scholarly journals Risk of Death from Hypertension among Chernobyl Accident Liquidators – Nuclear Industry Workers

2021 ◽  
pp. 47-51
Author(s):  
A.R. Tukov ◽  
◽  
I.L. Shafranskiy ◽  
O.N. Prokhorova ◽  
M.V. Kalinina ◽  
...  
Keyword(s):  
Chernobyl Accident ◽  
Nuclear Power ◽  
Radiation Risk ◽  
Data File ◽  
Nuclear Industry ◽  
Risk Of Death ◽  
Relative Risks ◽  
Safety Regulations ◽  
Relative Risk Of Death ◽  
Using Data

The aim of the study was to assess the radiation risk of death from hypertension in liquidators of the Chernobyl nuclear power plant accident consequences — workers of the nuclear industry — using doses from various types of irradiation. Materials and methods of the study. The study was conducted using data from the Industry Register of Persons exposed to radiation as a result of the Chernobyl accident — workers of the nuclear power industry. Information on 12659 liquidators (all male) was included in the analysis. 1327 of them got occupational radiation doses. Crude relative risks of death from hypertension were estimated for five dose groups using internal controls. Based on the stratified data file, a Poisson regression procedure was performed using the AMFIT module of Epicure program and the excess relative risk of death from hypertension was calculated and the nature of the dose-dependent excess relative mortality was investigated. Results of the study and their analysis. Direct estimates of radiogenic risk of death from hypertension were obtained. No increase in mortality from hypertensive disease per unit dose was found for both the doses received during the liquidation of the Chernobyl accident consequences and for the total doses. The results of the study can be used in the development of radiation safety regulations for persons working with sources of ionizing radiation.

Estimation of Radiation Risk of the Initiation of Malignant Novelties in the Liquidators of the Consequences of the Accident at the Chernobyl Nuclear Power Plant, Workers of the Nuclear Industry, with the Account of Doses of Various Types of Irradiation

2019 ◽  
pp. 54-57
Author(s):  
А. Туков ◽  
A. Tukov ◽  
И. Шафранский ◽  
I. Shafransky ◽  
А. Цовьянов ◽  
...  
Keyword(s):  
Radiation Dose ◽  
Chernobyl Accident ◽  
Nuclear Power ◽  
Radiation Risk ◽  
Malignant Neoplasm ◽  
Personal Data ◽  
Nuclear Industry ◽  
Risk Indicators ◽  
Reliable Assessment ◽  
Total Radiation Dose

Purpose: Estimate of the excess relative risk of malignant neoplasm disease (MND) in nuclear industry workers, participants in the elimination of the consequences of the Chernobyl accident, taking into account the doses of various types of irradiation. Material and methods: An epidemiological experiment was conducted in which the personal data of the information base of the Industry Register of persons exposed to radiation as a result of the Chernobyl accident, the doses of occupational exposure, and tabular data on the dose of natural exposure, presented in the reports on the radiation situation in populated areas ESKID, No. 4-DOZ) were used. Results: It is shown that the risk assessment of the disease in the Chernobyl accident liquidators, obtained with the use of doses of different types of exposure, has different risk indicators (ERR at 1 Sv: the Chernobyl NPP radiation dose is 0.13, the ChNPP + professional dose is 1.13 and the ChNPP dose + professional + natural – 0.56). Conclusions: – Using any part of the total radiation dose of a person to calculate the risk of dose-induced diseases, we will get incorrect results is unknown how far from the truth. – For a reliable assessment of the risk of the disease, an overall dose is required from a person from all types of radiation, which is required by the radiation safety directives.

Architecting “Maintenance Program” for Piping and Pipe Support

2013 ◽  
Author(s):  
Koichi Tsumori ◽  
Yoshizumi Fukuhara ◽  
Hiroyuki Terunuma ◽  
Koji Yamamoto ◽  
Satoshi Momiyama
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Industry ◽  
Maintenance Management ◽  
3D Cad ◽  
Cad System ◽  
Nuclear Disaster ◽  
Safety Regulations ◽  
Maintenance Program

A new inspection standard that enhanced quality of operating /maintenance management of the nuclear power plant was introduced in 2009. After the Fukushima Daiichi nuclear disaster (Mar. 11th 2011), the situation surrounding the nuclear industry has dramatically changed, and the requirement for maintenance management of nuclear power plants is pushed for more stringent nuclear safety regulations. The new inspection standard requires enhancing equipment maintenance. It is necessary to enhance maintenance of not only equipment but also piping and pipe support. In this paper, we built the methodology for enhancing maintenance plan by rationalizing and visualizing of piping and pipe support based on the “Maintenance Program” in cooperating with 3D-CAD system.

