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Radiation protection and safety documents for routine conditions are required to support the licensing requirements for nuclear power plant site. This research is focused in the assessment and analysis of the results of PWR safety study related to the routine release of radioactivity from the SMR subsystems and components of the 100 MWe-type PWR along with its consequences in the site. The core inventory calculation was done using ORIGEN2 software, applying release parameters from the existing analysis and calculation results. The radiological consequences were calculated by the PC-CREAM program package. Environmental and meteorological data were obtained using Arc-GIS and spatial analysis. The Bangka Belitung (Babel) site was used as the specific footprint. Analyzing PC-CREAM output data the radiological consequences of routine operation of 3 100 MWe PWR modules on Sebagin site (South Bangka) and Muntok site (West Bangka) in 16 sectors and within a radius of 20 km were concluded. The calculation results for the Sebagin site is that the maximumdose within a radius of 500 m (exclusion zone) is 1.15E+02 µSv/year. For a radius beyond 500 m, the maximum dose is 4.71E+01 µSv/year. Whereas for Muntok site (West Bangka), the maximum dose in the exclusion area (500m) is 3.10E+00 µSv/year. The individual dose for the Babel site in the exclusion area is below the dose constraint for non-radiation service workers as the general public of 0.3 mSv/year or 300 µSv/year, while the maximum dose for outside exclusion is also below the constraint as stipulated in BAPETEN Regulation No 4 Year 2013 on Radiation Protection and Safety.

OBJECTIVE To analyze historical radiation dose data from fluoroscopy users at a major university medical center and compare the impact of two alternate dose monitoring methodologies. MATERIALS AND METHODS Interventional radiologists have traditionally worn two radiation monitoring badges to estimate their radiation dose. This study evaluates if a single badge monitoring system can reduce the administrative burden of radiation monitoring without negatively impacting safety or compliance. This study reviewed the dose history data for a 10-y period including 114,500 individual dose measurements. These individuals were each issued two badges for each wear period, including one worn at the collar (outside a protective garment) and one worn at the chest or waist (beneath a protective garment). The dose for each of the badges was derived from the database of personnel dose records. Badges that could be clearly identified as improperly worn were excluded from the study. The EDE as assigned from the two-badge system and as derived from the wear of the collar badge only were both compared to the thresholds for ALARA notifications currently in use. RESULTS Calculated EDE values are an average of 2.7 times higher when applying a one-badge system as compared to a two-badge system. This is observed to result in a slight increase in the ALARA notification frequency (excluding badges improperly worn in the two-badge system). The overall increase in notification frequency is small because notifications are dominated by dose to the lens of the eye. CONCLUSION Although providing less accurate personnel dose estimates relative to a two-badge system, the use of a one-badge monitoring system for fluoroscopy users may have a minimal effect on radiation dose records and "as low as (is) reasonably achievable" (ALARA) notifications, with potentially significant savings in notifications due to improper badge wear, volume of radiation monitoring badges handled, and cost of the radiation monitoring system.

The article presents results of the analysis of information on the doses of technogenic exposure of personnel and the population due to the normal operation of radiation facilities, exposure of the population due to natural sources and technogenically altered radiation environment, and medical exposure of patients. The data were obtained using the Unified System of Individual Dose Control of the RF citizens for 2019. The analysis was carried out on the basis of the data contained in the forms of state statistical observation No. 1-DOZ (personnel individual doses), No. 2-DOZ (emergency doses), No. 3-DOZ (patients’ exposure doses) and No. 4-DOZ (population exposure doses from natural and technogenically impacted background) for 2019 submitted by the organizations and territories, the state sanitary and epidemiological supervision of which was carried out by Rospotrebnadzor and FMBA of Russia. The article used data obtained within the framework of Radiation-Hygiene passportization. In 2019, 18430 organizations dealing with technogenic sources of ionizing radiation submitted forms No. 1-DOZ with the information on the doses to personnel with a total number of 247934 people, of which 227723 people belonged to the personnel group A and 20211 person to the personnel group B. For these groups, the doses were assessed based on results of individual dosimetric control. In 2019, according to the Unified System of Individual Dose Control data, the average individual annual effective dose of technogenic exposure to the personnel group A was 1.19 mSv, and for the personnel group B it was 0.64 mSv. The total number of X-ray and radiological diagnostic procedures performed in the Russian Federation in 2019 exceeded 306.5 million, or 2.09 procedures per a citizen. The average annual effective dose of medical radiation exposure per one resident of Russia in 2019 was 0.62 mSv, and per procedure — 0.31 mSv. The submittedforms No. 4-DOZ of the constituent entities of the Russian Federation for 2019 contained results of the measurements of dose rate of gamma radiation in 9179 wooden houses, 11,307measurements in low-rise stone houses, 121323 measurements in multi-storey stone houses and 229342 measurements in open areas. These also contained results of 3930 measurements of radon levels in wooden houses, 5071 measurements in low-rise stone houses and 46896 measurements in multi-storey stone houses, as well as the results of 19444 analyses of the levels of natural radionuclides in drinking water. The average annual effective dose of radiation to residents of the Russian Federation from natural sources, according to all measurements for the period from 2001 to 2019, was 3.36 mSv. The article provides Appendices with the final forms of Unified System of Individual Dose Controlfor the Russian Federation for 2019. Data for the forms have been obtained on the basis of summarizing the information contained in the forms of state statistical observation No. 1-DOZ, 3-DOZ and 4-DOZ of the constituent entities of the Russian Federation.

