra of 192Ir HDR source at depths in phantom due to its photon energy dependence. Claims of some authors that LiF TLDs over-responds by 8.5% at 10 cm depth in phantom, necessitating depth-dependent correction factors even for an 192Ir source and of some others for no over-response were evaluated. The over-response of LiF TLD-100 rods, against a calibrated ion chamber having a photon energy-independent response within 2%, was found to be not exceeding 2.5% at a depth of 10 cm in the phantom as compared to a depth at 1 cm, for a precision of the order of +/- 1% (1sigma) in the TLD measurements. By using ISO equivalent photon beams, photon energy dependence of the dosimeters was evaluated and for LiF TLD-100 rods it was found to be in close agreement (within 3%) with the ratios of mass energy absorption coefficients of LiF and water in the range of effective photon energy from 26 keV to 1.25 MeV. Parameters that could contribute to the discrepancy in the reported values of experimental results have been discussed.

Graphite-mixed CaSo4: Dy teflon TLD discs for beta dosimetry.

The thickness of commonly employed thermoluminescent dosemeters (TLDS) is responsible for the problem of energy dependence in beta dose estimation in situations where this thickness is comparable to the range of beta particles in the TLD material. The effective thickness of solid TLD discs can, however, be reduced by use of some additives which would reduce their transparency to the TL light. The incorporation of various amounts of graphite powder into 0-8 mm thick CaSO4: Dy Teflon TLD discs has been investigated. This has considerably reduced their energy dependence for beta rays with Emax values ranging from 0-4 MeV to 2-27 MeV. Addition of graphite also results in sharp glow curves thereby minimizing the heating time during TL measurements. Significantly, graphite was also found to reduce the non-radiation-induced TL signal and this helps in low dose measurements.

A fast and sensitive TLD method for measurement of energy and homogeneity of electron beams using transmitted radiation through lead.

A simple and fast, but sensitive TLD method for the measurement of energy and homogeneity of therapeutically used electron beams has been developed and tested. This method is based on the fact that when small thicknesses of high-Z absorbers such as lead are interposed in the high-energy electron beams, the transmitted radiation increases with the energy of the electron beams. Consequently, the ratio of readouts of TLDS held on the two sides of a lead plate varied sharply (by factor of 70) with a change in energy of the electron beam from 5 MeV to 18 MeV, offering a very sensitive method for the measurement of the energy of electron beams. By using the ratio of TL readouts of two types of TLD ribbon with widely different sensitivities, LiF TLD-700 ribbons on the upstream side and highly sensitive CaF2:Dy TLD-200 ribbons on the downstream side, an electron energy discrimination of better than +/- 0.1 MeV could be achieved. The homogeneity of the electron beam energy and the absorbed dose was measured by using a jig in which the TLDS were held in the desired array on both sides of a 4 mm thick lead plate. The method takes minimal beam time and makes it possible to carry out measurements for the audit of the quality of electron beams as well as for intercomparison of beams by mail.

A thermoluminescent fast-neutron dosemeter based on pellets of CaSO4: Dy mixed with sulphur.

The fast neutron activation reaction 32S(n, p) 32P in CaSO4: Dy has been used in the measurements of fast neutron dose by employing a post-irradiation TL accumulation method. In order to increase the efficiency of the method CaSO4: Dy powder was mixed with sulphur powder in various proportions from which pellets weighing each were made. After neutron irradiation these pellets were each burnt in an aluminium planchette and the phosphor residue with 32P beta activity on it was allowed to undergo self-irradiation for TL accumulation. The fast neutron efficiency of the system employing 10 pellets of 0.1% CaSO4: Dy was found to be about 100 times that of bare CaSO4: Dy powder.

X- and gamma-ray response of the TLD badge based on CaSO4:Dy Teflon TLD discs.

A TLD badge based on CaSO4: Dy Teflon TLD discs has been designed for personnel monitoring of radiation workers encountering X-rays of effective energies above 20 keV. The badge had two Teflon TLD discs, one of which is used bare (without any filter) and other which is used with a metal filter. By taking into account the TL readout of both of these discs, the problems of photon energy dependence as well as directional dependence of the badge have been reduced to a minimum. The uncertainty due to photon energy dependence above 29 KeV (eff.) was found to be within a value of +/- 15% (at an angle of incidence of 45 degrees). The directional dependence of the badge is within +/- 30% in the energy range from 35 KeV to 1.25 MeV. The badge is designed so as to provide approximate information on the effective photon energy of the X-ray exposures.

Dose equivalent response of a TLD badge--influence of body backscatter.

In personnel monitoring, operational quantities recommended by ICRU Publication No. 39 for photon radiation can be realized by calibrating dosimeters on a phantom and considering body backscatter photons by using established conversion factors. Personnel dosimeters used in this study are based on CaSO4:Dy Teflon thermoluminescence dosimeter discs (TLD) that have a highly photon energy-dependent response. Since body backscattered photons have lower energies than the incidence photons, methods for correcting for energy dependence of both the incident and body backscattered photons have to be developed. By using readouts of two TLD discs (one under a composite metal filter and the other without a metal filter) in an empirical relation valid at all energies, it is possible to correct for the effect of change in response from change in the photon energies. It was found that the new operational quantities recommended by ICRU could be estimated to within +/- 15% by a TLD badge design based on this method. Angular dependence limits for photons in accordance with the new international standards and a high beta dose-equivalent discrimination in the mixed fields of beta and low-energy x rays could also be achieved.

