Pub Date : 2023-10-02DOI: 10.21514/1998-426x-2023-16-3-67-80
Z. A. Lantukh, M. P. Shatenok, Yu. V. Druzhinina, K. V. Tolkachev, I. V. Soldatov, S. A. Ryzhov, A. V. Vodovatov
There is a well-established opinion that the radiation safety of the patient and staff lies within the scope of the activities and responsibilities of the radiation diagnostics departments. However, repeated referrals and unjustified X-ray examinations from clinicians can make a significant contribution to the radiation load of the patient and the workload of the staff. The radiation safety requirements formulated in the article are designed for an effective monitoring tool for unjustified studies – the Clinical Decision Support System. The modern park of domestic software in this area was also analyzed. It was found, that the existing domestic Clinical Decision Support Systems do not fully meet the formulated current radiation safety requirements. The majority of clinical decision support system do not offer a choice of the most sparing methods of X-ray examinations (only 31% offer), and do not contain information about the accumulated patient dose for making a decision on the appointment of studies (only 23% contain). The developed methodology for assessing the Clinical Decision Support Systems will allow choosing and implementing the most optimal system in terms of radiation safety into clinical practice.
{"title":"Russian decision support systems in radiation diagnostics as an element of ensuring the radiation safety of patients","authors":"Z. A. Lantukh, M. P. Shatenok, Yu. V. Druzhinina, K. V. Tolkachev, I. V. Soldatov, S. A. Ryzhov, A. V. Vodovatov","doi":"10.21514/1998-426x-2023-16-3-67-80","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-67-80","url":null,"abstract":"There is a well-established opinion that the radiation safety of the patient and staff lies within the scope of the activities and responsibilities of the radiation diagnostics departments. However, repeated referrals and unjustified X-ray examinations from clinicians can make a significant contribution to the radiation load of the patient and the workload of the staff. The radiation safety requirements formulated in the article are designed for an effective monitoring tool for unjustified studies – the Clinical Decision Support System. The modern park of domestic software in this area was also analyzed. It was found, that the existing domestic Clinical Decision Support Systems do not fully meet the formulated current radiation safety requirements. The majority of clinical decision support system do not offer a choice of the most sparing methods of X-ray examinations (only 31% offer), and do not contain information about the accumulated patient dose for making a decision on the appointment of studies (only 23% contain). The developed methodology for assessing the Clinical Decision Support Systems will allow choosing and implementing the most optimal system in terms of radiation safety into clinical practice.","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135828284","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-10-02DOI: 10.21514/1998-426x-2023-16-3-22-36
I. K. Romanovich, A. B. Bazyukin, A. N. Barkovsk, A. M. Biblin, A. A. Bratilova, G. Ya. Bruk, K. V. Varfolomeev, A. V. Gromov, E. A. Drozdova, T. V. Zhesko, S. A. Ivanov, M. V. Kaduka, T. A. Kormanovskaya, O. S. Kravtsova, V. A. Nekrasov, V. P. Ramzaev, K. A. Saprykin, N. V. Titov, O. A. Isakov, E. I. Zlotnikova, A. G. Sosnitskiy, V. I. Filin, A. V. Kudryashov, A. A. Ladik, V. A. Lalayan
This study presents results of radiation-hygienic surveys of the Bryansk Oblast settlements bordering the Republic of Belarus. The data were obtained in the course of implementation of measures of the “Program of joint activities of Russia and Belarus within the framework of the Union State for the protection of the population and rehabilitation of the territories affected by the Chernobyl NPP accident” in 2019–2022. The first part of the study presents a general characteristic of the current state of the problem of returning the residents of radioactively contaminated territories to normal living conditions and provides information on the settlements of the surveyed region. The modern demographic composition of the population is considered; the structure of private subsidiary plots is investigated. The results described in this part of the study indicate the main ways, which are relevant for the formation of the internal exposure dose of the public at the current stage of the radiation accident.
