Reference dosimetry and measurement quality assurance

Measurements of absorbed dose made by a reference dosimetry system, such as alanine, have been suggested for achieving quality assurance through traceability to primary standards. Such traceability can assist users of radiation worldwide in enhancing quality control in medicine, agriculture, and industry. International and national standards of absorbed dose are still needed for applications of γ-ray and electron dosimetry at high doses (e.g. radiation therapy, food irradiation and industrial radiation processing). Reference systems, such as ferrous sulfate dosimeters measured by spectrophotometry and alanine measured by electron spin resonance spectrometry are already well established. Another useful reference system for high doses is supplied as dichromate solutions measured by spectrophotometry. Reference dosimetry, particularly for electron beams, can be accomplished with thin alanine or radiochromic dye film dosimeters.     

Application of an alanine dosimetry system for industrial irradiation and radiation protection

This paper reports the application of alanine dosimetry in radiation processing. Continuous checks of the EPR measuring conditions as well as using high-quality alanine dosimeters and consistent technique for dose determination guarantee an accuracy of about ±3% intermediate dose levels. The alanine dosimetry system was applied for dose mapping measurements during irradiator qualification and performance qualification of different products, routine dosimetry, and special radiation protection application within the gamma irradiator.     

One year of experience with alanine dosimetry in radiotherapy

Commercially available alanine dosimeters from different manufacturers were purchased for this study. The response of the detectors was evaluated with ⁶⁰Co gamma radiation in the dose range 0.2–200 Gy, using a small EPR spectrometer dedicated to dosimetry. The batch sensitivity, inter-specimen scattering and background signal for the different selection of dosimeters were evaluated. The usefulness of the alanine dosimetry system for clinical routine is illustrated by in vivo measurements during ¹⁹²Ir brachytherapy of cervix carcinoma.     

Ionizing radiation dosimetry in the absorbed dose range 0.01-50 MGy based on resistance and ESR linewidth measurements of organic conducting crystals

The materials studied in the present work as high-dose dosimeters are members of a large class of molecular crystals which are organic conductors of electricity. Very different from each other in the details of their molecular and crystal structures, they all behave in the same way when subjected to increasing high doses of radiation, at least from the point of view of their electronic transport properties, because of the quasi-one-dimensional character of the conduction process. Their resistivities increase exponentially with the absorbed dose while their electron spin resonance (ESR) linewidths decrease exponentially. Very small single crystals less than 10 micron thick can be used as dosimeters in the dose range 0.01-50 MGy for gamma rays as well as for electron irradiations, by applying four probe resistance measurements. Only a few compounds over a large number of candidates have been irradiated in the present work with gamma-rays, low energy x-rays and electrons. In some favourable cases the energy and temperature dependences of the dosimeters have been checked experimentally. Their mass energy absorption coefficients and electron stopping powers have been also calculated. It is hoped to extend this kind of dosimetry to lower and higher doses by trying new compounds from the large family of organic conductors or by improving the resistivity and ESR measurement techniques.     

The extension of the range of NIM alanine/ESR dosimetric system to therapy level

The NIM alanine/ESR dosimetric system, which was designed for industrial radiation processing, has been improved to be suited for applications in therapy dose range. Two different procedures of dose intercomparisons between IAEA and NIM were carried out with the improved system in the range of 2.5 to 100 Gy. In the first procedure, a set of NIM alanine dosimeters were irradiated at IAEA dosimetric laboratory and part of dosimeters marked “for evaluated” were evaluated using the rest of those with “known dose” given by IAEA. Most of evaluated doses agreed with IAEA doses within 1%. In the second procedure, all above dosimeters were evaluated on the base of NIM dosimetry. The results indicated that the doses determined by NIM agreed with those given by IAEA within 3% on the average.     

Uncertainties in alanine dosimetry in the therapeutic dose range

A method for evaluating the overall uncertainty of alanine EPR transfer dosimetry in the therapeutic dose range is described. The method uses experimental data on EPR signal reproducibility from replicate dosimeters irradiated to low doses (1–5 Gy), estimates of Type B uncertainties, and Monte Carlo simulations of heteroscedastic orthogonal linear regression. A Bruker ECS106 spectrometer and Bruker alanine dosimeters have been used for this evaluation. The results demonstrate that alanine dosimetry can be used for transfer dosimetry in that range with the overall uncertainty 1.5–4% (1σ) depending on the dose, the number of replicate dosimeters, and the duration of the calibration session (the session should not exceed one working day).     