Tacrolimus has a narrow therapeutic range and requires dose adjustment, usually based on the trough blood concentration but preferably on the area under the concentration–time curve over 12 h post-dose (AUC0–12h). The single-arm, multicentre, clinical study IMPAKT aimed: (i) to develop, in de novo kidney transplant recipients, pharmacokinetic models and maximum a-posteriori Bayesian estimators for a generic, immediate-release, oral formulation of tacrolimus to estimate tacrolimus AUC0–12h at different post-transplant periods using a limited sampling strategy, and considering the CYP3A5*3 polymorphism as a covariate and (ii) to compare the performance of these Bayesian estimators to those previously developed for the original formulation. Thirty patients were enrolled and 29 provided nine blood samples over 9 h at day 7 and months 1 and 3 post-transplant. Tacrolimus blood profiles measured with liquid chromatography-tandem mass spectrometry were modelled using one-compartment, double gamma absorption, linear elimination models developed in-house. Different limited sampling strategies of three time-points within 4 h post-dose were tested for the maximum a-posteriori Bayesian estimator of tacrolimus AUC0–12h. The models and estimators were validated internally and their performance compared to that of models previously developed for the original formulation. The concentration–time curves, AUC0–12h/dose and trough blood concentration/dose exhibited wide inter-individual variability. The covariate-free pharmacokinetic models developed for the three post-transplant periods closely fitted the individual profiles. Maximum a-posteriori Bayesian estimators based on three different limited sampling strategies and no covariate yielded accurate AUC0–12h estimates, including for the five cytochrome P450 3A5 expressers and for the four patients without corticosteroids. The 0–1 h–3 h strategy finally chosen had very low bias (− 4.0 to − 2.5%) and imprecision (root mean square error 5.5–9.2%). The maximum a-posteriori Bayesian estimators previously developed for the reference product fitted the generic profiles with similar performance. We developed original pharmacokinetic models and accurate maximum a-posteriori Bayesian estimators to estimate patient exposure and adjust the dose of generic tacrolimus, and confirmed that the robust tools previously developed for the original formulation can be applied to this generic.

Due to the rapid development and further improvement of radiation treatment technologies oncologists have an opportunity to precisely deliver individual dose distributions to the tumor, minimizing the doses obtained by critical organs and healthy structures. For the correct and successful application of these complex methods of radiation therapy, it was necessary to enforce the requirements for the technical and dosimetric parameters of the radiotherapy equipment. The purpose of the research is to determine the magnitude of the possible error for patients’ positioning during their radiotherapy treatments using medical linear accelerators by modeling the impact of the patient’s body on the treatment couch. To determine the values of a possible error, the authors have considered the design and characteristics of a typical treatment couch, developed a model of the “average” patient’s body (phantom), which allowed changing the load to the treatment couch with a step of 1 kg. The position parameters of treatment couches were determined for the main types of localization of radiation therapy for malignant tumors: head and neck tumors, breast tumors and pelvic tumors. Numerical values of the treatment coach deviations from prescribed horizontal position were experimentally established for a load from 40 to 180 kg for a treatment couch used at the N.N. Alexandrov National Cancer Centre of Belarus. Based on the obtained experimental data, the necessity to correct the patient's treatment conditions at the stage of treatment planning were confirmed in order to ensure the delivery accuracy of individual dose distributions as required by the radiation therapy protocols. Authors stated that an analysis of the dependence of the deviations in the dose delivered to the patients on the deviation of the radiotherapy table from its horizontal position should be carried out for each radiotherapy table used in clinical practice. The development and implementation of a mechanism that will allow considering this information when choosing the parameters of the patient’s treatment session and prescribing the dose for any localization of malignant neoplasms is needed.

The analysis of published data on the average annual effective doses to personnel of Russia, Germany, Switzerland, France and Canada in dynamics for 2013-2017 was performed. It was established that in the countries under consideration there are significant differences in the processing of primary measurement information, the calculation on its basis of individual effective doses, as well as ways of averaging the data obtained and their presentation. Factors that may lead to different interpretations of the results are considered: – taking into account background doses due to natural radiation; – use in processing the results of various (in different countries) values of the minimum level of registration; – dose averaging in the absence of activity periods (loss of a dosimeter / vacation), and when registering unexpectedly high doses. These differences exist between the data of foreign countries, but the data presented by the Russian Joint state system of control and accounting of the individual doses of the citizens are especially different. It is shown that the data on average annual effective doses to personnel presented in the Federal Data Base of personnel exposure doses within the framework of the Russian Joint state system of control and accounting of the individual doses is 3-4 times higher than in foreign countries. It is shown that such a difference is caused not by actually high doses, but by the method of processing primary information and averaging data during generalization. It should be noted that such differences occur only for extremely small doses of technogenic exposure to personnel, and do not lead to a significant impact on the overall assessment of the state of radiation safety in the country, but when comparing with other countries, it is necessary to understand the reasons for such differences. The purpose of this work was to identify the causes of these discrepancies and to develop a method for processing primary measurement information and averaging the data when summarizing the results, which allows them to be significantly reduced. Such a method should ensure that the effective doses of personnel closest to the conditionally true values are obtained in the entire range of values, and can be used to summarize the data contained in the Federal Data Base of personnel exposure doses. Since the conversion of the data contained in the Federal Data Base of personnel exposure doses was not the task of the authors of this article, in order to achieve this goal, an attempt was made to process and summarize the measurement results (total 23 204) of the quarterly values of the individual dose equivalent Hp (10) obtained in the Laboratory of Radiation Control of Saint-Petersburg Research Institute of the Radiation Hygiene after Professor P.V. Ramzaev. Such processing has been performed. The subsequent comparison showed that the average annual effective doses to the personnel of medical organizations of St.-Petersburg, in which individual dosimetric control was carried out in the Laboratory of Radiation Control, transformed according to the developed algorithm, are much better consistent with similar data from foreign countries.