Chernobyl coverage: how the US media treated the nuclear industry

1992 ◽  
Vol 1 (3) ◽  
pp. 305-323 ◽  
Author(s):  
Sharon M. Friedman ◽  
Carole M. Gorney ◽  
Brenda P. Egolf
Keyword(s):  
Chernobyl Accident ◽  
Nuclear Power ◽  
Western Europe ◽  
Nuclear Industry ◽  
Current Status ◽  
Background Information ◽  
The Us ◽  
The Usa ◽  
History Of ◽  
Level Of Understanding

This study attempted to uncover whether enough background information about nuclear power and the nuclear industries in the USA, USSR and Eastern and Western Europe had been included during the first two weeks of US coverage of the Chernobyl accident so that Americans would not be misled in their understanding of and attitudes toward nuclear power in general. It also sought to determine if reporters took advantage of the Chernobyl accident to attack nuclear technology or the nuclear industry in general. Coverage was analysed in five US newspapers and on the evening newscasts of the three major US television networks. Despite heavy coverage of the accident, no more than 25% of the coverage was devoted to information on safety records, history of accidents and current status of nuclear industries. Not enough information was provided to help the public's level of understanding of nuclear power or to put the Chernobyl accident in context. However, articles and newscasts generally balanced use of pro- and anti-nuclear statements, and did not include excessive amounts of fear-inducing and negative information.

scholarly journals Radiation Safety in Radioactive Waste Management: Radiation Doses and Prospects for Regulatory Framework Development

2020 ◽  
Vol 11 (2) ◽  
pp. 6-16
Author(s):  
I. I. Linge ◽  
Keyword(s):  
Nuclear Power ◽  
Radiation Safety ◽  
Nuclear Industry ◽  
Safety Regulations ◽  
Long Run ◽  
Radiation Sources ◽  
Exposure Levels ◽  
Public Exposure ◽  
Evaluation Of Data ◽  
Framework Development

Based on the evaluation of data on public exposure from various sources, the paper demonstrates that the contribution of nuclear power and nuclear industry into individual and total collective doses in Russia is minor compared to the exposure from natural radiation sources and medical treatment even in regions with sites run by Rosatom. The personnel are exposed to a level being considered common for the nuclear industry. Public exposure associated with the management of RW is practically absent with the same exposure levels being forecasted in the long run. Based on the above and considering the objectives for the USS RW development, the paper presents relevant proposals on further elaboration of basic radiation safety regulations: NRB, OSPORB and SPORO.

scholarly journals Risk of death from circulatory diseases in a cohort of patients exposed to chronic radiation

2017 ◽  
Vol 89 (1) ◽  
pp. 18-27 ◽  
Author(s):  
T V Azizova ◽  
E S Grigoryeva ◽  
N Hunter ◽  
M V Pikulina ◽  
M B Moseeva
Keyword(s):  
Nuclear Power ◽  
Atomic Bomb ◽  
Statistical Significance ◽  
Radiation Risk ◽  
Gamma Dose ◽  
Internal Exposure ◽  
Risk Of Death ◽  
Chronic Radiation ◽  
Smoking Index ◽  
Circulatory Diseases

Aim. To assess mortality from circulatory diseases (CD) in a cohort of workers exposed occupationally to chronic radiation in relation to external and internal exposure, by taking into account known non-radiation risk factors (RFs), such as smoking (including smoking index), alcohol consumption, hypertension, and body mass index. Subjects and methods. Mortality from CD (ICD-10: I00 — I99) was studied in a cohort of 22,377 nuclear power plant («Mayak» Production Association) workers exposed occupationally to chronic radiation. The study was based on the individual dose estimates of external and internal exposure taken from the new Mayak workers dosimetry system 2008 (MWDS-2008). The quantitative characteristics of smoking (smoking index) were used for the first time to assess the risk for CD in the cohort of workers exposed to chronic radiation. Results. There was a statistically significant linear relationship between CD mortality and external gamma-dose after adjusting for the non-radiation RFs; the excess relative risk per unit dose (ERR/Gy) was 0.05 (95% confidence interval (CI): 0 to 0.11). Introducing an additional adjustment for internal alpha-dose resulted in a twofold increase in ERR/Gy (0.10 (95% CI: 0.02 to 0.21). There was a statistically significant increasing trend in CD mortality with the elevated absorbed dose from internal alpha-radiation in the liver (ERR/Gy=0.27; 95% CI: 0.12 to 0.48). However, ERR/Gy decreased and lost its statistical significance after adjusting for external gamma-dose. Conclusion. The results of this study are in good agreement with risk estimates obtained in the Japanese cohort of atomic bomb survivors and in the cohorts of occupationally exposed workers.