{"title":"Results of modern radiation-hygienic surveys of settlements of Bryansk Oblast of the Russian Federation bordering the Republic of Belarus. Part 1: Characteristics of the settlements","authors":"I. K. Romanovich, A. B. Bazyukin, A. N. Barkovsk, A. M. Biblin, A. A. Bratilova, G. Ya. Bruk, K. V. Varfolomeev, A. V. Gromov, E. A. Drozdova, T. V. Zhesko, S. A. Ivanov, M. V. Kaduka, T. A. Kormanovskaya, O. S. Kravtsova, V. A. Nekrasov, V. P. Ramzaev, K. A. Saprykin, N. V. Titov, O. A. Isakov, E. I. Zlotnikova, A. G. Sosnitskiy, V. I. Filin, A. V. Kudryashov, A. A. Ladik, V. A. Lalayan","doi":"10.21514/1998-426x-2023-16-3-22-36","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-22-36","url":null,"abstract":"This study presents results of radiation-hygienic surveys of the Bryansk Oblast settlements bordering the Republic of Belarus. The data were obtained in the course of implementation of measures of the “Program of joint activities of Russia and Belarus within the framework of the Union State for the protection of the population and rehabilitation of the territories affected by the Chernobyl NPP accident” in 2019–2022. The first part of the study presents a general characteristic of the current state of the problem of returning the residents of radioactively contaminated territories to normal living conditions and provides information on the settlements of the surveyed region. The modern demographic composition of the population is considered; the structure of private subsidiary plots is investigated. The results described in this part of the study indicate the main ways, which are relevant for the formation of the internal exposure dose of the public at the current stage of the radiation accident.","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135895133","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-10-02DOI: 10.21514/1998-426x-2023-16-3-56-66
A. S. Vasilyev
For many years internal exposure to radon has been the main contributor to the annual dose to the population. The paper presents results of a hygienic assessment of doses and health risks for students (pupils) and employees of several educational institutions of the Leningrad region due to exposure to radon and its progeny, and also suggests the protocol for conducting measurements of indoor radon concentration in existing operated public buildings. Individual annual effective doses to students (pupils) and employees due to exposure to radon while in the building of an educational institution calculated on the basis of the results of instant measurements of radon EEC obtained in the normal operation mode of buildings ranged from 0.1 to 3.7 mSv/year for different institutions. However, calculation on the basis of the results of long-term measurements of radon concentration resulted in the dose values up to 10 times higher (from 0.2 to 22.9 mSv/year). Moreover, calculation on the basis of the results of instant measurements of radon EEC after leaving the premises for 12 hours with closed windows and doors according to the requirements of paragraph 6.5 of MU 2.6.1.2838-11 resulted in the dose values up to 7 times higher (from 0.1 to 13.5 mSv/year). Nevertheless, these high dose values do not reflect the real exposure scenario. According to the classification established in sanitary rules and norms OSPORB 99/2010, the exposure of students (pupils) and employees of several educational institutions can be classified as “increased” (from 5 to 10 mSv/year) or as “high” (more than 10 mSv/year) depending on methods and approaches to measuring indoor radon concentration. The average individual lifetime risk of radoninduced lung cancer death (based on the results of instant measurements of radon EEC obtained in the normal operation mode of buildings) for students (pupils) and employees of surveyed educational institutions ranged from 1.6∙10–4 to 1.4∙10–3. However, the usage of the results obtained with other methods and approaches to measuring indoor radon concentration, as a rule, did not lead to a significant increase in risk value, but in some cases it led to a change in the risk level category. The results of the assessment can be used to improve the method for indoor radon concentration monitoring in existing operated public buildings in the Russian Federation, which in turn will make it possible to obtain correct values of public doses and health risks.