The aim of CONFIDENCE WP2 is to improve the situation awareness in the early phase of a nuclear accident by trying to reduce the uncertainty in individual dose assessment when dealing with external and internal exposures. Main WP2 research actions to improve external dosimetry in this emergency frame were the development of destruction-free protocols using electronic components in smartphones for external dose measurements, Monte Carlo (MCNP) calculations for organ dose assessment with associated uncertainties and the organization of a workshop for integration of biodosimetry into emergency response. On the other hand, one of the main concerns after the release of radioactive material in case of a nuclear reactor accident is the intake of radioiodines in workers and population. A smartphone/tablet application for direct calculation of thyroid doses from monitoring data of the content of 131I (and 132I) in the thyroid was developed during the project (Prototype of processing unit for thyroid dose monitor [IDOSE]). Up to date age-dependent ICRP dose per content values are used by this tool, allowing a rapid screening of exposed persons. A sensitivity analysis on thyroid doses was carried out, considering 16 exposure scenarios leading to 16 different dose estimates, using ICRP56/119 (ICRP60) vs. ICRP130/137 iodine models for adults, varying the time of intake, the time pattern (acute vs. chronic) and considering not well defined relative abundance of short-lived radioiodines and 132Te. Real cases of Europeans contaminated in Japan shortly after the Fukushima NPP accident (low doses), and artificial cases of high doses generated to see the impact of the different parameters in this study, were used for applying this multi-intake scenario approach. Main conclusions of the study are presented here.

Results of individual monitoring for personnel of X-ray surgical teams in several clinics of St. Petersburg are presented and analyzed. Measurements of the operational quantities – individual dose equivalents Hp (3) and Hp (10) were performed by thermoluminescent dosimetry method. Dosimeters designed to measure Hp (3) were located in the operators forehead area, and to determine Hp (10) both above the operator ‘s individual protective apron in the collar or chest area and under the protective apron in the chest area. The results of 34 measurements of the annual values of Hp (3) and Hp (10) measured above the apron and 24 values of Hp (10) measured below the apron were processed and analyzed. The results after the statistical treatment show that the probability of exceeding the annual values of Hp (3) in the personnel of X-ray surgical teams of the new dose limit 20 mSv is small, less than 1%. Exceeding the current dose limit of the equivalent exposure dose of the lens of the eye (150 mSv) is hardly possible at all under normal conditions. The best solution for evaluating the radiation dose of the lens of the eye is to measure the individual equivalent of the dose Hp (3), using a suitably calibrated TL-dosimeter (thermoluminescent dosimeter) located near the worker’s eyes. However, this additional dosimeter is only necessary when the values of eye lens equivalent dose can approach the new value of dose limit of 20 mSv. According to the results of the study, it is possible to introduce such an additional dosimeter if the annual value of Hp (10) recorded by the dosimeter located above the protective apron is more than 10 mSv.

The work provides a comparative analysis of average annual individual radiation doses based on the obtained values of individual dose equivalent Hp (10), which had been obtained during 5 years of investigations (2014-2018) by using the thermo-luminescent dosimetry method of 70 employees working computed tomography, radioscopy, fluorography and radiography from 15 medical institutions in Dushanbe city. The ratio of medical personnel of the different professional groups showed that 63% of them were engaged in radiography, 19% x-ray, 10% computed tomography and 8% radioscopy. Analysis of the average annual radiation doses of every occupational group showed that the specialists in charge of fluorography have a high dose (max 1.74 mSv) and the personal of computed tomography have the lowest dose (max 1.34 mSv), and over time there is a tendency to equalize the values of average annual doses for all professional groups in the area close to the value of 1.5 mSv. The obtained data of the effective annual dose for all occupational categories had not exceeded the permissible dose limits values required by the «Radiation Safety Standards» (NRB-06 SP 2.6.1.001-06). Calculations are given without subtracting background values. The analysis data allows to identify the most exposed professional groups and to address the issues of ensuring radiation safety in a targeted manner.

In the last years radiation-hygienic passportization and Joint state system of control and accounting of the individual doses of the citizens have become a trusted source of the validated data on the state of the radiation safety in the Russian Federation and have become the basis of the Russian system of the information provision of the radiation safety. Annual analysis of that data is presented in the annual information bulletin “Doses of the population of the Russian Federation”. The current study is focused on the analysis of the data from the information bulletins to evaluate the trends in the doses of the Russian population from main sources of ionizing exposure in 2003–2018. It is indicated that the mean annual doses from man-made exposure of the group A staff in that period varies from 1,0–1,4 mSv per year, group B – 0,65–0,8 mSv per year. The number of exceedances of the annual dose limits from group A staff varied from 5 to 52 per year; for group B – 0–22 per year. For the whole investigated period there were only three cases of the exceedance of the 50 mSv annual individual dose for group A staff and four cases of the exceedance of the 12,5 mSv annual effective dose for group B staff. Mean effective dose per X-ray examination in 2006–2013 was decreasing from 0,56 mSv to 0,26 mSv and started to slowly increase leading to 0,29 mSv in 2018. The same trends were identified for the mean dose from medical exposure per citizen: reduction in 2003-2013 from 0,86 mSv to 0,45 mSv with the subsequent increase up to 0,56 mSv. The biggest contributor for the dose from medical exposure is computed tomography: the number of CT examinations increased from 1,3 mln in 2003 to 11,7 mln in 2018; contribution to the collective dose – from 5,7% to 54%. Mean annual effective doses from natural exposure of the population of the Russian regions varied from 1,6 to 15,1 mSv per year with the mean value for Russia of 3,11 – 3,79 mSv/year. The highest mean annual doses exceeding 5 mSv in each year were observed in Republic of Altay, Jewish Independent Region, Stavropol and Zabaikalskiy Krai, Republic of Tyva and Irkutsk region. Total effective doses exceeding 10 mSv/year were observed in Republic of Altay and Jewish Independent Region. For ten subjects of the Russain Federation (Republics of Buryatia, Altay, Tyva, Stavropol and Zabaikalskiy Krai, Irkutsk and Chita regions, Jewish Independent Region, Aginsko-Buryatskiy and Ust’-Ordinskiy independent districts) they exceed 5 mSv/year for the whole assessed period.