Radiation doses for pregnant women in the late pregnancy undergoing fetal-computed tomography: a comparison of dosimetry and Monte Carlo simulations

The purposes of this study were (1) to compare the radiation doses for 320- and 80-row fetal-computed tomography (CT), estimated using thermoluminescent dosimeters (TLDs) and the ImPACT Calculator (hereinafter referred to as the “CT dosimetry software”), for a woman in her late pregnancy and her fetus and (2) to estimate the overlapped fetal radiation dose from a 320-row CT examination using two different estimation methods of the CT dosimetry software. The direct TLD data in the present study were obtained from a previous study. The exposure parameters used for TLD measurements were entered into the CT dosimetry software, and the appropriate radiation dose for the pregnant woman and her fetus was estimated. When the whole organs (e.g., the colon, small intestine, and ovaries) and the fetus were included in the scan range, the difference in the estimated doses between the TLD measurement and the CT dosimetry software measurement was <1 mGy (<23 %) in both CT units. In addition, when the whole organs were within the scan range, the CT dosimetry software was used for evaluating the fetal radiation dose and organ-specific doses for the woman in the late pregnancy. The conventional method using the CT dosimetry software cannot take into account the overlap between volumetric sections. Therefore, the conventional method using a 320-row CT unit in a wide-volume mode might result in the underestimation of radiation doses for the fetus and the colon, small intestine, and ovaries.     

Dosimetry of interstitial brachytherapy using radiophotoluminescence glass: On absorbed dose of anterior wall of the rectum]

It has been almost impossible to perform in-vivo dosimetry of interstitial brachytherapy because of the lack of appropriate dosimeters. The newly developed photoluminescence dosimeter "Dose Ace" is suitable for interstitial brachytherapy dosimetry in terms of its small size, ease of handling, and good reproducibility. We performed dosimetry of the anterior rectal wall by suturing a Teflon tube containing photoluminescence dosimeters. We measured doses at 50 points in seven pelvic malignancy patients and calculated the dose at each point by planning computer. The mean ratio of measured dose to calculated dose was 1.108 to 0.213. The absorbed dose of the anterior rectal wall can be presumed from the calculated dose with about 10% deviation.     

Using NanoDot dosimetry to study the RS 2000 X-ray Biological Irradiator

Abstract

Purpose: To use NanoDot dosimeters to study the RS 2000 X-ray Biological Irradiator dosimetry characteristics and perform in vivo dosimetry for cell or small animal experiments.

Methods and materials: We first calibrated the Landauer NanoDot^? Reader by irradiating some NanoDot dosimeters with a set of known doses at specific positions defined by the irradiator. A group of five NanoDot dosimeters were placed at five specific positions where the dose rates were known and provided by the irradiator. Each group was irradiated for a set of times respectively. By correlating the readings of dosimeters with the given irradiated doses, we established the dose-reading relationship for the irradiator under the specific running condition. The established calibration curve was validated by exposing arbitrary known doses to a set of dosimeters, using the Landauer NanoDot^? Reader to measure the doses, and then making the comparison between the two doses. To study the dose gradient of the X-ray inside the irradiated target (dose variation/cm), we placed dosimeters under different thicknesses of water-equivalent bolus and irradiated them, then measured the doses to determine the dose gradient.

Results: Using the method described above, we were able to calibrate the Landauer InLight NanoDot^? Reader and use NanoDot dosimeters to measure the actual doses delivered to the targets for the cell/small animal experiments that use the RS 2000 X-ray Biological Irradiator.

Conclusions: NanoDots are ideal dosimeters to use for in vivo dosimetry for cell/small animal irradiation experiments. The dose decrease inside the animal tissue is about 20% per cm.     

In vivo ESR dosimetry in total body irradiation

Total body irradiation (TBI) using high doses (about 10 Gy) with photons in the range between 1 and 10 MV combined with intensive chemotherapy has been used successfully in treatment of acute and chronic leukemia before bone marrow transplantation. One of the principal international guidelines in TBI is to use in vivo dosimetry in order to compare the prescribed dose with that absorbed. The use of in vivo dosimetry is also useful as a retrospective evaluation of any deviation from the prescribed dose greater than +/- 5% for relevant parts of the body, especially in the lung and in other organs at risk. In this paper, Electron Spin Resonance (ESR), using alanine dosimeters, is demonstrated to be a powerful tool for absorbed dose evaluation in TBI by detection of free radicals produced in alanine by ionizing radiation. In this study, we present the results obtained using ESR dosimetry in eleven patients undergoing TBI. The major advantages appear to be: 1. the ESR signal in alanine dosimetry is stable for years without fading: 2. the detection of the ESR signal does not destroy the information and so enables a retrospective judgment of the TBI plan adopted.     

Evaluation of doses in radiotherapy using solid-state composites based on natural colourless topaz.