{"title":"Exposure of students (pupils) and employees of educational institutions in the Leningrad region to natural sources of radiation Part 2: Hygienic assessment of doses and health risks depending on methods and approaches to measuring indoor radon concentration","authors":"A. S. Vasilyev","doi":"10.21514/1998-426x-2023-16-3-56-66","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-56-66","url":null,"abstract":"For many years internal exposure to radon has been the main contributor to the annual dose to the population. The paper presents results of a hygienic assessment of doses and health risks for students (pupils) and employees of several educational institutions of the Leningrad region due to exposure to radon and its progeny, and also suggests the protocol for conducting measurements of indoor radon concentration in existing operated public buildings. Individual annual effective doses to students (pupils) and employees due to exposure to radon while in the building of an educational institution calculated on the basis of the results of instant measurements of radon EEC obtained in the normal operation mode of buildings ranged from 0.1 to 3.7 mSv/year for different institutions. However, calculation on the basis of the results of long-term measurements of radon concentration resulted in the dose values up to 10 times higher (from 0.2 to 22.9 mSv/year). Moreover, calculation on the basis of the results of instant measurements of radon EEC after leaving the premises for 12 hours with closed windows and doors according to the requirements of paragraph 6.5 of MU 2.6.1.2838-11 resulted in the dose values up to 7 times higher (from 0.1 to 13.5 mSv/year). Nevertheless, these high dose values do not reflect the real exposure scenario. According to the classification established in sanitary rules and norms OSPORB 99/2010, the exposure of students (pupils) and employees of several educational institutions can be classified as “increased” (from 5 to 10 mSv/year) or as “high” (more than 10 mSv/year) depending on methods and approaches to measuring indoor radon concentration. The average individual lifetime risk of radoninduced lung cancer death (based on the results of instant measurements of radon EEC obtained in the normal operation mode of buildings) for students (pupils) and employees of surveyed educational institutions ranged from 1.6∙10–4 to 1.4∙10–3. However, the usage of the results obtained with other methods and approaches to measuring indoor radon concentration, as a rule, did not lead to a significant increase in risk value, but in some cases it led to a change in the risk level category. The results of the assessment can be used to improve the method for indoor radon concentration monitoring in existing operated public buildings in the Russian Federation, which in turn will make it possible to obtain correct values of public doses and health risks.","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135828294","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-10-02DOI: 10.21514/1998-426x-2023-16-3-37-45
L. V. Repin, R. R. Akhmatdinov, A. M. Biblin, A. V. Vodovatov, L. A. Chipiga, I. G. Shatskiy
adiation risks assessment in medical exposure of patients is one of the mandatory steps in justifying the medical radiological examinations. The main objectives of such assessment are the need for benefit-harm analysis, when prescribing a study, and informing patients or their legal representatives about the radiation risk associated with the recommended examination. The traditional approach to radiation risk assessment is the use of measures based on lifetime morbidity and/or mortality due to radiation exposure in risk characterization. However, the development of the methodology of population health assessment and the need to harmonize the methodology of radiation risk assessment with risks from exposure to factors of other nature imply the use of more informative generalized health indicators in the assessment of exposure to harmful environmental factors. The aim of actual work was to apply the developed methodology of radiation detriment assessment to characterize the risk by calculating DALY (number of years of healthy full life lost due to exposure to ionizing radiation) values for different sex and age groups of Russian patients undergoing computed tomography. To achieve this goal, the previously developed method of estimating the number of years of healthy life lost due to exposure to ionizing radiation was used. Calculations were performed with the use of a specially developed computer program based on the models of the International Commission on Radiological Protection using medical and demographic data of Russian population. The article presents the results of DALY calculation for six types of computed tomographic examinations. The use of DALY to characterize risk instead of the most widely used value of radiation detriment (or lifetime risk of death, relating the harm from the reduction in the quality of life in the case of non-fatal oncological disease) is an attempt to harmonize the methodology of radiation risk assessment with the methodologies of other kind of health risks. One of the directions of calculation results usage is the development of sexand age-dependent risk coefficients associated with medical exposure of patients. The analysis of the obtained results showed that the age distribution of risks agrees well with the data presented in the methodological recommendations MR 2.6.1.0215-20 “Assessment of radiation risk to patients in radiology examinations”. It is also shown that the DALY indicator can serve as a basis for comparative assessment of obtainable and avoidable risks in the field of medical radiation exposure of patients.