Cervical cancer patients may sometimes experience subserosal tandem insertions during brachytherapy, which can lead to increased but unnoticed irradiations to the small bowel (SB). In this study, we aimed to quantify and further predict individual SB dose increase and to increase focus on the SB in subserosal tandem insertions. Images and dosimetry data of cervical cancer brachytherapy with subserosal insertion (SI) were reviewed. The percentage increases in the SB dose compared with intracavitary insertion (II) at 8 points of D(x)cc with 10 cc intervals were assessed. SI was classified into anterior and posterior SI according to the insertion site. The differences in minimum distance from the tandem tip to the SB on the axial view between these 2 insertions were tested using the Mann-Whitney test. The distance and D(x)cc were involved in the individual dose increase model by linear regression as prediction factors. A total of 27 insertions were evaluated, including 8 insertions with SI and 19 insertions with II. The median percentage increases in the normalized SB dose for all SI showed a logarithmic trend with a 55.4% increase at the hotspot. In contrast to posterior SI, anterior SI demonstrated a more significantly logarithmic trend, which featured highly increased doses at the hotspot (79.1% for the absolute SB dose and 137.8% for the normalized SB dose). The prediction models can predict the percentage dose increases in SI: Increased D(x)cc [%] = 31.370 – 7.865 ln (distance) – 3.949 ln (x) (absolute SB dose), and Increased D(x)cc [%] = 55.618 – 18.591 ln (distance) – 7.232 ln (x) (normalized SB dose). We developed prediction models for individual SB dose increase in SI in our study. SB hotspots in anterior SI require greater attention during cervical cancer brachytherapy. The models are new ones and are given for the first time.

The Chernobyl accident on 26 April 1986 led to a sharp increase in thyroid cancer (TC) incidence in the individuals exposed to radiation in childhood. The major risk factor for TC was exposure to Iodine-131 (131I). Here, we estimated the thyroid doses due to 131I intake for 2041 participants of the genome-wide association study of TC in Belarusian people exposed to radioactive fallout from the Chernobyl accident. The following parameter-values specially developed in this study were used to estimate individual thyroid doses: (i) scaling factors for adjustment of the model-based doses, (ii) age and gender diet to characterize 131I intake, and (iii) area-, age- and gender-specific S-values for the thyroid gland per 131I decay in the thyroid. The most reliable doses were calculated for 103 people with measured 131I thyroid activity (the arithmetic mean of 1.2 Gy, median 0.52 Gy), and 275 individuals with detailed residential history and dietary data (the arithmetic mean of 0.41 Gy, median 0.24 Gy). The arithmetic mean of thyroid doses among all study participants was 0.23 Gy (median 0.082 Gy); the highest individual dose was 9.0 Gy. Special attention was paid to the reliability and validity of the obtained estimates, in particular for the individuals without 131I thyroid activity measurements and individual data on residential history and diet, by comparing those with the doses from other post-Chernobyl epidemiological studies. Overall, the doses estimated in the current study were in reasonable agreement with previously reported thyroid doses. These doses will be used in the genome-wide association study of TC in people exposed in Belarus to 131I after the Chernobyl accident.

Purpose: Descriptive analysis of the distributions of organ/tissue doses for individuals exposed to radiation as a result of liquid waste releases into the Techa River by the Mayak Production Association (PA) in 1949–1956. Material and methods: The dosimetry system TRDS-2016D has been used to compute individual doses of external and internal exposures. TRDS-2016D databases include information on radionuclide intakes and dose rates in air for settlements located in the contaminated areas of the Techa River and the East Ural Radioactive Trace (EURT). Combining these village-average data with the residence history and age of a particular person, the system produces an individual scenario of external exposure and individual radionuclide intakes and then calculates corresponding external and internal doses from the Techa River and EURT. Available 90Sr-body-burden measurements and available information on individual household locations relative to the contaminated river have been used for refinement of individual dose estimates. Results: Individual doses have been calculated for 29,647 persons included in the Techa River Cohort (TRC). According to residence history data, 5,280 members of the TRC were additionally exposed due to residency in the EURT villages. The cohort-average dose for the majority of extra-skeletal tissues does not exceed 100 mGy, while for the red bone marrow (RBM) it is equal to 350 mGy. In addition to the doses from the Techa River and EURT, individual thyroid doses for TRC members exposed to the Mayak PA atmospheric 131I releases have been calculated in a separate computer program. The cohort–average thyroid dose is 210 mGy. Maximum doses (about 1 Gy to the majority of extra-skeletal tissues and over 7 Gy to the thyroid and RBM) are observed for the persons who lived in their childhood and adolescence in the upper Techa region at close distance to the Mayak PA. Conclusion: The TRC members were exposed to chronic radiation over a wide range of doses, but at low-to-moderate-dose rates. Estimates of absorbed doses can be used to analyze the dose dependences of the incidence of solid cancers and leukemias. This can make it possible to verify risk coefficients of low-dose-rate effects of ionizing radiation which can be used for radiation protection purposes.

