scholarly journals Potential radiological risk for the population during implementation of the Rosatom Proryv project. Part 2. Radiation detriment assessment

2020 ◽  
Vol 29 (4) ◽  
pp. 48-68
Author(s):  
V.K. Ivanov ◽  
◽  
S.Yu. Chekin ◽  
A.N. Menyajlo ◽  
S.S. Lovachev ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Radiation Safety ◽  
Fuel Cycle ◽  
Radiation Risk ◽  
Population Based ◽  
Normal Operation ◽  
Radiation Doses ◽  
Radiation Risks ◽  
Proryv Project ◽  
Current Health Care System

Nuclear power is effective and safe source of electricity. Meanwhile, uranium reserves in the earth's crust will run out in 100 years with the development of traditional nuclear reactors. The Rosatom “Proryv” project implementation will allow multiplying fuel sources for the new genera-tion nuclear power through the closing fuel cycle. Radiation safety of the new nuclear powers should be based on the state of the art Russian national and international regulations, as well as on predicted radiation doses, estimates of potential radiation risks and radiation detriment of the public. Developed methods for computational analysis of possible doses of estimates of radia-tion risks and population-based detriment, associated with atmospheric fallouts of radioactive substances from the BREST-OD-300 reactor, corresponds to the currently recognized approach-es to evaluating safety of nuclear energy facilities. Developed method for radiation detriment es-timating is in accordance with ICRP recommendations. It allows making assessment of radiation-associated health effects for Russian population with account of patients’ quality of life provided by the current health care system. The analysis of possible radiation doses and potential radia-tion risks shows that the upper 95% confidence bound of radiation detriment for the critical group of population in the town of Seversk (girls of 5 years of age) even in the event of beyond design basis accident at the reactor equals 1.1610-5 year-1, and does not exceed the radiation risk limit of 510-5 years-1, established by Russian national radiation safety regulations NRB-99/2009 for the population during normal operation of ionizing radiation sources. In the event of an accidental situation on the Brest-OD-300 reactor, the average estimates of radiation risks for the population living within the 30-km zone around the JSC “Siberian Chemical Combine” will generally remain in the range of negligible risk and will not exceed the level of 10-6 year-1.

scholarly journals Achievability of radiological equivalence associated with closed nuclear fuel cycle with fast reactors: impact of uncertainty factors in scenarios of Russian nuclear power development through to 2100. Part 1. Fast and thermal reactors

2021 ◽  
Vol 30 (2) ◽  
pp. 62-76
Author(s):  
V.K. Ivanov ◽  
◽  
A.V. Lopatkin ◽  
A.N. Menyajlo ◽  
E.V. Spirin ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy Development ◽  
Radioactive Wastes ◽  
Fast Reactors ◽  
Power Development ◽  
The Public ◽  
Radiation Risks ◽  
Nuclear Power Development

The Russian Government approved the Energy Strategy of the Russian Federation (Government Decree No.1523-r of June 9, 2020). The Strategy envisages the use of both thermal (TR) and fast (FR) reactors. The Strategy points out that the problems of nuclear power are associated with po-tential high expenses for irradiated fuel and radioactive wastes management. The previously de-signed model of the Russian nuclear energy development suggested that fast reactors only would operate at NPPs after 2010. Radiological equivalence, expressed as the equivalence of lifetime radiation risks to the public from radioactive wastes and from primary uranium ore, was shown to be achieved after 100-year storage. The burnup of 241Am, 237Np и 242Сm in closed nu-clear fuel cycle with fast reactors is a key part in the achievability of radiation risks equivalence. Scenarios of the Russian nuclear energy development through to 2100 with account of uncertain-ty factors in the measurement of contribution of fast and thermal reactors to the electric energy production are considered in the paper. The following three scenarios were developed: uncer-tainty is replaced by FRs; uncertainty is replaced by TRs; 50 per cent of FRs and 50 per cent of TRs replace uncertainty. If the energy is produced by fast reactors only (scenario 1) radiological equivalence was found to be achieved in 412 years. In two other scenarios radiological equiva-lence will be achieved after more than 1000 years. Contribution of main dose-forming radionu-clides and relevant ratios of potential biological hazards is included in models regardless of whether uncertainty in nuclear energy development is taking or not taking into account. Results of the study of conditions for radiological equivalence achievement should be used for amending Strategic plan of Russian nuclear power development through to 2100 that meets requirements of radiation ecology and radiation protection of the public.

scholarly journals Development of the automated system for assessing radiation risks to the population of the Russian Federation based on the data of radiation-hygienic certification of territories