The thermoluminescent properties of composites containing powdered topaz embedded in Teflon or glass were studied and compared with the corresponding properties of the well known TLD-100 commercial dosimeters. Relative sensitivity, TL fading, reproducibility of the sample preparation process, and possibility of re-utilisation of the dosimeters were investigated. Measurements of absorbed doses in simulated radiotherapy treatments were also taken. The irradiations were performed using gamma rays from a 60Co source in the dose range from 1cGy to 2Gy. The dosimeters were installed in badges and attached inside acrylic plates of various thicknesses in the radiation fields. The dose profiles obtained with this procedure are very similar to the ones obtained with equivalent tissues. It is concluded that these composites of natural colourless topaz crystals can be efficiently used as TL dosimeters.     

Exposure of medical personnel to radiation during radionuclide therapy practices

OBJECTIVES: Radioisotopes that emit beta radiation are used for the treatment of hepatocellular carcinoma, of arthritic patients (radiosynovectomy) and treatment of bone metastases with, respectively, I-labelled lipiodol, colloidal citrate of Y or and Sm-labelled EDTMP. Radiation energy of these radioisotopes that emit beta or beta and gamma radiation (from 300 to 2000 keV) leads to an increase in radiation dose received by nuclear medicine staff. In this paper we focused on clinical and laboratory staff exposure during these types of metabolic radiation therapies. METHODS: Cylindrical LiF thermoluminescence dosimeters were used to measure radiation-related whole-body doses (WBDs) and finger doses of the clinical staff. RESULTS: Exposure of the two radiopharmacists and three nurses taking part in I-labelled lipiodol, Y-colloid and Sm-EDTMP therapies, for 12 months in succession, were 146 microSv and 750 microSv, respectively, considering WBD, and 14.6 mSv and 6.5 mSv, respectively, considering finger doses. Extrapolated annual exposures (six radiosynovectomies per year) for the rheumatologists were estimated to be 21 microSv (WBD) and 13.2 mSv (finger dose). Extrapolated annual WBDs and finger doses (25 I-labelled lipiodol treatments per year) for radiologists were estimated to 165 microSv and 3.8 microSv, respectively. CONCLUSION: Fortunately, these doses were always lower than the limits reported in the European Directive EURATOM 96/29 05/13/1996 (WBD <20 mSv.year; finger dose: 500 mSv.year) but have to be added to those relative to other metabolic radiotherapies such as radioiodine treatments and new metabolic radiotherapies (Y-conjugated peptides or antibodies). Nevertheless, the global exposure of medical staff involved in all these clinical practices justifies dosimetry studies to validate protocols and radiation protection devices for each institution.     

Radiation dose and risk from fluoroscopically guided percutaneous transluminal angioplasty and stenting in the abdominal region

The objective of this study was to estimate the radiation dose and associated risks resulting from fluoroscopically guided percutaneous transluminal angioplasty with or without stent placement in the abdominal region. Average examination parameters for renal and aortoiliac procedures were derived using data from 80 consecutive procedures performed in our institute. Organ and effective doses were estimated for endovascular procedures with the use of a Monte Carlo (MC) transport code and an adult mathematical phantom. Thermoluminescent dosimeters were used in an anthropomorphic phantom to verify MC calculations. Radiation-induced risks were estimated. Results are presented as doses normalized to dose area product, so that the patient dose from any technique and X-ray unit can be easily calculated for iliac and renal PTA/stenting sessions. The average effective dose varied from 75 to 371 μSv per Gycm² depending on the beam quality, procedure scheme and sex of the patient. Differences up to 17% were observed between MC-calculated data and data derived from thermoluminescent dosimetry. The radiation-induced cancer risk may be considerable for younger individuals undergoing transluminal angioplasty with stent placement.     

A method for determining simultaneously the dose and the elapsed time since irradiation using TLDs

Information about the time that has elapsed since an external radiation exposure is useful in order to determine the time of occurrence of an abnormal exposure in personal and accidental dosimetry is presented. This information can be obtained from certain irradiated thermoluminescent dosimeters. A computational method based on decay rates of thermoluminescence glow peaks has been used to estimate a range of suitable values of trap lifetimes of low temperature glow peaks. This provides a basis for the selection of an appropriate thermoluminescent material to assess not only the absorbed dose from a radiation exposure, but also the elapsed time. Experimental studies have been used to obtain additional information on decay rates as a function of energy, temperature and absorbed dose.     

Chemical dosimetry using an iodide/iodate aqueous solution: application to the gamma irradiation of blood.