{"title":"Characterization of radiation risk associated with computed tomography for the Russian patients using disability-adjusted life years measure","authors":"L. V. Repin, R. R. Akhmatdinov, A. M. Biblin, A. V. Vodovatov, L. A. Chipiga, I. G. Shatskiy","doi":"10.21514/1998-426x-2023-16-3-37-45","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-37-45","url":null,"abstract":"adiation risks assessment in medical exposure of patients is one of the mandatory steps in justifying the medical radiological examinations. The main objectives of such assessment are the need for benefit-harm analysis, when prescribing a study, and informing patients or their legal representatives about the radiation risk associated with the recommended examination. The traditional approach to radiation risk assessment is the use of measures based on lifetime morbidity and/or mortality due to radiation exposure in risk characterization. However, the development of the methodology of population health assessment and the need to harmonize the methodology of radiation risk assessment with risks from exposure to factors of other nature imply the use of more informative generalized health indicators in the assessment of exposure to harmful environmental factors. The aim of actual work was to apply the developed methodology of radiation detriment assessment to characterize the risk by calculating DALY (number of years of healthy full life lost due to exposure to ionizing radiation) values for different sex and age groups of Russian patients undergoing computed tomography. To achieve this goal, the previously developed method of estimating the number of years of healthy life lost due to exposure to ionizing radiation was used. Calculations were performed with the use of a specially developed computer program based on the models of the International Commission on Radiological Protection using medical and demographic data of Russian population. The article presents the results of DALY calculation for six types of computed tomographic examinations. The use of DALY to characterize risk instead of the most widely used value of radiation detriment (or lifetime risk of death, relating the harm from the reduction in the quality of life in the case of non-fatal oncological disease) is an attempt to harmonize the methodology of radiation risk assessment with the methodologies of other kind of health risks. One of the directions of calculation results usage is the development of sexand age-dependent risk coefficients associated with medical exposure of patients. The analysis of the obtained results showed that the age distribution of risks agrees well with the data presented in the methodological recommendations MR 2.6.1.0215-20 “Assessment of radiation risk to patients in radiology examinations”. It is also shown that the DALY indicator can serve as a basis for comparative assessment of obtainable and avoidable risks in the field of medical radiation exposure of patients.","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135898920","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-10-02DOI: 10.21514/1998-426x-2023-16-3-101-117
P. S. Druzhinina, I. K. Romanovich, A. V. Vodovatov, L. A. Chipiga, R. R. Akhmatdinov, A. A. Bratilova, S. A. Ryzhov
The article presents the analysis of the structure of computed tomography diagnostics according to the forms of the federal state statistical observation (radiation-hygienic passports in 2011–2021, forms № 3-DOZ in 2011-2021 and forms № 30 in 2014–2020) in order to assess the status of CT diagnostics in the Russian Federation and identify the main trends in the development of this type of radiation diagnostics and patient doses. In 2011–2021, there was a sharp development of CT diagnostics in the Russian Federation – an increase in the number of CT examinations per 1000 people (up to a factor of 5.9 – from 32 CT examinations per 1000 people to 189 CT examinations per 1000 people) and the contribution of CT in the collective dose from medical diagnostic exposure (3 times from 26% to 77%). The number of CT examinations per 1 CT device from 2014 to 2019 increased by 2 thousand (52%), and in 2020 by another 1.85 thousand (32% compared to 2019) and reached 7.7 thousand. The increase in the number of CT examinations was mainly due to the increased use of CT equipment. The main contribution to the structure and collective dose of computed tomography in 2021 is made by examinations of chest (58%/65%), abdomen (8%/14%), pelvis and hips (3%/4%), skull and maxillofacial area (18%/7%). In 2011-2021 for chest CT examinations, the average effective dose was in the range from 4.2 to 5.9 mSv per examination, for abdomen – from 6.5 to 9.2 mSv, for pelvis and hips – 5 to 6.7 mSv, for skull and maxillofacial area – 1.5 to 2.4 mSv. The COVID-19 pandemic in 2020-2021 caused a change in the structure of CT examinations and collective dose in the Russian Federation – the chest CT examinations occupied the first place of the contribution to the number of examinations and the collective dose. The number of CT examinations per 1000 people and the contribution of CT to the collective dose from medical diagnostic exposure in the Russian Federation were significantly lower than those in foreign countries (up to a factor of 3.5 in the number of CT examinations per 1000 people and up to a factor of 1.6 of the contribution of CT to the collective dose).
