Optimization Of Radiation Protection Research Articles

CT-scan patient dose monitoring on thorax examination in general hospital Sanjiwani Gianyar

Currently, in the world of medicine, the use of medical devices is very important. Along with the development of technology, the need for imaging in radio diagnostics is getting higher. This can be seen from the increasing trend of using medical devices by experts that are tailored to the needs of patients. The progress of radiological examination is growing rapidly with the use of radiation sources, one of which is by using a CT-Scan (Computed Tomography Scanning). The use of CT-Scans must be monitored to ensure the protection and safety of workers, patients, and the public. Protection requirements that must be met in the use of radiation are optimization of radiation protection and safety. The optimization of radiation protection is determined from the diagnostic guide level or the Indonesian Diagnostic Reference Level (I-DRL). The data used in this study is a chest contrast examination with the category of adults (15 years and over). From the CT-Scan irradiation, the CTDIVol and DLP values ??were determined in the 3rd quartile (Q3=75 percentile).

Distribution of tritium and its compounds in the environment under normal conditions of operating of Kalininskaya nuclear power plant

Tritium is one of the most important dose-forming radionuclides that determine the radiation situation in the area where nuclear fuel cycle enterprises are located. At the same time, it is not possible to catch the tritium formed during the operation of a nuclear power plant using modern, efficient and cheap technologies. This causes an increase in its concentration in environmental objects and an increase in the contribution of technogenic tritium to the radiation load of the population. Therefore, the task of monitoring the formation of tritium during the operation of nuclear power plants, the content of tritium in emissions and discharges of nuclear power plants, as well as the distribution of this radionuclide in the environment is especially urgent today. The study aims to analyze the environmental pollution due to emissions and discharges of tritium from the Kalininskaya nuclear power plant, the process of spreading tritium by air, as well as the accumulation of this radionuclide in water bodies, soil and food products grown in the area of the nuclear power plant. The following methods, developed by the specialists of the Burnasyan Federal Medical Biophysical Center were used during the research: 1) "Method for determining the volumetric activity of organic and inorganic tritium compounds in water bodies by liquid scintillation spectrometry". 2) "Methodology for determining the concentration of organic and inorganic tritium compounds in the air of the environment and industrial premises". 3) "The method for determining the specific activity of tritium compounds in soil and vegetation" was developed and tested in the course of field studies at the Kalinin NPP. As a sample preparation we used the method based on burning a selected sample in a specialized Pyrolyser-6 Trio oven. All prepared counting samples were measured by liquid scintillation spectrometry on a counter Tri-Carb 3180TR/SL. On the basis of an integrated approach to assessing the content of tritium and its compounds in air, water, soil and food, an analysis of the formation of environmental pollution due to emissions and discharges of tritium from the Kalinin NPP was carried out. It is shown that the transport of emissions from the NPP by air and the wind direction prevailing in the territory of the NPP location have a significant importance in the formation of the contribution to the ingress of tritium into foodstuffs. The necessity of taking into account the ingress of tritium and its compounds with nuclear plant emissions into the environment in the task of optimization of radiation protection of the population under conditions of normal operation of NPP is shown.

THE POTENTIAL TO USE TLD MEASUREMENTS TO VALIDATE THE OCCUPATIONAL RADIATION PROTECTION AT THE DEPARTMENT OF NUCLEAR MEDICINE.

Diagnostic examinations in nuclear medicine increase. This can cause a higher radiation burden to the personnel. The aim of this study was to create and apply a method to validate the occupational radiation protection at the Department of Nuclear Medicine using thermoluminescence dosemeters (TLD). Occupational doses in- and outside of the department and the dose rate distribution around the positron emission tomography/computed tomography (PET/CT) were validated in terms of Hp(10) using TLD-100. Backscatter correction factors were estimated to implement the TLD measurements on different materials. After correction for backscatter, the result indicates that doses in- and outside of the department are below recommended values and dose limits. The highest and the lowest dose rate were measured beside the 18F-autoinjector and the PET/CT gantry, respectively. The method of using TLD gives a good estimate of how the occupational radiation protection performs at the Department of Nuclear Medicine and can thus help in the optimization of radiation protection.