The decommissioning of one nuclear power plant in a multi-unit nuclear power plant (multi-unit NPP) site may pose radiation exposure risk to decommissioning workers. Thus, it is essentially required to evaluate the exposure dose of decommissioning workers of operating multi-unit NPPs nearby. The ENDOS program is a dose evaluation code developed by the Korea Atomic Energy Research Institute (KAERI). As two sub-programs of ENDOS, ENDOS-ATM to anticipate atmospheric transport and ENDOS-G to calculate exposure dose by gaseous radioactive effluents are used in this study. As a result, the annual maximum individual dose for decommissioning workers is estimated to be 2.31×10-3 mSv·y-1, which is insignificant compared with the effective dose limit of 1 mSv·y-1 for the public. Although it is revealed that the exposure dose of operating multi-unit NPPs does not result in a significant impact on decommissioning workers, closer examination of the effect of additional exposure due to actual demolition work is required. The calculation method of this study is expected to be utilized in the future for planned decommissioning projects in Korea. Because domestic NPPs are located in multi-unit sites, similar situations may occur.

Standardised growth curves (SGCs) were established for extracts of potassium feldspar (K-feldspar), plagioclase and polymineral grains from various geological settings (deserts, loess, lake or fluvial deposits) from Northern China. Single-aliquot regenerative-dose (SAR) protocol was used with the measurements of multiple elevated temperature post-IR IRSL (MET-pIRIR) signals from 50 °C to 250 °C with an interval of 50 °C. Regenerative-dose normalisation was applied for the SGC construction. The shapes of the SGCs of K-feldspar vary between IRSL signals measured at different temperatures. For coarse grains (63–180 μm), the SGCs of the K-feldspar, plagioclase and polymineral fractions are close to each other. However, the polymineral fine grains (4–11 μm) have a distinct SGC from the coarse-grain fractions. It may be caused by the difference in alpha irradiation. Two test doses (145 Gy and 72.5 Gy) were applied to construct the SGCs for K-feldspar. The SGC built with the larger test dose has a larger characteristic saturation dose (D0). Test dose used for equivalent dose (De) measurements need to be the same as the test dose used for SGC construction, otherwise the SGC De may not be estimated accurately. With the same test dose used, the De values estimated from SGCs are identical with the De values generated from individual dose response curves.

The article presents the results of the generalized analysis of the data on staff, patient, and public doses from ionizing radiation obtained from the Unified System of Individual Dose Control for 2017. The analysis is conducted on the basis of the annual data from the forms of Federal State Statistical. Observation No.1-DOZ (staff individual doses), No.2-DOZ (doses from radiation accidents), No.3-DOZ (patient doses) and No.4- DOZ (public doses from natural and technogenically impacted background). The information is submitted by the organizations and territories under the supervision of the Rospotrebnadzor and FMBA of the Russian Federation. The article is based on the data obtained within the framework of Radiation-Hygiene passportization. In 2017, 18 324 organizations working with the artificial radiation sources submitted the form No.1-DOZ. The form No.1-DOZ contains data on 235 271 staff individual doses, 215 290 of the staff group A and 19 981 the staff group B with individual monitoring. In 2017, the average individual dose for the staff group A was 1,23 mSv, the staff group B – 0,67 mSv. In 2017, 13 036 healthcare organizations submitted the form No.3- DOZ. According to the No.3-DOZ data, more than 286 mln. X-ray procedures were conducted in the Russian Federation in 2017. An average dose per capita from medical exposure was 0,55 mSv/year and a mean dose per an X-ray examination was 0,28 mSv. In 2017, the form No.4-DOZ contained data on 8 130 measurements of gamma-radiation dose rate in wooden houses, 1 557 measurements in one-storey stone houses, 126 550 measurements in multi-storey stone houses and 178 138 measurements on the open ground As well as the results of 4 417 measurements of radon concentration levels in wooden houses, 5 971 measurements in one-storey stone houses, 57 461 measurements in multi-storey stone houses. The public average effective dose from natural ionizing radiation sources corresponded to 3.34 mSv/year, the average values for the subjects of the Russian Federation fall in the range from 2,15 mSv/year (Nenets Autonomous Okrug) to 8,9 mSv/year (Altai republic). The article includes the Annexes with the final generalized forms of the Unified System of Individual Dose Control in 2017 based on the forms of statistical observations No. 1-, 3- and 4-DOZ of the subjects of the Russian Federation.

Dose- and dose rate-dependent increase in the number of СD3+СD16+CD56+-lymphocytes and lysosomal activity of neutrophils was noted in peripheral blood of the Techa riverside residents with increased level of TCR gene-mutated T lymphocytes long after chronic exposure of predominantly red bone marrow (mean exposure dose was 0.89 ± 0.09 Gy, individual dose range was 0.09–1.96 Gy). The performed analysis showed that the above-mentioned immunological changes could be a response to an increase in the frequency of mutations (TCR mutations in particular) in the cells of exposed individuals.