{"title":"Trends in the development of computed tomography in the Russian Federation in 2011–2021","authors":"P. S. Druzhinina, I. K. Romanovich, A. V. Vodovatov, L. A. Chipiga, R. R. Akhmatdinov, A. A. Bratilova, S. A. Ryzhov","doi":"10.21514/1998-426x-2023-16-3-101-117","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-101-117","url":null,"abstract":"The article presents the analysis of the structure of computed tomography diagnostics according to the forms of the federal state statistical observation (radiation-hygienic passports in 2011–2021, forms № 3-DOZ in 2011-2021 and forms № 30 in 2014–2020) in order to assess the status of CT diagnostics in the Russian Federation and identify the main trends in the development of this type of radiation diagnostics and patient doses. In 2011–2021, there was a sharp development of CT diagnostics in the Russian Federation – an increase in the number of CT examinations per 1000 people (up to a factor of 5.9 – from 32 CT examinations per 1000 people to 189 CT examinations per 1000 people) and the contribution of CT in the collective dose from medical diagnostic exposure (3 times from 26% to 77%). The number of CT examinations per 1 CT device from 2014 to 2019 increased by 2 thousand (52%), and in 2020 by another 1.85 thousand (32% compared to 2019) and reached 7.7 thousand. The increase in the number of CT examinations was mainly due to the increased use of CT equipment. The main contribution to the structure and collective dose of computed tomography in 2021 is made by examinations of chest (58%/65%), abdomen (8%/14%), pelvis and hips (3%/4%), skull and maxillofacial area (18%/7%). In 2011-2021 for chest CT examinations, the average effective dose was in the range from 4.2 to 5.9 mSv per examination, for abdomen – from 6.5 to 9.2 mSv, for pelvis and hips – 5 to 6.7 mSv, for skull and maxillofacial area – 1.5 to 2.4 mSv. The COVID-19 pandemic in 2020-2021 caused a change in the structure of CT examinations and collective dose in the Russian Federation – the chest CT examinations occupied the first place of the contribution to the number of examinations and the collective dose. The number of CT examinations per 1000 people and the contribution of CT to the collective dose from medical diagnostic exposure in the Russian Federation were significantly lower than those in foreign countries (up to a factor of 3.5 in the number of CT examinations per 1000 people and up to a factor of 1.6 of the contribution of CT to the collective dose).","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135895318","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-10-02DOI: 10.21514/1998-426x-2023-16-3-91-100
V. S. Repin, K. V. Varfolomeeva, S. A. Zelentsova, G. V. Arkhangelskaya, K. A. Sednev
The article considers the methodological features of long-term observations of the dynamics of changes in low levels of tritium in water bodies of the environment located in places of potential contamination by tritium. The еxperience of measurements of tritium on the low-background liquid scintillation alpha-, beta-radiometer “Quantulus 1220-003” has shown, that the accuracy of estimating the absolute values of the specific activity of tritium in the samples under study at its low levels is significantly related to the counting rate of the background sample. When planning long-term dynamic observations of changes in low levels of tritium in water bodies, it is necessary to foresee a number of factors that affect the accuracy of the estimates. One of the most significant factors is the presence of a background sample with a count rate of not more than 0.6 imp/ min, which makes it possible to measure the activity concentration of tritium at a level of 1 Bq/l for 12 hours. The stability and reproducibility of the results can be monitored using a reference solution, which must be used throughout the entire period of dynamic observation. Calibration of the device using the reference solution should be provided each time the scintillation cocktail is changed, since there may be differences in efficiency up to 10% when using the same type of scintillators with different shelf life. For the preparation of counting samples, rooms with minimal levels of tritium in air moisture and at a significant distance from rooms where work with elevated levels of tritium activity is carried out should be chosen. When reusing vials, it should be borne in mind that the efficiency of tritium detection may decrease, therefore, when using such vials, calibration measurements of standard solutions should also be carried out.