A MODEL FOR EVALUATING THE USE OF IMAGING IN IMAGE-GUIDED INTERVENTIONAL PROCEDURES—POSSIBLE IMPLICATIONS ON OPTIMISATION OF RADIATION PROTECTION

The present study focuses on introducing the concept of optimisation and proposing a model, including evaluation of image quality, to be used in the clinical routines where image-guided intervention is being performed. The overall aim of the study was to develop a model for evaluating the use of imaging in X-ray-guided interventional procedures and its possible implications on optimisation of radiation protection. In the search for an adequate evaluation model, data from endovascular interventions of the aorta (EVAR procedures) were used. The procedure was schematically described in steps. Every imaging event was connected to the steps in the medical procedure and was also described with the purpose of the imaging event. Available technical, as well as procedural parameters, were studied and analysed. Data were collected from the X-ray equipment for 70 EVAR procedures and, out of these, 12 procedures were randomly selected to be recorded on video to understand the procedure better. It was possible to describe the EVAR procedures in a general way with explanations of the clinical purpose connected to each imaging event. Possible quality parameters of the procedure were identified for the imaging events (radiation dose, image quality). The model method still needs to be refined and will then be applied to clinical data and to other clinical procedures to test the validity.

Proposals for the Russian quality assurance program in computed tomography

To ensure the quality assurance of CT-examinations, it is necessary to obtain the high-quality diagnostic information and maintain the optimal exposure levels of patients and medical staff. This paper is focused on the requirements and main aspects of quality assurance of CT-examinations, which include quality control of the equipment, methods of CT-image quality control, optimization of radiation protection, as well as management of the unintended and accidental medical exposure. The paper contains recommendations on quality control of diagnostic equipment, methods for monitoring the quality control of CT-images, values of diagnostic reference levels for the detection of abnormally high patient doses and optimization of the radiation protection of patients, as well as the recommendations for management of radiation and non-radiation accidents. All main sections of the paper represent an unified quality assurance system in computed tomography.

ESTIMATION OF ENTRANCE SURFACE AIR KERMA IN DIGITAL RADIOGRAPHIC EXAMINATIONS.

Contribution of radiation doses from medical X-ray examination to collective dose is significant. Unusually, high doses may increase the risk of stochastic effects of radiations. Therefore, radiation dose assessment was performed in 241 digital X-ray examinations in the study and was compared with published dose reference levels (DRLs). Entrance surface air kerma (ESAK) was calculated in chest PA, cervical AP/Lat, abdomen AP, lumbar AP/Lat and pelvis AP digital radiographic examinations (119 male and 122 female) following the International Atomic Energy Agency recommended protocol. Initially, 270 digital examinations were selected, reject analysis was performed and final 241 examinations were enrolled in the study for dose calculations. The exposure parameters and X-ray tube output were used for dose calculations. Effective doses were estimated with the help of conversion coefficients from ICRP 103. Median ESAK (mGy) and associated effective doses obtained were cervical spine AP (1.30mGy, 0.045mSv), cervical spine Lat (0.25mGy, 0.005mSv), chest PA (0.11mGy, 0.014mSv), abdomen AP (0.90mGy, 0.118mSv), lumbar spine AP (1.52mGy, 0.177mSv), lumbar spine Lat (7.76mGy, 0.209mSv) and pelvis AP (0.82mGy, 0.081mSv). Results were compared with the studies of UK, Oman, India and Canada. The calculated ESAK and effective dose values were less than or close to previously published literature except for cervical spine AP and lumbar spine Lat. The results reinforce the need for radiation protection optimization, improving examination techniques and appropriate use of automatic exposure control in digital radiography. ESAK values reported in this study could further contribute to establishing local DRLs, regional DRLs and national DRLs.

Thermohydraulic simulation of a channel with targets for production of radioactive isotopes in the IVV-2M nuclear reactor

The importance of radioisotope products usage in industry, science and medicine is underlined. The necessity of safety ensuring and radiation protection optimization while transporting the containers with radioactive isotopes is postulated. The information on isotope products making in the IVV-2M nuclear reactor of Research Institute of Nuclear Materials, JSC, from the beginning of 1990-ies is given. The data on application properties of Selenium 75 isotope are presented. The requirements to the thermohydraulic conditions of Se 75 isotope production in the nuclear reactor are formulated. The stages of a solid model development of a target for Se-75 isotope production as a part of an irradiation device of IVV-2M nuclear reactor are described. The results of hydraulic simulation of the coolant flow for various ways of devices arranging in the irradiation channel of the reactor are given. The analysis of thermohydraulic processes was performed with the help of SolidWorks Flow Simulation software.