2021 ◽  
Vol 14 (4) ◽  
pp. 114-121
Author(s):  
R. R. Akhmatdinov ◽  
A. M. Biblin ◽  
L. V. Repin
Keyword(s):  
Russian Federation ◽  
Radiation Safety ◽  
Negative Impact ◽  
Radiation Risk ◽  
Quantitative Characteristic ◽  
Computer Programs ◽  
Automated System ◽  
Risk Indicators ◽  
Radiation Risks ◽  
The Russian Federation

The assessment of the radiation risk based on the data of the radiation-hygienic passports of the territories makes it possible to give a brief quantitative characteristic of the negative impact of sources of ionizing radiation on the health of the population of various regions of the Russian Federation at the population level. The calculation of individual indicators of radiation risk for the population of particular region of the Russian Federation is a time-consuming task that requires referring to radiation-hygienic passports of territories for particular years. Therefore, the purpose of the performed work was to develop specialized software designed to assess the indicators of radiation risk to the population of the Russian Federation according to the data of the radiation-hygienic certification system of territories. Automation of the calculation of radiation risk allows not only to simplify the calculation procedure but also to carry out a spatial-temporal analysis of risk in dynamics for different regions of the Russian Federation over long periods. The methodological basis for the software development is guideline MR 2.6.1.0145-19 “Calculation of radiation risk according to the data contained in the radiation-hygienic passports of the territories to provide a comprehensive comparative assessment of the radiation safety status of the population of the subjects of the Russian Federation”. To achieve the set goal, two computer programs were developed: 1) to automate the process of calculating radiation risk based on the information contained in the radiation-hygienic passports of territories, a computer program “Calculation of radiation risk indicators according to RGPT data”; 2) for the spatial visualization of the calculations, a specialized geographic information system “Radiation risks of the population of the Russian Federation according to radiation-hygienic certification data”. The computer programs developed in the course of the work allow an automated calculation of radiation risk based on the data of radiation-hygienic passports of territories, visualize the spatially distributed results of calculating radiation risk, carry out a preliminary assessment of the state of radiation safety, based on the data contained in radiation-hygienic passports of territories using radiation risk indicators. 

scholarly journals Prospective lifetime radiation risk of cancer among Russian cleanup workers in Chernobyl

2021 ◽  
Vol 30 (1) ◽  
pp. 94-109
Author(s):  
S.Yu. Chekin ◽  
◽  
A.N. Menyajlo ◽  
V.V. Kashcheev ◽  
S.S. Lovachev ◽  
...  
Keyword(s):  
Chernobyl Accident ◽  
Radiation Safety ◽  
Risk Model ◽  
Radiation Risk ◽  
Epidemiological Data ◽  
Risk Models ◽  
Radiation Risks ◽  
Risk Of Cancer ◽  
Cleanup Workers

As stated in the Basic sanitary rules of radiation safety, radiation risk is one of the main character-istics of radiation safety. Before the work persons involved in cleanup operations after radiation accidents should be informed about subsequent risks to their health. However, mathematical models for radiation risk prediction and methods for its calculation are currently at the stage of scientific research and have not yet been standardized for solving practical problems of risk pre-diction. At the international level, UNSCEAR, ICRP and WHO developed radiation risk models on the basis of radiation-epidemiological data on survivors of Hiroshima and Nagasaki atomic bombings in August 1945. In recent decades, data on radiation-epidemiological follow-up of co-horts contained people exposed to radiation after the Chernobyl accident in 1986, in particular NRER data, have been used to identify and assess radiation risks. The radiation risk models iden-tified from the Chernobyl cohorts of exposed individuals differ from the models identified from the Japanese cohort, which leads, respectively, to different projections of lifetime radiation risk. The purpose of this work is to compare quantitatively the possible lifetime radiation risks of can-cer for a cohort of Russian liquidators of the Chernobyl accident, evaluated with radiation risk models developed by UNSCEAR, WHO and NRER. It is shown that after 2020, 1297 cases of cancer are expected in the cohort of Russian liquidators, this figure is 2.4 times higher than esti-mates obtained with the international models. The radiation risk model of leukemia, built on the basis of NRER follow-up data, predicts 145 cases of leukemia in the observed cohort of liquida-tors, which is 8 times higher than the values estimated with the use of international models. Since the liquidators of the considered cohort are generally over 50 years old, the results obtained may indicate the need to adjust the dose limits established by the current radiation safety standards based on ICRP risk models for people over 50 years old.

scholarly journals Application of a Specifi c Indicator for the Estimation of Radioactive Wastes Generation Volumes During Normal Operation of Nuclear Power Plants in Russia

