ABSTRACT
The purpose of this work is to assess accuracy and compare the performance of radionuclide calibrators (RNCs) used in nuclear medicine departments in Serbia. Testing of the RNCs included verification of measurement accuracy, as well as analysis of routinely used quality control protocols, by using the certified radioactivity standards (57Co, 137Cs). RNCs performances were assessed with 99mTc through comparison of reference value for radionuclide activity and RNC measurements. Results of the intercomparison revealed that RNCs, 15 in total, are accurate within 10% in vial geometry and within 15% in syringe geometry. Most of them showed similar performance. The results revealed that container geometry is an important influencing parameter in the accuracy of activity measurement. Obtained results indicate a need for regular calibration and implementation of Quality Control program in order to achieve and maintain the accuracy of activity measurements in nuclear medicine.
Subject(s)
Nuclear Medicine , Radioisotopes/analysis , Calibration , Quality Control , SerbiaABSTRACT
PURPOSE: The purpose of this article was to analyse the impact of low-dose ionizing radiation to nuclear medicine professionals of the Nuclear Medicine Centre of Serbia (NMCRS). METHODS: Data from the previous/initial and the last medical check-ups, obtained from the medical records of 65 employees from NMCRS, were analysed. A typical checkup, haematological parameters analysis, as well as special cytogenetical analyses, such as unstable chromosomal aberrations and micronucleus test, were carried out. For analyses of chromosomal aberrations the modified Moorhead's micro method was applied to the culture of peripheral blood lymphocytes and conventional cytogenetic technique of chromosomal aberrations was applied. The received cumulative 5-year dose was measured by personal inactive thermoluminescent dosimeters (TLD) calibrated into personal doses equivalent Hp(10). RESULTS: An increased frequency of all unstable chromosomal aberration forms, such as acentric chromosomes and isochromatid lesions, was noticed in the last periodical check-up as compared to the previous/initial checkups (p<0.05). As for haematological parameters, a higher erythrocytes and monocytes count in the periodical checkups was noticed (p<0.01). There was a negative correlation between reticulocytes and received 5-year cumulative dose (p<0.01). The duration of exposure had significant influence on higher level of leucocytes in the last periodical check-up (p<0.05). CONCLUSIONS: Nuclear medicine employees have increased health risks and there is a need to monitor their health condition by periodical check-ups for prevention from occupational diseases (carcinoma).
Subject(s)
Chromosome Aberrations , Diagnostic Imaging/adverse effects , Health Personnel , Lymphocytes/radiation effects , Nuclear Medicine , Occupational Exposure/adverse effects , Occupational Health , Radiation Dosage , Radiation Exposure/adverse effects , Radiation Injuries/etiology , Adult , Biomarkers/blood , Cells, Cultured , Cytogenetic Analysis , Diagnostic Imaging/methods , Female , Humans , Lymphocytes/pathology , Male , Medical Records , Micronucleus Tests , Middle Aged , Radiation Injuries/blood , Radiation Injuries/diagnosis , Radiation Injuries/genetics , Risk Assessment , Risk Factors , Serbia , Thermoluminescent Dosimetry , Time Factors , WorkforceABSTRACT
The purpose of this study was to assess the patient exposure and staff eye dose levels during implantation procedures for all types of pacemaker therapy devices performed under fluoroscopic guidance and to investigate potential correlation between patients and staff dose levels. The mean eye dose during pacemaker/defibrillator implementation was 12 µSv for the first operator, 8.7 µSv for the second operator/nurse and 0.50 µSv for radiographer. Corresponding values for cardiac resynchronisation therapy procedures were 30, 26 and 2.0 µSv, respectively. Significant (p < 0.01) correlation between the eye dose and the kerma-area product was found for the first operator and radiographers, but not for other staff categories. The study revealed eye dose per procedure and eye dose normalised to patient dose indices for different staff categories and provided an input for radiation protection in electrophysiology procedures.
Subject(s)
Electrophysiology/methods , Lens, Crystalline/radiation effects , Medical Staff, Hospital/statistics & numerical data , Occupational Exposure/analysis , Patient Safety/statistics & numerical data , Radiation Monitoring/statistics & numerical data , Radiation Protection/methods , Fluoroscopy , Humans , Radiation Dosage , Radiation Monitoring/instrumentation , Radiation Protection/instrumentation , Risk AssessmentABSTRACT
We designed the GammaKey system for the acquisition, storage and analysis of images from semi-analogue gamma scintillation cameras (GSCs). The GammaKey system, operating on a standard PC, replicates the functionality of earlier dedicated computer systems, allows the exchange of data in the DICOM format and has an open architecture enabling the development of new diagnostic techniques. The main purpose of the GammaKey is to enable the continued use of old GSCs which have functional scintillation crystals, but also to permit data exchange with new digital GSCs. The GammaKey has been technically validated by standards established by the National Electrical Manufacturers Association. The GammaKey has been used for seven years in two leading centres for nuclear medicine in Serbia (the Clinical Center of Serbia, Belgrade, and the Clinical Center of Vojvodina, Novi Sad) in approximately 30,000 patients. Clinical application proves that the GammaKey is a robust and reliable system with high-quality image output. Data processing can be upgraded with non-standard features added on request as shown in two examples: (1) the testing of splenectomy efficacy in the case of thrombocytopenia with normal production; and (2) the detection and localisation of parathyroid adenomas.
Subject(s)
Gamma Cameras , Image Processing, Computer-Assisted/methods , Medical Informatics/methods , Algorithms , Automation , Computer Systems , Humans , Lung/diagnostic imaging , Nuclear Medicine/methods , Parathyroid Neoplasms/diagnostic imaging , Perfusion , Radionuclide Imaging , Saliva/metabolism , Serbia , Software , Splenectomy/methods , Thrombocytopenia/surgeryABSTRACT
Protection at positron emission tomography-computed tomography (PET-CT) installations is the most complex problem in the field of designing structural protection from ionising radiation in medical practice. This paper provides a discussion on the values for shield widths obtained from two different estimation methods, as well as of certain theoretical differences inherent in the two approaches. After the general operation principles of a PET-CT device are expounded, a comparative analysis of two methods for calculating structural barriers is performed. The first calculation was conducted by the 'Vinca' Institute of Nuclear Sciences, according to the recommendations of the AAPM task group 108, while the second was performed by a PET-CT device manufacturer, following the DIN 6844-3 standard.