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
- MeSH
- Occupational Health trends MeSH
- Humans MeSH
- Protective Clothing * standards MeSH
- Operating Rooms standards MeSH
- Radiation Protection * instrumentation MeSH
- X-Rays adverse effects MeSH
- Check Tag
- Humans MeSH
- Publication type
- Newspaper Article MeSH
A collection of personal protective equipment (PPE), suitable for use in case of accident in nuclear facilities or radiological emergencies, was gathered at the National Institute for Nuclear, Chemical and Biological Protection, Czech Republic. The shielding characteristics of the various PPE materials were measured via narrow geometry spectral attenuation measurements with point radionuclide sources covering a broad range of photon energies. Photon relative penetration and attenuation for relevant energies of the spectra were the principal experimentally determined quantities for tested PPE. Monte Carlo simulations in the MCNPX™ code were carried out to determine photon attenuation for respective energies in the tested PPE, and the results were compared to those determined experimentally. Energy depositions in a unit volume of an ORNL phantom were simulated in a radioactive aerosols atmospheric environment to determine effective doses both for the whole body and in various organs in the human torso during exposure to different dispersed radioactive aerosols while wearing one of the PPE protecting against X- and gamma-ray. This work aimed to determine the effective dose and its decrease for individual PPE protecting against X- and gamma-ray.
- MeSH
- Aerosols MeSH
- Radiation Dosage MeSH
- Photons MeSH
- Humans MeSH
- Monte Carlo Method MeSH
- Protective Clothing * MeSH
- Computer Simulation MeSH
- Radiation Protection instrumentation methods MeSH
- Scattering, Radiation MeSH
- Radiography MeSH
- X-Rays MeSH
- Gamma Rays * MeSH
- Check Tag
- Humans MeSH
- Publication type
- Journal Article MeSH
The graphite pile was set up at CMI to provide reference thermal neutron field for metrology and dosimetry purposes. It consists of three Pu-Be and three Am-Be radionuclide sources located in a 1.95 m (width) × 1.95 m (length) × 2.0 m (height) graphite moderator block. The neutron field in the volume of the experimental channel with dimensions of 40 cm × 40 cm × 135 cm (depth) was characterised experimentally and by Monte-Carlo calculations. Neutron fluence was determined by the activation of gold foils and Manganese tablets irradiated in nine different positions and by two 3He detectors of different construction irradiated in one position (bare and covered in three spherical PE moderators of 3, 3.5 and 4 inch diameter). Weighted mean value of the neutron fluence rate measured by all the abovementioned detectors in the pile centre was 2.91 × 104 cm-2 s-1 ± 1.8%. This value was used as a calibration factor for the Monte-Carlo model predictions. The neutron spectral fluence rate calculated by validated Monte-Carlo model was used to determine the conventionally true ambient and personal dose equivalent rates at different positions.
- Keywords
- kolimátor, kolimace,
- MeSH
- Humans MeSH
- Infant, Premature MeSH
- Infant, Newborn MeSH
- Radiation Exposure * prevention & control MeSH
- Radiation Protection * methods instrumentation MeSH
- Radiography * methods instrumentation MeSH
- Radiography, Thoracic methods MeSH
- Radiographic Image Interpretation, Computer-Assisted MeSH
- Radiographic Image Enhancement MeSH
- Check Tag
- Humans MeSH
- Infant, Newborn MeSH
This article addresses practical issues as being faced in the process of testing, verification and calibration of passive and active personal neutron dosemeters. Namely, a limited choice of neutron sources and geometric limitations occurring when ISO water phantom is used. The requirements of international standards for personal neutron dosemeters and the possibilities to fulfil them are discussed briefly.
- MeSH
- Radiation Dosage MeSH
- Phantoms, Imaging MeSH
- Calibration MeSH
- Humans MeSH
- Radiation Monitoring instrumentation methods standards MeSH
- Neutrons * MeSH
- Occupational Exposure analysis prevention & control MeSH
- Radiation Protection instrumentation methods standards MeSH
- Reproducibility of Results MeSH
- Water MeSH
- Check Tag
- Humans MeSH
- Publication type
- Journal Article MeSH
Rapid measurement techniques are required for a large-scale emergency monitoring of people. In vivo measurement of the bremsstrahlung radiation produced by incorporated pure-beta emitters can offer a rapid technique for the determination of such radionuclides in the human body. This work presents a method for the calibration of spectrometers, based on the use of UPh-02T (so-called IGOR) phantom and specific (90)Sr/(90)Y sources, which can account for recent as well as previous contaminations. The process of the whole- and partial-body counter calibration in combination with application of a Monte Carlo code offers readily extension also to other pure-beta emitters and various exposure scenarios.
- MeSH
- Beta Particles MeSH
- Whole-Body Counting instrumentation methods MeSH
- Radiation Dosage MeSH
- Electromagnetic Radiation MeSH
- Phantoms, Imaging MeSH
- Calibration MeSH
- Humans MeSH
- Monte Carlo Method MeSH
- Radiation Monitoring instrumentation methods MeSH
- Radiation Protection instrumentation methods MeSH
- Strontium Radioisotopes analysis MeSH
- Yttrium Radioisotopes analysis MeSH
- Radioisotopes MeSH
- Check Tag
- Humans MeSH
- Publication type
- Journal Article MeSH
The annual effective doses of aircrew members often exceed the limit of 1 mSv for the public due to the increased level of cosmic radiation at the flight altitudes, and thus, it is recommended to monitor them [International Commission on Radiation Protection. 1990 Recommendations of the International Commission on Radiological Protection. ICRP Publication 60. Ann. ICRP 21: (1-3), (1991)]. According to the Monte Carlo simulations [Battistoni, G., Ferrari, A., Pelliccioni, M. and Villari, R. Evaluation of the doses to aircrew members taking into consideration the aircraft structures. Adv. Space Res. 36: , 1645-1652 (2005) and Ferrari, A., Pelliccioni, M. and Villari, R. Evaluation of the influence of aircraft shielding on the aircrew exposure through an aircraft mathematical model. Radiat. Prot. Dosim. 108: (2), 91-105 (2004)], the ambient dose equivalent rate Ḣ*(10) depends on the location in the aircraft. The aim of this article is to experimentally evaluate Ḣ*(10) on-board selected types of aircraft. The authors found that Ḣ*(10) values are higher in the front and the back of the cabin and lesser in the middle of the cabin. Moreover, total dosimetry characteristics obtained in this way are in a reasonable agreement with other data, in particular with the above-mentioned simulations.
- MeSH
- Radiation Dosage MeSH
- Cosmic Radiation * MeSH
- Aircraft * MeSH
- Aviation MeSH
- Humans MeSH
- Radiation Monitoring instrumentation MeSH
- Occupational Exposure analysis MeSH
- Radiation Protection instrumentation standards MeSH
- Software MeSH
- Models, Theoretical MeSH
- Dose-Response Relationship, Radiation MeSH
- Check Tag
- Humans MeSH
- Publication type
- Journal Article MeSH
- Research Support, Non-U.S. Gov't MeSH
- Keywords
- mobilní C - ramena,
- MeSH
- Radiation Dosage MeSH
- Humans MeSH
- Protective Clothing standards utilization MeSH
- Operating Rooms * standards MeSH
- Radiation Protection * methods standards instrumentation MeSH
- Radiography * methods instrumentation utilization MeSH
- Reference Standards MeSH
- Quality Control MeSH
- Check Tag
- Humans MeSH