Photon energy response of luminescence dosemeters and its impact on assessment of Hp(10) and Hp(0.07) in mixed fields of varying energies of photons and beta radiation.

X and gamma rays continue to remain the main contributors to the dose to humans. As these photons of varying energies are encountered in various applications, the study of photon energy response of a dosemeter is an important aspect to ensure the accuracy in dose measurement. Responses of dosemeters have to be experimentally established because for luminescence dosemeters, they depend not only on the effective atomic number (ratio of mass energy absorption coefficients of dosemeter and tissue) of the detector, but also considerably on the luminescence efficiency and the material surrounding the dosemeters. Metal filters are generally used for the compensation of energy dependence below 200 keV and/or to provide photon energy discrimination. It is noted that the contribution to Hp(0.07) could be measured more accurately than Hp(10). For the dosemeters exhibiting high photon energy-dependent response, estimation of the beta component of Hp(0.07) becomes very difficult in the mixed field of beta radiation and photons of energy less than 100 keV. Recent studies have shown that the thickness and the atomic number of metal filters not only affect the response below 200 keV but also cause a significant over-response for high energy (>6 MeV) photons often encountered in the environments of pressurised heavy water reactors and accelerators.

Effect of heating rate on the responses of CaF2:Cu, CaF2:Tm, CaF2:Dy and CaF2:Mn.

Recent development of CaF2:Cu (the most sensitive material for radiation dosimetry) exhibiting a TL glow peak around 270 degrees C similar to that of CaF2:Mn has made it attractive to study the influence of heating rate on the response of CaF2 based TLDs. Influence of heating rate on CaF2:Mn (known to reduce the response with increasing heating rate) was confirmed in view of the reported controversy about other TLDs. Responses of TL glow peaks around 270 degrees C in CaF2:Cu, CaF2:Tm, CaF2:Dy and CaF2:Mn were studied. Except CaF2:Mn, no other CaF2 based TLD exhibited a reduction in response with increasing heating rate. On the contrary, in some cases a small increase (10-15%) was noted with increasing heating rate from 1 degrees Cs(-1) to 50 degrees Cs(-1). The shape and the position of the glow peak and the parameters derived from the shape of the glow curve appear to have no relation to reduction of TL efficiency at higher heating rates. Apart from the increased probability of non-radiative transitions at higher temperatures, the observed effects have been assigned to the effect of heating rate on the migration of charge carriers released during the TL readout.

Calibration of TLD badges for photons of energy above 6 MeV and dosimetric intricacies in high energy gamma ray fields encountered in nuclear power plants.

CaSO4:Dy and LiF TLDs do not exhibit photon energy dependence beyond +/-55% for photons in the energy range from 1 MeV to about 7 MeV. However, when sandwiched between metal filters or used in TLD badge holders having metal filters, the response changes for irradiation from high energy photons as compared to that from 60Co gamma rays (generally used for reference calibrations). This effect is about the same for both the lower atomic number TLD (LiF) and higher atomic number TLD (CaSO4:Dy). For TLDs held on the surface of the phantom and irradiated in collimated photon beams, the response of TLDs without any filter or those under the open window of the TLD badge is considerably reduced due to insufficient build-up to high energy photons, whereas for uncollimated radiation fields from power reactors, an over-response is observed. It is observed that the use of inappropriate encapsulation of dosemeters would cause a significant error not only in the estimation of doses due to penetrating radiations but also in the estimation of beta doses in the mixed fields of beta radiation, high energy gamma rays and high energy electrons often encountered in the fields of pressurised heavy water reactors.

The use of computerised glow curve analysis will optimise personal thermoluminescence dosimetry measurements. Opposing the proposition.

Referring to the proposition for this debate, it is necessary to consider what is meant by 'optimise personal thermoluminescence dosimetry measurements'. Much research has been performed on the thermoluminescence glow curves that can be used to determine absorbed dose, and much of the knowledge gained from this research has been put into practice. Thermoluminescence dosemeters are capable of measuring an extremely wide range of doses and dose rates. Nearly all types of radiation can be measured, and some TL dosemeters have been designed to function as elementary spectrometers. More recently, the microdosimetric properties of TL dosemeters have been investigated. TL dosemeters are worn by a large proportion of radiation workers worldwide. But, can we conclude that thermoluminescence dosimetry measurements are at an optimum level? Perhaps that is not a fair question because it may be impossible to say when anything is truly optimum. Although the techniques pointed out by our debaters may not yet be used by all large, personal dosimetry services, as with many recent innovations, implementation may be as near as the next computer chip upgrade.

Batch-to-batch variation in the TL glow peaks and sensitivity in the production of CaSO4:Dy TLD phosphor.

The thermoluminescence (TL) glow peak height ratio of the main dosimetric peak (at about 240 degrees C) and the lower temperature satellite peak (at about 140 degrees C) of CaSO4:Dy was found to vary between 1.4 and 11.5 in more than 100 batches of CaSO4:Dy TLD tested in the last 5 years. Efforts were made to minimise the batch-to-batch variation. In most of the batches (90% of cases), the peak height ratio was more than 5 and the variation in the TL sensitivity (with respect to the reference batch) rarely exceeded 10%. The study of the grain size dependence of the peak height ratio of ground and unground and with and without acid wash of phosphor grains indicated that the surface effects contribute significantly to the batch-to-batch variation. Crystallisation of phosphor grains was found to be affected considerably by the interruptions in the process of evaporation of acid during the preparation. Phosphor grain size was found to be an important parameter for maintaining the quality of production of CaSO4:Dy TLD phosphor.