Comparative analysis of radon concentrations in buildings of different energy efficiency classes on example of five Russian cities

A comparative analysis of the radon concentrations in modern multi-storey residential buildings of high energy efficiency class and buildings typical for urban areas of the twentieth century was carried out. The study was conducted in Russian cities located in various climatic zones – Ekaterinburg, Krasnodar, St. Petersburg, Salekhard, Chelyabinsk. The radon concentration in samples of buildings was measured using integrated radon radiometers based on nuclear track detectors according to a single method. The surveyed sample included 498 apartments in multi-apartment buildings. Among all the examined building types, the highest average radon concentration is observed in modern energy-efficient houses – 43 Bq/m3. In other types of buildings, the following average radon concentrations were obtained: brick 2–5 floors – 35 Bq/m3; panel 5 floors – 32 Bq/m3; panel 7–12 floors 1970-1990 years of construction – 22 Bq/m3; brick> 5 floors 1970–1980 years of construction – 20 Bq m3; panel, built since 1990 – 24 Bq/m3. The results of the study confirm the assumption that radon concentration in modern multi-storey energy-efficient houses is on average higher than in typical residential buildings of the Soviet period. The increased accumulation of radon in energy-efficient buildings is associated with a decrease in the building envelope permeability and the contribution of fresh air to the general air exchange. Despite the fact that there were no cases of exceeding hygienic standards for the indoor radon concentration in the framework of this study, the higher radon concentration in buildings of increased energy efficiency requires attention from the point of view of implementing the principle of optimization of radiation protection. In the future, extensive construction of energy-efficient buildings may increase the average and collective doses to the urban population in the Russian Federation.

The optimization of radiation protection to interventional cardiologists

Scattered dose radiation to occupational in interventional cardiology cannot be neglected due to the long time for each procedure. The limit dose for occupational is 20 mSv per year or 0.01 mSv/h. The aim of this study is to calculate the effective dose of occupational and to analyse the optimization of radiation protection in the Cath lab. The simulation has been done using Rando phantom as a patient and Unfors Xi as scattered dose measuring instrument (in mGy/h). The data is collected in 6 different positions from altitudes 25 cm to 75 cm with a range of 15 cm without protective shielding. Field size of primary beam is varied to 20×20 cm and 25×25 cm, while gantry tilt is varied to caudal, cranial, and Left Anterior Oblique (LAO). The obtained data is multiplied by weighting factor base on its height. The result shows that the effective dose of occupational is in the range of 0.18-0.94 mSv/h, which is exceed the limit dose. To accommodate the limit dose for occupational, we propose the limitation of procedure time to 21-110 hours a year or the use of protective shielding as thick as 1-1.6 mm lead.

Radiation dose measurements in intraoral and panoramic dental radiography in the Southern Region of Saudi Arabia

Objective: This study aims to estimate patient radiation doses for intraoral and panoramic dental radiography in the southern region of Saudi Arabia. Material and Methods: For intraoral units, the radiation doses were measured in terms of incident air kerma, Ki, and the detector was placed at 50 cm from the focus point. For panoramic dental radiography, the radiation doses were measured in terms of air Kerma-area product, PKA, using a calibrated CT ionization chamber. Results: For intraoral, the values for the estimated incidence of air kerma, Ki, ranged from 1.25 to 4.61 mGy (average: 2.55 mGy). For panoramic, the values for estimated Kerma-area product, PKA, values ranged from 79.5 to 122.1 mGy.cm2 (average: 99 mGy.cm2) for adults and ranged from 43.3 to 80.2 mGy.cm2 (average: 58.5mGy.cm2) for paediatrics. Conclusion: The study’s outcomes were compared with previous studies from other countries, indicating similar or slightly higher values. These results could serve as baseline data for radiation protection optimization and the development of national diagnostic reference levels in Saudi Arabia.