{"title":"Methodological features of monitoring the long-term dynamics of low levels of tritium in the environment","authors":"V. S. Repin, K. V. Varfolomeeva, S. A. Zelentsova, G. V. Arkhangelskaya, K. A. Sednev","doi":"10.21514/1998-426x-2023-16-3-91-100","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-91-100","url":null,"abstract":"The article considers the methodological features of long-term observations of the dynamics of changes in low levels of tritium in water bodies of the environment located in places of potential contamination by tritium. The еxperience of measurements of tritium on the low-background liquid scintillation alpha-, beta-radiometer “Quantulus 1220-003” has shown, that the accuracy of estimating the absolute values of the specific activity of tritium in the samples under study at its low levels is significantly related to the counting rate of the background sample. When planning long-term dynamic observations of changes in low levels of tritium in water bodies, it is necessary to foresee a number of factors that affect the accuracy of the estimates. One of the most significant factors is the presence of a background sample with a count rate of not more than 0.6 imp/ min, which makes it possible to measure the activity concentration of tritium at a level of 1 Bq/l for 12 hours. The stability and reproducibility of the results can be monitored using a reference solution, which must be used throughout the entire period of dynamic observation. Calibration of the device using the reference solution should be provided each time the scintillation cocktail is changed, since there may be differences in efficiency up to 10% when using the same type of scintillators with different shelf life. For the preparation of counting samples, rooms with minimal levels of tritium in air moisture and at a significant distance from rooms where work with elevated levels of tritium activity is carried out should be chosen. When reusing vials, it should be borne in mind that the efficiency of tritium detection may decrease, therefore, when using such vials, calibration measurements of standard solutions should also be carried out.","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135899127","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-10-02DOI: 10.21514/1998-426x-2023-16-3-118-128
S. Yu. Bazhin, E. N. Shleenkova, V. Yu. Bogatyreva
The review presents description of the work and the main provisions on the working conditions for nondestructive testing operators from the standpoint of the system for ensuring radiation safety and radiation control. The values of the average annual effective doses of flaw detectorists in the Russian Federation and abroad are indicated. Official sources of information on doses in the Russian Federation and in the world, obtained from the results of individual dosimetric monitoring, were selected for presentation. The data of our own measurements were not included in this review. The difference in the name of the specialty of the studied group of personnel in Russian and English and the difference in the processing of primary measuring information in domestic and foreign sources of information are taken into account. The relevance of the need to resolve the issues of radiation safety and radiation monitoring of personnel involved in nondestructive testing is demonstrated, due to the fact that in the Russian Federation there are regulatory and methodological documents affecting the organization and conduct of individual dosimetric monitoring of personnel in the medical field and the nuclear industry, but they do not include personnel conducting nondestructive testing. Therefore, individual dosimetric control for nondestructive testing operators is carried out by accredited laboratories in accordance with the provisions of Methodical guidelines 2.6.1.3015-12.“Organization and management of individual dosimetry of medical staff”, i.e. without taking into account the exposure scenarios for personnel involved in nondestructive testing and the specifics of it work. The doses estimated in this way are included in the regional and federal databanks of personnel exposure doses. When entering dose values into data banks, there is no division of personnel into the personnel performing nondestructive testing in stationary and nonstationary conditions, therefore, the doses of personnel performing various types of nondestructive testing are averaged.
{"title":"Working conditions and values of average annual effective doses for nondestructive testing operators in the Russian Federation and abroad","authors":"S. Yu. Bazhin, E. N. Shleenkova, V. Yu. Bogatyreva","doi":"10.21514/1998-426x-2023-16-3-118-128","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-118-128","url":null,"abstract":"The review presents description of the work and the main provisions on the working conditions for nondestructive testing operators from the standpoint of the system for ensuring radiation safety and radiation control. The values of the average annual effective doses of flaw detectorists in the Russian Federation and abroad are indicated. Official sources of information on doses in the Russian Federation and in the world, obtained from the results of individual dosimetric monitoring, were selected for presentation. The data of our own measurements were not included in this review. The difference in the name of the specialty of the studied group of personnel in Russian and English and the difference in the processing of primary measuring information in domestic and foreign sources of information are taken into account. The relevance of the need to resolve the issues of radiation safety and radiation monitoring of personnel involved in nondestructive testing is demonstrated, due to the fact that in the Russian Federation there are regulatory and methodological documents affecting the organization and conduct of individual dosimetric monitoring of personnel in the medical field and the nuclear industry, but they do not include personnel conducting nondestructive testing. Therefore, individual dosimetric control for nondestructive testing operators is carried out by accredited laboratories in accordance with the provisions of Methodical guidelines 2.6.1.3015-12.“Organization and management of individual dosimetry of medical staff”, i.e. without taking into account the exposure scenarios for personnel involved in nondestructive testing and the specifics of it work. The doses estimated in this way are included in the regional and federal databanks of personnel exposure doses. When entering dose values into data banks, there is no division of personnel into the personnel performing nondestructive testing in stationary and nonstationary conditions, therefore, the doses of personnel performing various types of nondestructive testing are averaged.","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135828486","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-10-02DOI: 10.21514/1998-426x-2023-16-3-46-55
L. A. Chipiga, A. V. Vodovatov, A. A. Mosunov, K. A. Saprykin, A. V. Gromov, S. K. Vasiliev, A. V. Petryakova, D. A. Vazhenina, M. V. Odintsova, V. B. Nomokonova, A. A. Stanzhevsky, D. N. Maystrenko
The aim of this study was to evaluate the activity of 225 Ac in urine of patients undergoing radionuclide therapy with 225 Ac-DOTA-TATE. Activity concentration was determined in the urine samples collected within 72 hours after injection of 225 Ac-DOTA-TATE, using the ORTEC semiconductor gamma spectrometer, model TSP-DX-100T-PAC-PKG-1. Calculation of excreted activities was additionally performed based on scintig- raphy scans of patients receiving 225 Ac-DOTA-TATE. Scans were conducted 5 times for each patient: immedi- ately after injection, at 4 hours, and on the 1st, 2nd, and 3rd days after injection of the radiopharmaceutical. Absolute activity values and fractions of the injected activity were calculated based on the specific activity values. The results of the calculated activity concentration values demonstrate that maximum excretion was observed within the four hours after 225 Ac-DOTA-TATE injection. Significant differences between the two methods of determining 225 Ac activity were observed only on the third day after radiopharmaceutical injection, which allows for the simplification of future experimental work by using indirect radioactivity measurement methods for activity calculations. There were no significant differences between patient groups with different number of 225 Ac-DOTA-TATE injection, which allows for the exclusion of this parameter in the evaluation of experimental results. The results of this study represent the first published experimental data on the determi- nation of actinium excretion in patients.