Background: Peptide receptor radionuclide therapy (PRRT) is an emerging therapeutic option for the treatment of neuroendocrine tumors (NETs), and the number of publications in this field has been increasing in recent years. The aim of the present study was to present the research status and summarize the key topics through bibliometric analysis of published PRRT literature.Methods: A literature search for PRRT research from 2000 to 2019 was conducted using the Science Citation Index Expanded of Web of Science Core Collection (limited to SCIE) on August 4, 2020. The VOSviewer, R-bibliometrix, and CiteSpace software were used to conduct the bibliometric analysis.Results: From 2000 to 2019, a total of 681 publications (523 articles and 158 reviews) were retrieved. Annual publication outputs grew from three to 111 records. Germany had the largest number of publications, making the largest contribution to the field (n = 151, 22.17%). Active cooperation between countries/regions was observed. Kwekkeboom from the Erasmus Medical Center is perhaps a key researcher in the field of PRRT. The European Journal of Nuclear Medicine and Molecular Imaging and Journal of Nuclear Medicine ranked first for productive (n = 84, 12.33%) and co-cited (n = 3,438) journals, respectively. Important topics mainly included matters related to the efficacy of PRRT (e.g., 90Y-dotatoc and 177Lu-dotatate), the long-term adverse effects of PRRT (e.g., hematologic and renal toxicities), standardization of NETs and PRRT in practice, the development of medical imaging techniques, and the individual dose optimization of PRRT.Conclusion: Using bibliometric analysis, we gained deep insight into the global status and trends of studies investigating PRRT for the first time. The PRRT field is undergoing a period of rapid development, and our study provides a valuable reference for clinical researchers and practitioners.

Hypotension in the Emergency Department (ED) and the prehospital setting has been associated with significant morbidity and mortality. Limited literature exists exploring the utilization of intravenous (IV) bolus-dose epinephrine (BDE) by Emergency Medical Services (EMS).A retrospective review evaluated patients transported to an academic medical center who had received IV BDE by a single urban EMS system from 2016 to 2020. The primary outcome was to assess the influence IV BDE had on systolic blood pressure (SBP). Secondary objectives were to assess changes in heart rate (HR), the impact of dose variability on SBP, and the incidence of severe hypertension (SBP220 mmHg).A total of 55 patients who received 96 administrations of IV BDE were included in the analysis. The most common individual dose was 10 μg (76.0%) and 45.5% received multiple doses. The median weight-based dose of BDE was 0.14 μg/kg. A significant increase in SBP (median 14.0 mmHg) was noted among all patients following BDE administration compared with baseline (p0.001). No significant difference was found in HR following BDE compared with baseline (p = 0.375). Those that received a BDE dose10 μg were noted to have a significantly greater rise in SBP than those that received 10 μg (30.0 mmHg vs. 11.0 mmHg; p = 0.022). Similarly, patients that received a dose ≥0.2 μg/kg had a significantly greater increase in SBP compared with those that received0.2 μg/kg (30.0 mmHg vs. 10.0 mmHg; p = 0.048). There were no incidences of severe hypertension following therapy.The utilization of IV BDE in the prehospital setting for acute hypotension resulted in a significant rise in SBP. A dose-response relationship was noted both in terms of a flat-based dose and a weight-based dose, with higher doses yielding a greater change in SBP. Additional investigations are necessary to further explore the most appropriate dose of this agent in this setting and its influence, if any, on clinical outcomes.

Chemotherapy-induced neuropathy, ranking among the most common toxic neuropathies, primarily affects the sensory nerve modalities. Taxanes and oxaliplatin commonly cause an acute pain problem, something that presents soon after each individual dose and then generally improves over a course of days. In addition, these drugs and several other neurotoxic chemotherapy drugs commonly cause a more gradually appearing and more chronic neuropathy that primarily involves distal extremities. There are a number of similarities regarding the peripheral neuropathy caused by many chemotherapy drugs, noting that there are some distinct differences in them, also. When neurotoxic chemotherapy is stopped, neuropathy problems often improve. However, neuropathy can become a prominent problem for years, in some patients, leading to marked disabilities.

Dosimetric monitoring is useful to limit exposures to ionising radiation in medical occupational settings, and reduce subsequent health risks. Scientific literatures, such as the UNSCEAR report 2017 and International Atomic Energy Agency Report 2014b, updated information on this subject; however, few African works have been found. This is the reason why we undertook this study, which summarises existing information on monitoring external radiation exposure doses for the whole body, using data from medical workers on this continent. Using standard terms and combining different keyword searches for radiation dose monitoring among radiology healthcare workers in Africa, from the titles, abstracts, and full texts, we found 3139 articles in the PubMed/MEDLINE, Google Scholar and INIS databases. Two reviewers screened the retrieved publications based on predefined eligibility criteria to identify relevant studies, extract key information from each, and summarise the data in table form. A total of 20 potentially relevant articles were identified. Among these 20 articles, 15 reported the overall average annual effective dose. Studies included in this systematic review represent an inventory of the radiation protection of medical workers in various African countries, with a focus on the monitoring of occupational radiation exposure. The size of studied populations ranged between 81 and 5152 occupational exposed workers. The mean annual effective doses ranged from 0.44 to 8.20 mSv in all specialities of medical sectors, while diagnostic radiology ranged from 0.07 to 4.37 mSv. For the nuclear medicine and radiotherapy from medical groups, the mean annual effective dose varied between 0.56 and 6.30 mSv. Industrial and research/teaching sectors data varied between 0.38 to 19.40 mSv. In conclusion, more studies implemented on dosimetric monitoring in Africa are needed to get a real picture of occupational exposure in the continent.