Radiology patient dosage monitoring for local diagnostic reference level

The utilization of radiation for health in Indonesia shows a significant increase, it can be seen from the increasing number of modalities of ionizing radiation sources used and the types of medical actions carried out with the help of radiation. The use of radiation must be monitored to ensure the protection and safety of workers, patients, and the community. In Government Regulation No. 33/2007 which regulates radiation safety for workers, the community and the environment, it can be seen that one of the protection requirements that must be met in the utilization of radiation is the optimization of radiation protection and safety. In diagnostic and interventional radiology, optimization can be interpreted as an attempt to make the dose received by patients as low as possible while maintaining optimum image quality. In this study, the effort to optimize patient dose is carried out on general radiography with the application of Si-INTAN (National Patient Dose Data Information System).

Key Elements for Optimization of Radiation Protection for the Postoperational Phase of Radioactive Waste Disposal

Key Elements for Optimization of Radiation Protection for the Postoperational Phase of Radioactive Waste Disposal

Comparison of deterministic and stochastic methods for external gamma dose rate calculation in the decommissioning of nuclear power plants

Calculations for individual scenarios are carried out for optimization of radiation protection, waste management, decommissioning planning, management of disposal facilities, and others. Comparative study of various calculation codes for different geometries with multilayer shields was performed. Reference geometries are models of the most frequently used waste packages in the decommissioning of nuclear power plants (NPP) in Slovakia. As representatives of deterministic calculation codes were chosen Visiplan, Microshield and Mercurad. Stochastic codes were represented by MCNP code. The impact of different build-up factor (BUF) selection in deterministic codes was evaluated. Experimental measurements with different multilayer shields were performed and compared to the results obtained by MCNP calculations. The percentage deviation between experiment and MCNP calculations was ±20% for every shielding configuration. Analysis of the differences between results was made. Recommendations for choosing of the most suitable calculation code for given application are formulated in this study.

Effect of the Principle of Radiation Protection Optimization on Radwaste Management Technology

Effect of the Principle of Radiation Protection Optimization on Radwaste Management Technology

RADIATION HYGIENIC ASPECTS OF THE SAFETY CONTROL OF THE PERSONNEL

Control of the radiation safety of workers is the one of the principal tasks of regulatory bodies responsible for the radiation safety and protection. This task is solved through the implementation of a set of organizational and technical measures, including:1) Organization and the execution of radiation monitoring; 2) Prediction of exposure doses to workers; 3) Selection of workers for the execution of radiation hazardous operations including emergency remedial works; 4) Planning of activities to implement the principle of the optimization of radiation protection; 6) Development and establishment of reference levels of exposure to radiation factors; 5) Organization of education and training of the personnel; 7) Continuous improvement of the occupational safety culture etc. The paper describes main actions of the management of radiation facilities aimed at the implementation of the above mentioned measures. Special attention is paid to the selection of the personnel of the required qualifications, possessing a sufficient reserve of an individual dose, to carry out radiation hazardous operations, to predict radiation doses to justify the development of the necessary protective measures and to plan actions to implement the principle of optimization of the radiation protection. The active use of the computer information and analytical system for the management of the protection from the occupational radiation is recommended. This system should include: 1. Database of individual occupational doses; 2. Database of radiation parameters characterizing the situation in workshops and at the industrial site of the radiation facility; 3. Software package for education and training of the personnel. The making of managerial decisions for the radiation protection of the personnel is aimed at increasing in the occupational reliability and, ultimately, improving the safety of radiation facilities, maintaining health and increasing the professional longevity of workers.

Оптимизация радиационной защиты на этапе вывода энергоблоков АЭС из эксплуатации

Оптимизация радиационной защиты на этапе вывода энергоблоков АЭС из эксплуатации

ESTIMATION OF ENTRANCE SURFACE RADIATION DOSE TO THYROID REGION IN COMPUTED TOMOGRAPHY BRAIN EXAMINATION

Objective: The objective of this study was to estimate the entrance surface radiation dose to the thyroid region in a computed tomography (CT) brain scan.Methods: Unfors Multi-O-Meter equipment was used to measure the entrance surface at the thyroid region of adult patients ranging from 18 to 70 years of age. A total of 115 patients were included in the study based on convenience sampling. The Multi-O-Meter was kept at the thyroid region during the scan, and the values for entrance surface dose (ESD) were noted from its monitor after the scan was complete.Results: The obtained data were analyzed and violate normal distribution; therefore, the median and quartiles were computed. The overall median (Q1, Q2), ESD of the patients, was 1.335 (1.213, 1.529) mGy. The minimum and maximum dose values recorded were 1.015 mGy and 1.964 mGy, respectively.Conclusions: The result showed a significant amount of entrance surface radiation dose to the thyroid region while taking a brain scan. This data can be used for optimization of radiation protection while undergoing CT scans of brain to reduce exposure to thyroid region.