{"title":"Preliminary assessment of <sub>225</sub>Ac excretion in patients undergoing radionuclide therapy with <sub>225</sub>Ac-DOTA-TATE","authors":"L. A. Chipiga, A. V. Vodovatov, A. A. Mosunov, K. A. Saprykin, A. V. Gromov, S. K. Vasiliev, A. V. Petryakova, D. A. Vazhenina, M. V. Odintsova, V. B. Nomokonova, A. A. Stanzhevsky, D. N. Maystrenko","doi":"10.21514/1998-426x-2023-16-3-46-55","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-46-55","url":null,"abstract":"The aim of this study was to evaluate the activity of 225 Ac in urine of patients undergoing radionuclide therapy with 225 Ac-DOTA-TATE. Activity concentration was determined in the urine samples collected within 72 hours after injection of 225 Ac-DOTA-TATE, using the ORTEC semiconductor gamma spectrometer, model TSP-DX-100T-PAC-PKG-1. Calculation of excreted activities was additionally performed based on scintig- raphy scans of patients receiving 225 Ac-DOTA-TATE. Scans were conducted 5 times for each patient: immedi- ately after injection, at 4 hours, and on the 1st, 2nd, and 3rd days after injection of the radiopharmaceutical. Absolute activity values and fractions of the injected activity were calculated based on the specific activity values. The results of the calculated activity concentration values demonstrate that maximum excretion was observed within the four hours after 225 Ac-DOTA-TATE injection. Significant differences between the two methods of determining 225 Ac activity were observed only on the third day after radiopharmaceutical injection, which allows for the simplification of future experimental work by using indirect radioactivity measurement methods for activity calculations. There were no significant differences between patient groups with different number of 225 Ac-DOTA-TATE injection, which allows for the exclusion of this parameter in the evaluation of experimental results. The results of this study represent the first published experimental data on the determi- nation of actinium excretion in patients.","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135828483","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-10-02DOI: 10.21514/1998-426x-2023-16-3-81-90
A. V. Petryakova, L. A. Chipiga, A. V. Vodovatov, M. Ya. Smolyarchuk
The development of nuclear medicine and, in particular, radionuclide diagnostics in the Russian Federation and the introduction of new technologies causes the necessity of the development and actualizing of the methods of the radionuclide diagnostics optimisation. Patient radiation protection optimisation through the equipment quality control and calibration is necessary to minimize the patient exposure levels and to obtain accurate and reproducible results of the uptake activity evaluation and high-quality image. However, in the national practice, conducting the equipment quality control and calibration is difficult due the lack of the requirements and methodology for quality control. The aim of the current study is the determination of the list of the necessary equipment quality control and calibration procedures in the radionuclide diagnostics department which will be harmonized between national and foreign standards and guidelines. The analysis of the national and the foreign documents standardized and recommended the gamma-camera and single photon emission computed tomography quality control and calibration procedures was performed in the study. The analysis demonstrated the national standards do not involve the frequency of the quality control for the most parameters. However, the methodology in the national standards is completely described, meets with foreign methodology and can be interchangeable, and can be used for quality control. Based on the analysis the list of the gamma camera and single photon emission computed tomography quality control and calibration procedures with recommended frequency, which is necessary for patient radiation protection optimisation and achievement of the accurate diagnostic results, are presented in the study.