A Model for Predicting Human Error in the Nuclear Industry

1982 ◽  
Vol 26 (10) ◽  
pp. 850-852 ◽  
Author(s):  
Neville Moray
Keyword(s):  
Nuclear Power ◽  
Human Error ◽  
Error Rates ◽  
Nuclear Industry ◽  
Summary Statistics ◽  
Plant Personnel ◽  
Using Data ◽  
Error Probabilities ◽  
Direct Measures

Usually the Theory of Signal Detection is used to estimate summary statistics, d' and β from measured false alarm and hit rates. Here we estimate d' and β directly and thus can estimate p(F) and p(M). This is possible even for very rare errors where it is difficult or impossible to obtain direct measures of error probabilities. An example of the model is provided using data collected from nuclear power plant personnel. The predicted error rates depend on the quality of the displays, and from the examples given the error rates appear quite close to those predicted by Swain and Guttman (1980).

Calibration Algorithms for Estimating the Number of Radiogenic Deaths in a Cohort

2021 ◽  
Vol 65 (6) ◽  
pp. 47-56
Author(s):  
E Vasilyev ◽  
E Annenkova ◽  
A. Biryukov ◽  
Yu. Orlov ◽  
S Dumansky ◽  
...  
Keyword(s):  
Chernobyl Accident ◽  
Risk Model ◽  
Radiation Risk ◽  
Total Mortality ◽  
Calculation Algorithm ◽  
Risk Models ◽  
Risk Of Death ◽  
Calculation Algorithms ◽  
Radiation Induced ◽  
Low Sensitivity

Background: Development of algorithms for estimating the number of radiogenic deaths in a cohort that happened or may happen before an arbitrary moment in time. Algorithms should be based on continuous lifelong risk models and minimize the errors of estimates based on deformable non-radiation models ("seed" models) reflecting the general patterns of Russian mortality, but with the possibility of calibrating according to selected data. Materials and methods: For the study, the databases of the register of liquidators of the consequences of the Chernobyl accident – employees of the enterprises of the Ministry of Atomic Energy of Russia were used. Persons with a non-zero dose of ionizing radiation received as a result of the accident and who were registered in the register until 2018 were selected from the register. There are 7324 men and 655 women in this sample. The number of deaths from the beginning of the observation period until 1996, 2006, 2016 from all causes, as well as from solid cancers and leukemias, was used as a reference data for the calibration. Radiation risk was calculated using UNSCEAR 2006 models. Calibration was performed using the Levenberg – Marquardt method. Results: A general formula was obtained for assessing the excess lifetime risk of death, which is the basis of the developed algorithms. The "seed" models of the risk of death from all causes and from solid cancers and leukemia’s were obtained. In accordance with the purpose of the work, two algorithms have been developed. The first algorithm is intended for direct (without using radiation risk models) estimation of the number of radiation-induced deaths in a cohort. The second uses radiation risk models. The performance of the algorithms was tested using the industry register of liquidators of the consequences of the Chernobyl accident. In particular, a 30 % calculated increase in the estimated number of deaths from radiation-induced solid cancers was recorded using calibrated models. Conclusions: The proposed calculation algorithms for calibrated models provide reliable (if the radiation risk models are considered sufficiently adequate) estimates of the number of Chernobyl deaths for points in time preceding the current one and, presumably, more accurate predictive estimates compared to the calculation algorithm for uncalibrated models. The low sensitivity of the lifelong risk model to variations in the parameters of the background models and the total mortality model makes it possible to apply models calibrated according to the liquidator register to other closely related populations (NPP workers, etc.).