2020 ◽  
Vol 11 (2) ◽  
pp. 66-74
Author(s):  
A. A. Ekidin ◽  
◽  
K. L. Antonov ◽  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Radiation Safety ◽  
Radioactive Wastes ◽  
Intermediate Level ◽  
Normal Operation ◽  
Low Level ◽  
Retrospective Assessment ◽  
High Level

Generation of radioactive wastes (RW) is viewed a most urgent problem of radiation safety under normal operation of nuclear power plants (NPP). The paper demonstrates the application of a specifi c indicator (rate) of RW generation per unit of generated power (m3/GW·h) for a retrospective assessment and forecasting of RW generation volumes at Russian NPPs. Mean and median values of annual specifi c RW generation rates were calculated for each NPP based on published environmental reports of JSC Rosenergoatom Concern for the period of 2008—2018. Advantage of applying median values in retrospective and forecast assessments was shown. Medians for solid very low-level, low-level, intermediate-level and high-level radioactive waste amounted to 1.5·10−2 m3/GW·h, 3.3·10−2 m3/GW·h, 3.3·10−3 m3/GW·h and 2.8·10−4 m3/GW·h, respectively; for liquid low-level and intermediate-level waste these values accounted for 1.4·10−3 m3/GW·h, 2.5·10−3 m3/GW·h, respectively. NPPs with RBMK reactor units are characterized by the highest mean and median values of specifi c RW generation rates for all RW categories. Given various types of reactor facilities and their characteristic specifi c rates, retrospective estimates for the total volume of liquid RW was increased by 8 % and for solid RW — by 12 %. The forecast estimates based on specifi c rate medians, as well as on increased power generation planned for Russian NPPs indicates probable increase in RW generation volumes by 0.8—7.1 % (depending on waste category) from 2020 to 2027.

scholarly journals Radiological protection of the public during the normal operating of the Pilot-demonstration energy complex (PDEC) and in increased total power of reactor plants in the Industrial power complex (IPC) within the framework of the Proryv Project

2021 ◽  
Vol 30 (4) ◽  
pp. 5-23
Author(s):  
V.K. Ivanov ◽  
◽  
E.V. Spirin ◽  
S.S. Lovachev ◽  
A.N. Menyajlo ◽  
...  
Keyword(s):  
Radiation Risk ◽  
Normal Operation ◽  
Total Power ◽  
Radiological Protection ◽  
Radiation Doses ◽  
Cancer Statistics ◽  
The Public ◽  
Energy Complex ◽  
Processing Module ◽  
Power Complex

The paper presents results of research on radiological protection of the public during normal op-eration of Pilot-demonstration energy complex (PDEC) and in increased total power of reactor plants in the Industrial power complex (IPC) based on the current national radiation safety stand-ards (NRB-99/2009), UNSCEAR conclusions and ICRP recommendations. To evaluate radiologi-cal protection of the public the concepts of radiological detriment (RD) and the level of radiation protection (LRP) were used. The concepts were also used to examine the compliance of the BREST-OD-300, fabrication/refabrication module, processing module, BR-1200 and BN-1200 re-actors, collectively called nuclear objects, with safety standards. RD and LRP were estimated with the use of data of the Russian national cancer statistics and cancer statistics of the regions, wherein nuclear objects are planned to be placed – Tomsk, Sverdlovsk, Chelyabinsk. For the public residing nearby the nuclear objects the estimated LRP and RD meet NRB-99/2009 re-quirements concerning the restriction of radiation risk at the level of 10Е-5 from potential irradiation during a year. For the public of the critical group (girls younger than 5 years of age), residing nearby the PDEC and the nuclear objects the negligible risk of 10Е-6 can be achievable if annual radiation doses of 3H, for BREST-OD-300, reduce by 80%, and of annual doses of Cs-137, for the processing module reduce by 75%. The negligible risk for the public can be achieved if annual radiation doses of H-3 for BREST-OD-300 reduce by 10% and annual radiation doses of Cs-137 for processing module reduce by 5%. Projected radiation risk value for the public residing nearby BN-1200 and BR-1200 or nearby the IPC with two BR-1200 facilities will be much lower than the level of the negligible risk of 10Е-6. The RD calculated with ICRP methodology, serves as confirmation of the need to improve efficiency in cancer care in Tomsk region in order the regional RD to be at the national level. Because the high level of radiological protection of the public during the normal operation of the fabrication/refabrication module, its further operation when establishing IPC based on BR-1200 is feasible.

