Úvod: Práce na pracovištích nukleární medicíny představuje pracovní činnosti, při kterých dochází k expozici ionizujícím zářením. Expozice může být ovlivněna nejen druhem aplikovaného radiofarmaka a jeho aktivitou, ale i způsobem aplikace. Metoda: Práce sleduje a hodnotí výsledky osobní dozimetrie lékařů na pracovišti Oddělení nukleární medicíny Masarykova onkologického ústavu v Brně ovlivněné instrumentací pro aplikaci radiofarmak. Výsledky: Využití instrumentace k aplikaci radiofarmak umožňuje redukci profesního ozáření aplikujících lékařů o více než 90 % v prstové a celotělové dozimetrii. Závěr: Na základě našich zkušeností s instrumentací v nukleární medicíně lze tento princip radiační ochrany (RO) označit za velmi účinný nástroj optimalizace RO také při aplikaci radiofarmak. Takto optimalizovanou RO dochází k posílení bezpečnostních prvků ve vztahu k aplikujícím pracovníkům, čímž se vytváří prostor k možnému navyšování provozu a zvyšování dostupnosti péče v oblasti nukleární medicíny ve vztahu k pacientům.
Introduction: Exposition to radiation is necessarily connected with working at departments of nuclear medicine. The exposure can be influenced by the type of a radiopharmaceutical, its activity and the way of application. Method: This paper analyses the personal dosimetry of physicians at the Department of Nuclear Medicine, Masaryk Memorial Cancer Institute in Brno and evaluates the influence of instrumental application of radiopharmaceuticals on radiation exposure. Results: Use of instrumentation for application of radiopharmaceuticals results in reduction of occupational exposure of physicians by more than 90 % in ring and whole-body dosimetry. Conclusion: Based on our experience with instrumentation at department of nuclear medicine, this principle of radiation protection (RP) has proved to be a very effective tool of RP optimization in application of radiopharmaceuticals. Such optimization of RP reinforces safety elements in relation to the applicating staff, therefore enabling the increase in number of examined patients and increase in availability of nuclear medicine care in relation of patients.
- MeSH
- Safety MeSH
- Radiation Dosage MeSH
- Infusion Pumps * classification MeSH
- Radiation, Ionizing MeSH
- Humans MeSH
- Occupational Diseases prevention & control MeSH
- Nuclear Medicine methods instrumentation statistics & numerical data MeSH
- Radiation Protection methods instrumentation MeSH
- Radiopharmaceuticals * administration & dosage MeSH
- Radiometry methods instrumentation adverse effects statistics & numerical data MeSH
- Check Tag
- Humans MeSH
- Publication type
- Research Support, Non-U.S. Gov't MeSH
The aim of our study was to examine the in vivo expression of p21 and expression and activation of ATF-2, c-Myc, and CREB in rat peripheral blood mononuclear cells (PBMC) after whole body γ-irradiation and to assess its contribution to biodosimetry. For Western blot experiments, male Wistar rats were whole-body irradiated by a single dose of 0, 0.5, 1, 3, and 5 Gy (60 Co, 1 m, 0.7 Gy/min). As a positive control, leukaemic MOLT-4 cells were used. For ELISA experiments, male Wistar rats were whole-body irradiated by a single dose of 0, 1, 2, 3, 4, and 5 Gy (60 Co, 1 m, 0.6 Gy/min). Blood samples were taken 4 h after the irradiation and PBMC were isolated using centrifugation on Histopaque-1077. Expressions of p21, ATF-2, phospho-ATF-2Thr69/71 , c-Myc, phospho-c-MycThr-58/Ser62 , CREB, and phospho-CREBSer133 were measured using Western blot method. Expression of p21 was also quantified using ELISA. We observed increase of p21 expression in rat PBMC 4 h after irradiation. According to ELISA, p21 levels increased 2.0-, 3.1-, 5.5-, 3.0-, and 3.1fold after irradiation by 1, 2, 3, 4, and 5 Gy, respectively. We did not detect any expression or activation of ATF-2, c-Myc and CREB. Protein p21 could be considered as a perspective biodosimetric marker of clinically significant irradiation (≥1 Gy) in vivo in unstimulated PBMC.
- MeSH
- Activating Transcription Factors * MeSH
- Biomarkers blood MeSH
- Time Factors MeSH
- Whole-Body Irradiation MeSH
- Enzyme-Linked Immunosorbent Assay MeSH
- Cyclin-Dependent Kinase Inhibitor p21 metabolism radiation effects MeSH
- Radiation, Ionizing * MeSH
- Mitogen-Activated Protein Kinase Kinases metabolism radiation effects MeSH
- Rats, Wistar MeSH
- Cyclic AMP Response Element-Binding Protein metabolism radiation effects MeSH
- Proto-Oncogene Proteins c-myc metabolism radiation effects MeSH
- Radiometry statistics & numerical data MeSH
- Dose-Response Relationship, Radiation MeSH
- Blotting, Western MeSH
- Gamma Rays MeSH
- Animals MeSH
- Check Tag
- Animals MeSH
- Publication type
- Research Support, Non-U.S. Gov't MeSH
Gamma- and neutron doses in an experimental reactor were measured using alanine/electron spin resonance (ESR) spectrometry. The absorbed dose in alanine was decomposed into contributions caused by gamma and neutron radiation using neutron kerma factors. To overcome a low sensitivity of the alanine/ESR response to thermal neutrons, a novel method has been proposed for the assessment of a thermal neutron flux using the (14)N(n,p) (14)C reaction on nitrogen present in alanine and subsequent measurement of (14)C by liquid scintillation counting (LSC).
