Meldonium is a metabolic drug whose inclusion in the 2016 List of Prohibited Substances and Methods followed the analysis of data collected under the 2015 World Anti‐Doping Agency Monitoring Program. In the early months of 2016, anti‐doping laboratories reported an unusually high number of cases in which urine samples contained high concentrations of meldonium. Consequently, the meldonium excretion period in healthy athletes and the substance's long‐term urine and blood (plasma) pharmacokinetics became central questions for the anti‐doping community to address, to ensure appropriate assessment of the scientific and medical situation, and also fair treatment of athletes from a result management and legal standpoint. At the present time, data on meldonium pharmacokinetics is limited to a few studies, with no known data available on long‐term excretion of high oral doses. The primary objective of this open‐label study was to determine long‐term urine and plasma pharmacokinetic parameters of meldonium in healthy volunteers. Study design included single and repeated functional load testing and assessment of L‐carnitine administration on meldonium excretion and pharmacokinetics. Thirty‐two volunteers were equally divided into two groups receiving either 1.0 g or 2.0 g of oral meldonium daily for 3 weeks. The study found meldonium takes several days to attain a steady state in blood and displays an elimination period over several months after cessation of treatment. Moreover, findings demonstrate that the daily dose, periodicity and duration of treatment with meldonium are the most important factors to consider in calculating the substance's elimination and complete body clearance.
Purpose: To obtain data of radiation survey in workplaces of the personnel of the Priargun Production Mountain Chemical Association (OJSC PPMCA), who work at the premises of the ground facilities. Material and methods: In the course of the radiation survey. Integral track methods were used to measure radon activity concentration by REI-1 track cameras of the TRACK-REI-1M kit. To assess the activity balance factor between radon and its radionuclide progenies, short term measurements of radon activity concentration (AC) and effective equilibrium concentration (EEC) of radon by handle radiometers of radon and its progenies. Gamma dose rate was measured by handle dosimeters. Results: Annual AC, EEC and effective dose due to radon and external gamma exposures in workplaces at the ground facilities of OJSC PPMCA have been obtained. Total number of the inspected workshops is 138, including 121 workshops occupied by the A group personnel, and 17 – by the B group personnel. Conclusions: It was shown that annual doses 20 mSv could be exceeded for the A group personnel who work at three workshops shaft 8K of the mine-2, one workshop of building 630A of the Hydro-metallurgical Plant and one workshop of shaft 5 B of G mine. In the workshops of the B group personnel, 5 mSv annual effective doses can be exceeded 2 and more times at the premises of canteen number 18 and administrative domestic building of mine-2.
Purpose: To share the experience in regulation of radiation safety and protection of workers involved in management of the spent nuclear fuel (SNF) and radioactive waste (RW), as well as radiation protection of the population and environment in the vicinity of sites for temporary storage at Andreeva Bay on the Kola Peninsula. Material and methods: Spent fuel from Russian nuclear powered submarines has been stored at shore based facilities for more than 20 years, notably at Andreeva Bay. The storage facilities were for some years poorly maintained and a significant fraction of the fuel that is still in store at the site wais damaged. Over the last years, hugemuch work has been done to improve the technical infrastructure and prepare for removal of the SNF from the temporary stores, management of existing RW. Results: This paper presents progress with projects of the FMBA of Russia and NRPA cooperation for regulation of radiation safety and protection. During the researches, the following issues were addressed: radiological threat assessment to identify the priority directions of regulation; detailed analysis of the radiation situation on sites, at the territories and nearby the sites; radiation control and monitoring of the environmental conditions; development of the computer maps and geo-information system; emergency preparedness and response; improvement of radiation safety culture; etc. Based on the received results of monitoring and assessment of the current risks, site-specific regulatory documents have been developed for the bodies and institutions under the FMBA of Russia involved in the activities to control the facility. Those documents include the requirements for: radiation protection of workers and population; personal dose monitoring; the RW management including the very low level RW; implementation of the environmental monitoring; radiation monitoring nearby the Andreeva Bay SevRAO facility; and remediation of the sites as remediation criteria and regulations. The next stage of work is to carry out the regulation of large-scale removal of SNF during 2017–2021 and its subsequent transfer to Mayak PA, and operations to bring the infrastructure of the site into the hsafe conditions, i.e., ecological remediation of the site – by 2025. Lessons learnt from this work are being used in support of improved international recommendations and guidance on how to address legacy issues. Conclusion: The experience accumulated during regulation of the remediation process of the former Naval Coastal Technical Bases, has helped to identify new relevant areas of improvement of the regulatory supervision at nuclear legacy sites. The study of potential hazard of radiation exposure to the personnel during technological operations of SNF and RW management is very important issue. In this light, the regulator in cooperation of the operator should develop some effective and efficient activities for dose monitoring. When dealing with the protection of the population and environment, a methodology of comprehensive radiation and chemical monitoring should be developed and models of radiation and chemical risks should be improved taking into account features of contamination of the site under remediation. An important link of the social focus of the regulator and the operator is to improve strategies of public communications near legacy sites under remediation.
The article analyzes the results of dental examination of employees with hazardous and normal working conditions in Atomenergomash enterprise with various dental care organization regimens and provides clear evidence of the effectiveness of serial attendances care in enterprise dental offices in terms of reduction in the dental treatment needs. Additional funding for departmental dental services was calculated by comparing the real cost of dental treatment and MHI tariffs allowing implementation of proposed dental care program.
In this article, the historical analysis of the application of ionizing radiation sources in medicine and industry from the early stages of the development of radiation technology to the present day is shown. A retrospective (1945-1960) assessment of the personnel radiation doses in the X-ray diagnostic department (the use of open and closed X-ray tubes) and of the personnel of flaw detection laboratories (using collet grips and non-standard flaw detectors) showed a significant exceeding of the permissible values existing at that period of time. For the time present the existing system for the protection of personnel in medical and industrial establishments is shown to meet modern requirements, and the exposure levels are well below the permissible values established by RSB (Radiation Safety Norms)-99/2009. In intervention methods of research problems of further improvement of the personnel safety system are shown to exist, first of all, the development of technical solutions for the protection of the lens is required.
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