ESTIMATION OF ENTRANCE SURFACE RADIATION DOSE TO THYROID REGION IN COMPUTED TOMOGRAPHY BRAIN EXAMINATION

Objective: The objective of this study was to estimate the entrance surface radiation dose to the thyroid region in a computed tomography (CT) brain scan.Methods: Unfors Multi-O-Meter equipment was used to measure the entrance surface at the thyroid region of adult patients ranging from 18 to 70 years of age. A total of 115 patients were included in the study based on convenience sampling. The Multi-O-Meter was kept at the thyroid region during the scan, and the values for entrance surface dose (ESD) were noted from its monitor after the scan was complete.Results: The obtained data were analyzed and violate normal distribution; therefore, the median and quartiles were computed. The overall median (Q1, Q2), ESD of the patients, was 1.335 (1.213, 1.529) mGy. The minimum and maximum dose values recorded were 1.015 mGy and 1.964 mGy, respectively.Conclusions: The result showed a significant amount of entrance surface radiation dose to the thyroid region while taking a brain scan. This data can be used for optimization of radiation protection while undergoing CT scans of brain to reduce exposure to thyroid region.

RADIATION EXPOSURE PROFILE IN RADIOLOGICAL DEPARTMENT TO SUPPORTING PROTECTION PROGRAMS IN HOSPITALS / RADIOLOGICAL CLINIC LABORATORY IN SEMARANG CITY

Background : All acts of radiation use, both for diagnostics, therapy and nuclear medicine, must go through a process of justification, limitation and optimization so that patients, officers and the surrounding environment get as much diagnostic benefit as possible with the smallest possible radiation risk. Some problems that arise in the Hospital / clinic, often ignore and do not pay attention to work exposure safety factors. The purpose of this study was to determine the profile of occupational radiation exposure and the effectiveness of radiation shielding in the radiology department of the Semarang city then compared to the reference dose to determine the optimization of radiation protection. Methods: The type of research conducted is quantitative research with a survey and observational approach. Exposure measurements were carried out in 5 radiology department, which included 3 hospitals and 2 clinical laboratories. Documents and room observations are also carried out. For the effectiveness of the radiation barrier it is also measured before and after the radiation shielding by using a surveymeter tool. The results data are then presented in descriptive analyses. Results: The results of the study of radiation exposure profiles in five radiology institutions, four institutions there was radiation exposure recorded on the surveymeter tool, with the largest exposure value was 0.099 mSv / h (still below the safe limit of 1 mSv / year). Only one hospital is safe, and there are no leaks. Conclusions: The effectiveness of the radiation retaining wall, four hospitals have a barrier level equal to 1 mm Pb at 80 kVp irradiation, and 1 hospital (RSJ) has a radiation barrier equivalent to 0.5 mmPb.

The First Step in the Optimization of Radiation Protection of Patients in Cerebral Angiography: Investigate the Possibility of Constructing the Diagnostic Reference Level by Imaging Objective/Disease Group Using Display Value of the Blood Vessel Imaging Apparatus

To optimize the radiation protection of patients, we investigated the possibility of constructing the diagnostic reference levels (DRLs) by imaging objective/disease group using display value of the blood vessel imaging apparatus (air kerma-area product: PKA, air kerma at the patient entrance reference point: Ka, r) in cerebral angiography. We used PKA and Ka, r recorded during surgery of 997 patients at our hospital, and classified them according to the purpose of imaging (diagnostic cerebral angiography or neuro interventional radiology) and disease group. Neuro interventional radiology (PKA: 268±155 Gy・cm2, Ka, r: 2420±1462 mGy) was significantly higher than that of diagnostic cerebral angiography (PKA: 161±70 Gy・cm2, Ka, r: 1112±485 mGy), (Mann-Whitney test, P<0.01). Significant difference was found between PKA and Ka, r for imaging purpose and disease group (Kruskal-Wallis test, P<0.05). It is highly probable that the DRL for cerebral angiography can be constructed by imaging purpose/disease group using display value (PKA, Ka, r) of the blood vessel imaging apparatus.