scholarly journals Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System

2013 ◽  
Vol 2013 ◽  
pp. 1-8 ◽  
Author(s):  
A. Simonis ◽  
P. Poskas ◽  
A. Sirvydas ◽  
D. Grigaliuniene
Keyword(s):  
Nuclear Power ◽  
Radiation Safety ◽  
Cooling System ◽  
Computer Code ◽  
Radiation Doses ◽  
Planning Tool ◽  
Direct Radiation ◽  
Radioactive Aerosols ◽  
Effective Doses ◽  
Core Cooling

Decommissioning of the Ignalina Nuclear Power Plant involves multiple problems. One of them is personnel radiation safety during the performance of dismantling activities. In this paper, modeling results of radiation doses during the dismantling of the pressurized tank from the emergency core cooling system (ECCS PT) of RBMK-1500 reactor are presented. The radiological surveys indicate that the inner surface of the ECCS PT is contaminated with radioactive products of corrosion and sediments due to the radioactive water. The effective doses to the workers have been modeled for different strategies of ECCS PT dismantling. In order to select the optimal personnel radiation safety, the modeling has been performed by the means of computer code “VISIPLAN 3D ALARA Planning tool” developed by SCK CEN (Belgium). The impacts of dismantling tools, shielding types, and extract ventilation flow rate on effective doses during the dismantling of ECCS PT have been analyzed. The total effective personnel doses have been obtained by summarizing the effective personnel doses from various sources of exposure, that is, direct radiation from radioactive equipment, internal radiation due to inhalation of radioactive aerosols, and direct radiation from radioactive aerosols arising during hot cutting in premises. The uncertainty of the collective doses is also presented in this paper.

Prediction of Radiation Doses During the Dismantling of the Pressurized Tank From Emergency Core Cooling System of RBMK-1500 Reactor

2013 ◽  
Author(s):  
A. Simonis ◽  
P. Poskas ◽  
G. Poskas
Keyword(s):  
Nuclear Power ◽  
Radiation Safety ◽  
Cooling System ◽  
Computer Code ◽  
Radiation Doses ◽  
Direct Radiation ◽  
Radioactive Aerosols ◽  
Effective Doses ◽  
Core Cooling ◽  
The Impact

Preparation for the decommissioning of the Ignalina Nuclear Power Plant involves multiple problems. Personnel radiation safety during the performance of dismantling activities is one of them. In order to assess the optimal personnel radiation safety, the modelling is performed for large components by the means of computer code “VISIPLAN 3D ALARA Planning tool” developed by SCK CEN (Belgium). Modelling results of radiation doses during the dismantling of the pressurized tank from the emergency core cooling system (ECCS PT) of RBMK-1500 reactor are presented in this paper. The mass of one ECCS PT is approximately 47.6 tons. The radiological surveys indicate that the inner surface of the ECCS PT is contaminated with radioactive products of corrosion and sediments due to the radioactive water. The assessment of workers exposure was performed to comply with ALARA. The effective doses to the workers were modeled for different strategies of ECCS PT dismantling. The impact of dismantling tools and shielding types and extract ventilation flow rate during the dismantling of ECCS PT on effective doses were analyzed. The total effective personnel doses were obtained by summarizing the effective personnel doses from various sources of exposure, i. e., direct radiation from radioactive equipment, internal radiation due to inhalation of radioactive aerosols, and direct radiation from radioactive aerosols arising during hot cutting in premises.

Radiopharmacology: Hazard or/and Benefit

1984 ◽  
Vol 23 (02) ◽  
pp. 87-91 ◽  
Author(s):  
K. Flemming
Keyword(s):  
Ionizing Radiation ◽  
Late Effects ◽  
Radiation Risk ◽  
Dose Effect ◽  
Radiation Hazard ◽  
Radiation Doses ◽  
Low Doses ◽  
Medical Radiology ◽  
Experimental Findings ◽  
In The Beginning

SummaryIn the beginning of medical radiology, only the benefit of ionizing radiation was obvious, and radiation was handled and applied generously. After late effects had become known, the radiation exposure was reduced to doses following which no such effects were found. Thus, it was assumed that one could obtain an optimal medical benefit without inducing any hazard. Later, due to experimental findings, hypotheses arose (linear dose-effect response, no time factor) which led to the opinion that even low and lowest radiation doses were relevant for the induction of late effects. A radiation fear grew, which was unintentionally strengthened by radiation protection decrees: even for low doses a radiation risk could be calculated. Therefore, it was believed that there could still exist a radiation hazard, and the radiation benefit remained in question. If, however, all presently known facts are considered, one must conclude that large radiation doses are hazardous and low doses are inefficient, whereas lowest doses have a biopositive effect. Ionizing radiation, therefore, may cause both, hazard as well as benefit. Which of the two effects prevails is determined by the level of dose.

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