A method is presented for measuring and verifying the radiation dose in gamma irradiators used for treating blood prior to transfusion. This method employs the iodide/iodate dosimeter (0.6M iodide, 0.1M iodate, and 0.01 borate at pH 9.25) which forms triiodide upon exposure to ionizing radiation; for Cs-137 radiation the G value is 14.1. Samples were placed in a canister and irradiated in a conventional blood bank irradiator containing several Cs-137 sources. The following were exposed: (a) nine 1.5 ml plastic tubes containing dosimetry solution taped inside a 250 ml blood bag, which, in turn, was filled with either water or blood, (b) 50 ml plastic syringes containing varying amounts of dosimetry solution, (c) a whole blood bag containing 250 ml of the dosimetry solution. A water phantom was not used during exposure. The absorbance changes at 352 nm due to triiodide formation were used to determine a dose rate, which was on the order of 10 Gy/min (+/-5%) for all samples measured. This value is consistent with an average time-decayed dose rate for the irradiation volume as determined from the manufacturers calibration of the unit taking into account the heterogeneous nature of the radiation field inside the irradiator and the absence of a water phantom. Because of its sensitivity, ease of operation, and reproducibility, it is suggested that the iodide/iodate dosimetry system be considered for on-site periodic conformation/verification of the radiation dose as part of a quality assurance requirement for blood irradiators.     

Personal dosimetry of the staff during treatment of neuroendocrine tumours with a high dose of Indium-111 Octreotide.

BACKGROUND: Therapeutic doses with Indium-111 (In-111)-DTPA-Octreotide are currently used in patients with somatostatin receptor positive tumours. It may result in tumour regression in some patients and this effect is ascribed to cell and receptor specific cytotoxicity by Auger or conversion electrons. Personnel being involved in this treatment may receive high radiation doses due to the emission of 173 keV and 247 keV photons. The aim of the present study was to assess the radiation dose to the personnel at different time intervals during treatment with Indium-111 Octreotide. METHODS: Five consecutive patients suffering from a neuroendocrine tumour were included in this dosimetry study. In total, 18 treatments with Indium-111 Octreotide have been given with a mean dose of 8000 MBq every three weeks. Three dosimeters (whole body, left and right hand) and a dose rate monitor were used to register doses and dose rates during labelling, administration and in-patient follow-up and whole body scintigraphy. These procedures were performed by a pharmacist, a nuclear physician and a technologist, respectively. RESULTS: The whole body dose received during the labelling procedure was 5 microSv. The mean total exposure time during administration, whole body scintigraphy and clinical follow-up was 47 minutes revealing a mean whole body dose of 45 microSv. The mean radiation dose to the hands was 60 microSv per treatment. CONCLUSIONS: The radiation risk to staff members and technologists seems to be very low during in-patient treatments with high dose Indium-111 Octreotide. According to the safety regulations no special radiation protection measures or personal dosimetry is required.     

Gamma irradiator dose mapping simulation using the MCNP code and benchmarking with dosimetry.

The Monte Carlo transport code, MCNP, has been applied in simulating dose rate distribution in the IR-136 gamma irradiator system. Isodose curves, cumulative dose values, and system design data such as throughputs, over-dose-ratios, and efficiencies have been simulated as functions of product density. Simulated isodose curves, and cumulative dose values were compared with dosimetry values obtained using polymethyle-methacrylate, Fricke, ethanol-chlorobenzene, and potassium dichromate dosimeters. The produced system design data were also found to agree quite favorably with those of the system manufacturer's data. MCNP has thus been found to be an effective transport code for handling of various dose mapping excercises for gamma irradiators.     

淋巴细胞微核检测可用作辐射生物剂量计

用外周血淋巴细胞微核检测法对一起６０Ｃｏ源事故及１例非何杰金氏淋巴瘤６０Ｃｏ源全身照射治疗后的生物剂量进行了估算，取得与物理剂量或染色体剂量一致的结果。照后３１天的微核剂量仍能反映实际剂量，认为微核检测可作为生物剂量计用于估算受照者的生物剂量。在事故情况下，为尽早向临床提供剂量数据，可先观察５２小时培养制片标本，计算出初步参考剂量，然后观察７２小时培养制片的标本，给出正式剂量。     

A dosimetric study of small photon fields using polymer gel and Gafchromic EBT films

The use of small field sizes is increasingly becoming important in radiotherapy particularly since the introduction of stereotactic radiosurgery and intensity-modulated radiation therapy techniques. The reliable measurement of delivered dose from such fields with conventional dosimeters, such as ionization chambers, is a challenging task. In this work, methacrylic and ascorbic acid in gelatin initiated by copper polymer gel dosimeters are employed to measure dose in 3 dimensions. Field sizes of 5 × 5 mm², 10 × 10 mm², 20 × 20 mm², and 30 × 30 mm² are investigated for a 6-MV x-rays. The results show an agreement with Gafchromic film, with some variation in measured doses near the edge of the fields, where the film data decrease more rapidly than the other methods. Dose penumbra widths obtained with gel dosimeters and Gafchormic film were generally in agreement with each other. The results of this work indicate that polymer gel dosimetry could be invaluable for the quantification of the 3-dimensional dose distribution in small field size.