Medical cannabis has shown to be effective in various diseases that have not successfully been treated with other marketed drug products. However, the dose of cannabis is highly individual and additionally, medical cannabis is prone to misuse. To combat these challenges, the concept of data-enriched edible pharmaceuticals (DEEP) is introduced. Quick Response (QR) code patterns containing lipophilic cannabinoids, i.e., cannabidiol (CBD) and delta-9-tetrahydrocannabinol (THC), were printed using a desktop inkjet printer. This allows for simultaneously printing an individual dose and encapsulating information relevant to the end-users and other stakeholders in a single dosage unit, which is readable by a standard smartphone. Different doses of CBD and THC were incorporated in the DEEP by printing various (1–10) layers of the cannabinoid-containing ink on porous substrates, i.e., solid foams, prepared by solvent casting and subsequent freeze-drying. The printed DEEP were still readable after 8 weeks of storage in dry and cold conditions. This approach of ‘in-drug labeling’ instead of ‘drug package labeling’ provides a new possibility for developing a more efficient supply chain of pharmaceuticals and safer medication schemes by increasing the traceability of drug products at a single dosage unit level.

The eye lens exposure among 16 technicians in two nuclear medicine departments at university hospitals in Finland was investigated by measuring the operational quantity Hp(3) using EYE-D dosemeters. For all workers, the annual mean Hp(3) was estimated to be 1.1 mSv (max. 3.9 mSv). The relation between Hp(3) to routinely monitored personal dose equivalent Hp(10) was clearly correlated. Considering individual dose measurement periods (2–4 weeks), the Hp(3)/Hp(10) ratio was 0.7 (Pearson’s coefficient r = 0.90, p 0.1 mSv vs.

We present a flexible and general adaptive experimental design for dose finding clinical trials. This method can be applied in sterotypical settings such as determining a maximum tolerated dose, when the dose response relationship is complex, or when the response is an arbitrary quantitative measure. Our design generalizes dose finding methods such as the continual reassessment method (CRM), modified CRM, and estimation with overdose control (EWOC). Similar to those, our design requires a working mathematical model, which assures efficiency, low bias, and a higher fraction of dose selected near the optimum compared to purely operational designs. Unlike typical model based designs that always employ the same model, our method allows individual dose response models tailored to the circumstance. Simulations are also integral to our design allowing it to account for both known and unknown effects of dose on outcome. This method is applicable to general dose finding problems such as those encountered with modern targeted anti-cancer agents, immunotherapies, and titrations against biomarker outcome measures. The method can also support improvements in the design of the experiment being conducted by providing a platform for concurrent simulations to assess the influence of projected design points. Although we present the design in the context of clinical trials, it is equally applicable to experiments with non-human subjects.

Data on occupational radiation exposure of radiation workers at a tertiary hospital in China during 2013–18 were analyzed to provide decision-making advice for hospitals and health administrative departments. A total of 1255 exposure records of radiation workers were collected. The average annual effective doses of radiation workers during 2013–18 was 0.4977 mSv, with 1150 (91.63%) records ranging between 0 and 1 mSv, 91 (7.25%) between 1 and 2 mSv, 10 (0.80%) between 2 and 5 mSv and 4 (0.32%) records exceeding 5 mSv. There was a significant difference in the average annual effective dose of radiation workers among different occupational categories except in 2015 indicating that hospitals and administrative authorities should pay more attention to the radiation workers in the nuclear medicine and intervention department. The average annual effective doses did not show significant differences between male and female workers except in 2017; in that year the average individual dose of female workers was higher than male workers’. There were no significant differences in the average annual effective doses among doctors, nurses and radiologic technologists except in 2016 and 2017; during that period the individual dose of nurses was higher than doctors’ and radiologic technologists’.

The registry and analysis of occupational exposure is significant for radiation protection against ionising radiation. This paper presents the current status of the 'Chinese Registry of Radiation Workers (CRRW)' and trends as well as the distribution of occupational exposure to ionising radiation in China from 2009 to 2018. A database with total 6.6 million monitoring records from 820 000 workers in 85 000 radiation units for medical uses, industrial uses and miscellaneous uses is established by the CRRW. The Mann-Kendall test shows statistically significant decreasing trends of average annual effective dose for the total, medical uses and industrial uses (p < 0.01), by 0.035, 0.042 and 0.020 mSv/y, respectively. The average annual effective dose for the monitored workers is 0.403 mSv for the 10-y period. More than 96.1% of the monitored workers receive annual doses less than the limit for public exposure (1 mSv) in 2018. The annual average effective dose in medical uses is significantly higher than industrial uses and miscellaneous uses (p < 0.05/3 = 0.017). In 2018, the annual collective dose of 107.41 man·Sv is received by 378 428 monitored workers, with medical uses as the dominant contributor. These observations could be a result of improvements in radiation protection practices in China. However, it is still necessary to take rigorous and continuous surveillance and radiation protection measures, to keep individual dose as low as reasonably achievable, especially for those found to receive relatively higher doses in medical uses.

