IDAC-Dose 2.1, an internal dosimetry program for diagnostic nuclear medicine based on the ICRP adult reference voxel phantoms (original) (raw)
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Radiation dosimetry in nuclear medicine
Applied Radiation and Isotopes, 1999
Radionuclides are used in nuclear medicine in a variety of diagnostic and therapeutic procedures. A knowledge of the radiation dose received by dierent organs in the body is essential to an evaluation of the risks and bene®ts of any procedure. In this paper, current methods for internal dosimetry are reviewed, as they are applied in nuclear medicine. Particularly, the Medical Internal Radiation Dose (MIRD) system for dosimetry is explained, and many of its published resources discussed. Available models representing individuals of dierent age and gender, including those representing the pregnant woman are described; current trends in establishing models for individual patients are also evaluated. The proper design of kinetic studies for establishing radiation doses for radiopharmaceuticals is discussed. An overview of how to use information obtained in a dosimetry study, including that of the eective dose equivalent (ICRP 30) and eective dose (ICRP 60), is given. Current trends and issues in internal dosimetry, including the calculation of patient-speci®c doses and in the use of small scale and microdosimetry techniques, are also reviewed. # : S 0 9 6 9 -8 0 4 3 ( 9 8 ) 0 0 0 2 3 -2 Applied Radiation and Isotopes PERGAMON * To whom all correspondence should be addressed. per unit time, integrating this over time gives the total number of disintegrations.
Nuclear Technology and Radiation Protection, 2014
Monte Carlo simulations and dose measurements were performed for radionuclides in the whole body and trunks of different sizes in order to estimate external radiation whole body doses from patients administered with radiopharmaceuticals. Calculations were performed on cylindrical water phantoms whose height was 176 cm and for three body diameters: of 24 cm, 30 cm, and 36 cm. The investigated radionuclides were: 99mTc, 131I, 23I, 67Ga, 201Tl, and 111In. Measured and MCNP-calculated values were 2-6 times lower than the values calculated by the point source method. Additionaly, the total dose received by the public until a radionuclide is completely disintegrated was calculated. The other purpose of this work is to provide data on whole body and finger occupational doses received by technologists working in nuclear medicine. Data showed a wide variation in doses that depended on the individual technologist and the position of the dosimeter.
EJNMMI Physics, 2014
Background: Effective dose represents the potential risk to a population of stochastic effects of ionizing radiation (mainly lethal cancer). In recent years, there have been a number of revisions and updates influencing the way to estimate the effective dose. The aim of this work was to recalculate the effective dose values for the 338 different radiopharmaceuticals previously published by the International Commission on Radiological Protection (ICRP). Method: The new estimations are based on information on the cumulated activities per unit administered activity in various organs and tissues and for the various radiopharmaceuticals obtained from the ICRP publications 53, 80 and 106. The effective dose for adults was calculated using the new ICRP/International Commission on Radiation Units (ICRU) reference voxel phantoms and decay data from the ICRP publication 107. The ICRP human alimentary tract model has also been applied at the recalculations. The effective dose was calculated using the new tissue weighting factors from ICRP publications 103 and the prior factors from ICRP publication 60. The results of the new calculations were compared with the effective dose values published by the ICRP, which were generated with the Medical Internal Radiation Dose (MIRD) adult phantom and the tissue weighting factors from ICRP publication 60. Results: For 79% of the radiopharmaceuticals, the new calculations gave a lower effective dose per unit administered activity than earlier estimated. As a mean for all radiopharmaceuticals, the effective dose was 25% lower. The use of the new adult computational voxel phantoms has a larger impact on the change of effective doses than the change to new tissue weighting factors. Conclusion: The use of the new computational voxel phantoms and the new weighting factors has generated new effective dose estimations. These are supposed to result in more realistic estimations of the radiation risk to a population undergoing nuclear medicine investigations than hitherto available values.
MODELLING DOSE ASSESSMENT DURING NUCLEAR MEDICINE
Radiation doses to staff preparing radiopharmaceuticals in a radionuclide dispensary have been evaluated by the determination of gamma dose rates on the exterior surfaces of cylindrical vessels containing radioactive solutions. A theoretical model based on Monte Carlo calculation has been used. Calculated results are compared with experimentally determined results for 99m Tc (a pure gamma emitter) in polypropylene containers of various wall thickness. Calculated results for the γ-ray dose rates to the skin of the fingers, for partially filled plastic syringes, are compared with other published results, for 59 Fe, 198 Au, 113m In, 131 I, 203 Hg and 99m Tc in syringes of various diameters and wall thicknesses. The calculations are extended to provide results for the γ ray dose rate distribution along the external surfaces of partially filled syringes for 198 Au and 99m Tc. These results are used to objectively derive guidelines for the safe handling of cylindrical vessels containing γ emitting radionuclides, without the use of extra shielding, good agreement was obtained. It is recommended, when using syringes without syringe guards, that the fingers should never approach the active volume closer than the rear end of the syringe barrel, and that syringes should not be filled beyond 75% of their capacity. These results are used to objectively derive guidelines for the safe handling of cylindrical vessels containing γ emitting radionuclides, without the use of extra shielding.
A new approach for the calculation of critical organ dose in nuclear medicine applications
Applied Radiation and Isotopes, 2005
The geometrical factor that is calculated to keep in mind the radiation source and detector position is rather frequently used in radiation measuring and calculating methods. In this study, using the geometrical factor is intended to suggest a new model to measure the absorbed dose in nuclear medicine applications. Therefore, the source and target organ's geometries are accepted to be disc and parallel to each other. In this manner, a mathematical model for the geometry of these discs is proposed and a disc-disc geometry factor is calculated. Theoretical calculations have been carried out with the MIRD (medical internal absorbed dose) method, which is widely used to the absorbed dose calculations in nuclear medicine. Absorbed radiation dose is separately calculated for a target organ, which is the testis, with disc-disc geometry factor model and MIRD model. Both the results are compared and the results of disc-disc geometry factor model are shown to be harmonious and acceptable with the results of MIRD model. r
Physics in Medicine and …, 2008
CALDose X is a software tool that provides the possibility of calculating incident air kerma (INAK) and entrance surface air kerma (ESAK), two important quantities used in x-ray diagnosis, based on the output of the xray equipment. Additionally, the software uses conversion coefficients (CCs) to assess the absorbed dose to organs and tissues of the human body, the effective dose as well as the patient's cancer risk for radiographic examinations. The CCs, ratios between organ or tissue absorbed doses and measurable quantities, have been calculated with the FAX06 and the MAX06 phantoms for 34 projections of 10 commonly performed x-ray examinations, for 40 combinations of tube potential and filtration ranging from 50 to 120 kVcp and from 2.0 to 5.0 mm aluminum, respectively, for various field positions, for 29 selected organs and tissues and simultaneously for the measurable quantities, INAK, ESAK and kerma area product (KAP). Based on the x-ray irradiation parameters defined by the user, CALDose X shows images of the phantom together with the position of the x-ray beam. By using true to nature voxel phantoms, CALDose X improves earlier software tools, which were mostly based on mathematical MIRD5-type phantoms, by using a less representative human anatomy.