{"title":"Equipment quality control during patient radiation protection optimisation in radionuclide diagnostics","authors":"A. V. Petryakova, L. A. Chipiga, A. V. Vodovatov, M. Ya. Smolyarchuk","doi":"10.21514/1998-426x-2023-16-3-81-90","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-81-90","url":null,"abstract":"The development of nuclear medicine and, in particular, radionuclide diagnostics in the Russian Federation and the introduction of new technologies causes the necessity of the development and actualizing of the methods of the radionuclide diagnostics optimisation. Patient radiation protection optimisation through the equipment quality control and calibration is necessary to minimize the patient exposure levels and to obtain accurate and reproducible results of the uptake activity evaluation and high-quality image. However, in the national practice, conducting the equipment quality control and calibration is difficult due the lack of the requirements and methodology for quality control. The aim of the current study is the determination of the list of the necessary equipment quality control and calibration procedures in the radionuclide diagnostics department which will be harmonized between national and foreign standards and guidelines. The analysis of the national and the foreign documents standardized and recommended the gamma-camera and single photon emission computed tomography quality control and calibration procedures was performed in the study. The analysis demonstrated the national standards do not involve the frequency of the quality control for the most parameters. However, the methodology in the national standards is completely described, meets with foreign methodology and can be interchangeable, and can be used for quality control. Based on the analysis the list of the gamma camera and single photon emission computed tomography quality control and calibration procedures with recommended frequency, which is necessary for patient radiation protection optimisation and achievement of the accurate diagnostic results, are presented in the study.","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135895714","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2023-10-01DOI: 10.21514/1998-426x-2023-16-3-13-21
V. Yu. Golikov
The paper demonstrates the limitations of the existing methodology for calculating the radiation shielding of X-ray rooms presented in SanPin 2.6.1.1192-03. It is shown that the algorithm for calculating the attenuation coefficient by the barrier does not take into account the features of the attenuation of different components of X-ray radiation: direct, scattered, and leakage radiation, which differ in the region of occurrence, intensity, energy spectrum, and other parameters. Instead, a single formula is used for all components, and the differences in their attenuation are taken into account by a parameter the values of which for different radiation components are in no way justified and are questionable. The calculation also does not take into account the distribution of the workload of X-ray machines by the tube voltage, the significant attenuation of direct X-ray radiation by additional structures necessary for image acquisition. The values of the radiation output of X-ray machines recommended for shielding design in SanPiN 2.6.1.1192-03 are 2–3 times overestimated in relation to the measured values. This leads to an unreasonable overestimation of the requirements for the thickness of radiation shielding in X-ray rooms and accordingly to suboptimal spending on healthcare. It is necessary to develop a new document to replace SanPiN 2.6.1.1192-03.
{"title":"Critical analysis of the existing approach to the calculation of radiation shielding in X-ray rooms","authors":"V. Yu. Golikov","doi":"10.21514/1998-426x-2023-16-3-13-21","DOIUrl":"https://doi.org/10.21514/1998-426x-2023-16-3-13-21","url":null,"abstract":"The paper demonstrates the limitations of the existing methodology for calculating the radiation shielding of X-ray rooms presented in SanPin 2.6.1.1192-03. It is shown that the algorithm for calculating the attenuation coefficient by the barrier does not take into account the features of the attenuation of different components of X-ray radiation: direct, scattered, and leakage radiation, which differ in the region of occurrence, intensity, energy spectrum, and other parameters. Instead, a single formula is used for all components, and the differences in their attenuation are taken into account by a parameter the values of which for different radiation components are in no way justified and are questionable. The calculation also does not take into account the distribution of the workload of X-ray machines by the tube voltage, the significant attenuation of direct X-ray radiation by additional structures necessary for image acquisition. The values of the radiation output of X-ray machines recommended for shielding design in SanPiN 2.6.1.1192-03 are 2–3 times overestimated in relation to the measured values. This leads to an unreasonable overestimation of the requirements for the thickness of radiation shielding in X-ray rooms and accordingly to suboptimal spending on healthcare. It is necessary to develop a new document to replace SanPiN 2.6.1.1192-03.","PeriodicalId":496413,"journal":{"name":"Радиационная гигиена","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"135459535","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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