Humans are daily exposed to the natural radioactivity present in rocks, soils, and water. The distribution of these elements in the surface is not uniform, being influenced by the variation of the physical, geological, and meteorological parameters. The concentration activities of natural radionuclides 238U, 226Ra, 228Ra, and 222Rn were determined in the groundwater supplying the Salutaris Mineral Waters Park, in Paraiba do Sul, in the state of Rio de Janeiro. The concentrations of 238U varied from 0.95 to 2.70 μg L−1 with a mean concentration of 1.96 μg L−1, 226Ra ranged from 1.50 to 12.6 mBq L−1 with an average of 5.03 mBq L−1, 228Ra presented levels between 1.80 and 2.80 mBq L−1, with an average of 2.40 mBq L−1, and 222Rn, with levels of 5.90–1.94 × 104 mBq L−1 with an average concentration of 7.50 Bq L−1. The contribution of the consumption of these radionuclides dissolved in the water distributed in the Park to the effective annual dose ranged from 0.03 to 0.10 mSv year−1, with an average of 0.08 mSv year−1. The results showed that all effective annual dose values per ingestion of these mineral waters were below the individual dose limit of 0.10 mSv year−1 recommended by the World Health Organization (WHO).

In order to create conditions for increasing the effectiveness of treatment of patients with metastatic lung disease a new method for calculating the dose of antitumor drug for performing isolated chemo-perfusion of the lung with metasta-sectomy taking into account the anatomical features of patients and previous operations on the lung was developed. The study consisted of three stages. As a result of the first stage of the study the effectiveness of the software package was measured in the volume of lung patients based on the presence of a strong positive correlation between the volumes of left lungs (Rs = 0.91, p

The Monitoring Service at the Materialprufungsamt Nordrhein-Westfalen in Dortmund develops a new dosemeter system for large-scale individual dose monitoring. The dosemeters make use of thermoluminescence light from a thin layer of LiF:Mg,Ti. In the large-scale routine dosimetry service, a high number of dosemeters have to be evaluated on a monthly basis, which requires a fast readout. Therefore, thermoluminescence is stimulated by exponential heating of the dosemeters. The main quantity of interest to obtain from a dosemeter is the irradiation dose. Since the data comes in the form of thermoluminescence glow curves, their analysis offers the possibility to extract more information from the data than the irradiation dose, e.g. the fading time. In addition, such an analysis can reduce the uncertainties of the reconstructed irradiation dose, especially for low irradiation doses. Because it is not possible to measure the temperature of the dosemeter during the readout process, the recorded time-dependent glow curves have to be converted to temperature-dependent glow curves before the analysis.

Dental ceramics are radiation sensitive materials and exhibit luminescent properties. Their samples can be potentially used for individual dose assessment in situations where retrospective dosimetry is required. In this work, we investigated dosimetry properties of two leucite glass-based dental ceramics using Optically Stimulated Luminescence (OSL) and Thermoluminescence (TL). We concentrated on characteristics as reproducibility, fading, optical bleaching, minimum detectable dose (MDD), dose response and photon energy response of TL and OSL signals. Both the dental ceramics exhibited very good reproducibility (

We postulated that a contiguous rectal dose-volume threshold curve obtained via a best mathematical fit of the toughest literature recommended dose-volume thresholds could be deemed as “safe” related to the risk of rectal toxicity. The practicality of restricting rectal doses to such ideal volume thresholds in clinical practice was tested by comparing data collected from a pool of prostate patients treated with external beam radiation therapy (EBRT) in our institution. Available rectal dose-volume constraint recommendation in prostate EBRT was collected. At each dose level, the toughest recommended volume limit was identified and an ideal dose-volume threshold curve was generated using a best mathematical fit. Rectal dose-volume data on 105 prostate patients treated to 75.6 Gy dose with intensity modulated radiation therapy (IMRT) in our institution were retrospectively reviewed. The “ideal” rectal dose-volume threshold curve is defined by V 75 ≤ 7%, V 70 ≤ 11%, V 65 ≤ 15%, V 60 ≤ 20%, V 50 ≤ 30%, V 40 ≤ 43%, and V 30 ≤ 60%. At doses larger or equal to 65 Gy, our patient averaged dose-volume histograms (DVHs) for all groups converged with the ideal curve. At intermediate and low doses (less than 60 Gy), higher volumes of rectum were irradiated than described by the hypothetical curve, with pelvic group receiving more rectal dose than prostate only group respectively. Rectal mean dose correlated strongly with V 40 values (R 2 = 0.84). Our “ideal” rectal dose-volume curve generated from literature dose-volume thresholds in the most stringent manner is realistic and achievable at high doses (≥60 Gy) and not realistic at intermediate and low doses (≤50 Gy). Standardizing rectal definition and dose-volume metrics will make published analyses and dose-volume constraint recommendations easier to follow.

As an important index shaping the design of fusion safety system, evaluation of public radiation consequences have risen as a hot topic on the way to develop fusion energy. In this work, the comprehensive public early dose was evaluated due to unit gram tritium (HT/HTO), activated dust, activated corrosion products (ACPs) and activated gases accidental release from ITER like fusion reactor. Meanwhile, considering that we cannot completely eliminate the occurrence likelihood of multi-failure of vacuum vessel and tokamak building, we conservatively evaluated the public radiation consequences and environment restoration after the worst hypothetical accident preliminarily. The comparison results show early dose of different unit radioactivity release under different conditions. After further performing the radiation consequences, we find it possible that the hypothetical accident for ITER like fusion reactor would result in a level 6 accident according to INES, not appear level 7 like Chernobyl or Fukushima accidents. And from the point of environment restoration, we need at least 69 years for case 1 (1kg HTO and 1000kg dust release) and 34-52years for case 2 (1kg HTO and 10kg-100kg dust release) to wait the contaminated zone drop below the general public safety limit (1mSv per year) before it is suitable for human habitation.