- MeSH
- Alanine chemistry radiation effects MeSH
- Electron Spin Resonance Spectroscopy methods statistics & numerical data MeSH
- Nuclear Power Plants standards MeSH
- Neutrons * MeSH
- Carbon Radioisotopes analysis MeSH
- Radiometry methods statistics & numerical data MeSH
- Scintillation Counting methods statistics & numerical data MeSH
- Dose-Response Relationship, Radiation MeSH
- Gamma Rays * MeSH
- Publication type
- Journal Article MeSH
- Research Support, Non-U.S. Gov't MeSH
- MeSH
- Radiation Dosage MeSH
- Phantoms, Imaging MeSH
- Financing, Organized MeSH
- Humans MeSH
- Radiation Monitoring methods instrumentation statistics & numerical data MeSH
- Emergencies classification MeSH
- Nuclear Medicine Department, Hospital statistics & numerical data MeSH
- Radiation Injuries classification MeSH
- Cesium Radioisotopes MeSH
- Cobalt Radioisotopes MeSH
- Radiometry methods statistics & numerical data MeSH
- Check Tag
- Humans MeSH
Fricke gel dosimeters in the form of layers are suitable to reconstruct bidimensional distributions of the absorbed dose; in accordance with their chemical composition and applying suitably developed algorithms, they can provide dose images of the different radiation components in a BNCT field. After the description of the applied method, this work presents the results obtained at the epithermal column of the BNCT facility at the NRI in Rez (CZ). The measured dose distributions are shown in comparison with data taken by means of other dosimeters thermoluminescence dosimeters (TLDs) and with calculations carried out with the Monte Carlo code MCNP5. The agreement with the results obtained by means of the different techniques is satisfying.
- MeSH
- Nuclear Reactors statistics & numerical data MeSH
- Phantoms, Imaging statistics & numerical data MeSH
- Humans MeSH
- Monte Carlo Method MeSH
- Radiotherapy Planning, Computer-Assisted statistics & numerical data MeSH
- Swine MeSH
- Radiometry instrumentation statistics & numerical data MeSH
- Solutions MeSH
- Fast Neutrons therapeutic use MeSH
- Boron Neutron Capture Therapy statistics & numerical data MeSH
- Thermoluminescent Dosimetry statistics & numerical data MeSH
- Water MeSH
- Gelatin MeSH
- Ferrous Compounds MeSH
- Animals MeSH
- Check Tag
- Humans MeSH
- Animals MeSH
- Publication type
- Journal Article MeSH
- Evaluation Study MeSH
- Research Support, Non-U.S. Gov't MeSH
- Comparative Study MeSH
- Geographicals
- Czech Republic MeSH
A thorax phantom has been designed, consisting of PMMA and PE plates containing a cavity filled with a laboratory-made lung-substitute. Fricke-gel dosimeters have been placed in the lung-substitute volume, and the phantom has been irradiated at the epithermal column of LVR-15 reactor. Absorbed dose images have been obtained for both gamma radiation and charged particles emitted in the (10)B reactions with thermal neutrons. Measurements with thermoluminescence dosimeters (TLDs) and Monte Carlo (MC) calculations have been performed too, in order to attain inter-comparison of results.
- MeSH
- Nuclear Reactors MeSH
- Boron therapeutic use MeSH
- Phantoms, Imaging statistics & numerical data MeSH
- Photons therapeutic use MeSH
- Gels MeSH
- Thorax MeSH
- Isotopes therapeutic use MeSH
- Humans MeSH
- Lung Neoplasms radiotherapy MeSH
- Radiotherapy Planning, Computer-Assisted statistics & numerical data MeSH
- Radiometry instrumentation statistics & numerical data MeSH
- Radiation-Sensitizing Agents therapeutic use MeSH
- Fast Neutrons therapeutic use MeSH
- Boron Neutron Capture Therapy instrumentation statistics & numerical data MeSH
- Check Tag
- Humans MeSH
- Publication type
- Journal Article MeSH
- Evaluation Study MeSH
- Research Support, Non-U.S. Gov't MeSH
- Geographicals
- Czech Republic MeSH
- MeSH
- Data Interpretation, Statistical MeSH
- Humans MeSH
- Radiation Monitoring methods standards statistics & numerical data MeSH
- Population MeSH
- Water Pollution, Radioactive prevention & control statistics & numerical data adverse effects MeSH
- Radiometry methods statistics & numerical data utilization MeSH
- Radioisotopes isolation & purification standards adverse effects MeSH
- Legislation as Topic history standards utilization MeSH
- Check Tag
- Humans MeSH
- Geographicals
- Czech Republic MeSH
- MeSH
- Housing standards statistics & numerical data legislation & jurisprudence MeSH
- Research Support as Topic MeSH
- Humans MeSH
- Radiation Monitoring methods standards statistics & numerical data MeSH
- Radiation Protection methods standards MeSH
- Radiometry methods statistics & numerical data utilization MeSH
- Radon isolation & purification standards adverse effects MeSH
- Ventilation methods standards MeSH
- Air Pollution, Indoor prevention & control adverse effects legislation & jurisprudence MeSH
- Check Tag
- Humans MeSH
- Geographicals
- Czech Republic MeSH