DEVELOPMENT OF THE MONITORING (CONTROL) PROGRAM OF THE SAFETY OF NUCLEAR POWER PLANTS

2020 ◽  
Vol 2020 (2) ◽  
pp. 50-56
Author(s):  
Mariya Berberova ◽  
Vladislav Chuenko ◽  
Oleg Zolotarev ◽  
Olga Trefilova ◽  
Maksim Grudev ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Radiation Risk ◽  
Safety Data ◽  
Control Program ◽  
Data Sheet ◽  
Risk Assessments ◽  
Safety Data Sheet ◽  
Increased Risk

Nuclear power plants (NPP), being complex technological systems, represent a source of increased risk, in particular, a specific risk of radiation exposure. Obtaining quantitative assessments of radiation risk is critical for risk reduction and accident prevention. Existing methods for assessing radiation risk do not take into account the influence of external factors, such as population composition, geographical features, anthropogenic environmental changes, etc.[1]. Since 1997, in connection with changes in the norms and rules in the field of the use of atomic energy, it became necessary to perform a probabilistic safety analysis (PSA) at all nuclear power plants in Russia. Subsequently, a standard safety data sheet for a hazardous facility was developed. To fill out the second section of the safety data sheet, it is necessary to carry out a risk assessment of the objects in question. From this moment on, risk assessments were performed for all power units of all operating nuclear power plants in Russia. Today, in our country there are 14 nuclear power plants. On average, there are 3 power units per nuclear power plant. In order to systematize and centralize data on NPP risk assessments, it became necessary to develop a program for monitoring NPP safety. The aim of the work is to develop a monitoring (control) program for ensuring the safety of nuclear power plants, using modern technologies to systematize and group data on nuclear safety data sheets, as well as organize quick access to information.

Nuclear icebreaker fleet and power supply on the basis of floating power units

2018 ◽  
Vol 35 (4) ◽  
pp. 110-113
Author(s):  
V. A. Tupchienko ◽  
H. G. Imanova
Keyword(s):  
Foreign Policy ◽  
Power Supply ◽  
Nuclear Power ◽  
Arctic Region ◽  
Nuclear Industry ◽  
The Arctic ◽  
Far North ◽  
The Arctic Region

The article deals with the problem of the development of the domestic nuclear icebreaker fleet in the context of the implementation of nuclear logistics in the Arctic. The paper analyzes the key achievements of the Russian nuclear industry, highlights the key areas of development of the nuclear sector in the Far North, and identifies aspects of the development of mechanisms to ensure access to energy on the basis of floating nuclear power units. It is found that Russia is currently a leader in the implementation of the nuclear aspect of foreign policy and in providing energy to the Arctic region.

scholarly journals An Approach to Analyze Diagnosis Errors in Advanced Main Control Room Operations Using the Cause-Based Decision Tree Method

Energies ◽  
2021 ◽  
Vol 14 (13) ◽  
pp. 3832
Author(s):  
Awwal Mohammed Arigi ◽  
Gayoung Park ◽  
Jonghyun Kim
Keyword(s):  
Decision Tree ◽  
Nuclear Power ◽  
Power Plants ◽  
Human Error ◽  
Cognitive Activity ◽  
Emergency Operation ◽  
Nuclear Industry ◽  
Working Environment ◽  
Control Rooms ◽  
Diagnosis Errors

Advancements in the nuclear industry have led to the development of fully digitized main control rooms (MCRs)—often termed advanced MCRs—for newly built nuclear power plants (NPPs). Diagnosis is a major part of the cognitive activity in NPP MCRs. Advanced MCRs are expected to improve the working environment and reduce human error, especially during the diagnosis of unexpected scenarios. However, with the introduction of new types of tasks and errors by digital MCRs, a new method to analyze the diagnosis errors in these new types of MCRs is required. Task analysis for operator diagnosis in an advanced MCR based on emergency operation was performed to determine the error modes. The cause-based decision tree (CBDT) method—originally developed for analog control rooms—was then revised to a modified CBDT (MCBDT) based on the error mode categorizations. This work examines the possible adoption of the MCBDT method for the evaluation of diagnosis errors in advanced MCRs. We have also provided examples of the application of the proposed method to some common human failure events in emergency operations. The results show that with some modifications of the CBDT method, the human reliability in advanced MCRs can be reasonably estimated.

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