Radiation Safety of Population: Experience and Ways of Improvement

2021 ◽  
Vol 66 (4) ◽  
pp. 25-32
Author(s):  
N. Shandala ◽  
Igor' Korenkov ◽  
A. Lyaginskaya ◽  
S. Kiselev ◽  
Yu Kvacheva ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Radiation Safety ◽  
Natural Radionuclides ◽  
Nuclear Facilities ◽  
Health Physics ◽  
Medical Problems ◽  
Chemical Safety ◽  
Environmental Media ◽  
The Public

The article describes the results of the activities of the department of radiation safety of the population of the A.I. Burnasyan FMBC of FMBA over the period from the foundation of the Center to the present. Results: The priority in the activity of the Institute of Biophysics, created in 1946, was the development of issues of radiation safety of the personnel and the public during the implementation of a nuclear project. The basic scientific direction «radiation safety of the population» was formed as an independent unit by 1955. Today, the department of radiation safety of the population of FMBC is a scientific, practical and methodological unit which deals with radiation and chemical safety including an assessment of health of the population living in the vicinity of Russian nuclear facilities. The main priorities of activity include: radiation-health physics monitoring and health physics regulation; monitoring the health of the population; expert activity in medical nuclear forensics. Scientific research in the field of protection and safety and improving the state health and epidemiological supervision covers the population living in the areas of enterprises under FMBA’s of Russia service, including nuclear shipbuilding facilities, nuclear and uranium legacy of Russia and Central Asia, nuclear power plants, cosmodromes, etc. Conclusion: In general, summarizing the 75-year activity in the field of the public radiation protection and safety, the following can be stated. Over the past years, a set of health physics works has been carried out at nuclear facilities, a methodology for radiation and health physics monitoring has been developed in conjunction with monitoring the public health, methods for determining man-made and natural radionuclides in food and environmental media have been developed and introduced into practice. The implementation of our new scientific developments and future prospects will be aimed at reducing the burden of medical problems associated with the operation of various radiation hazardous facilities and legacy management; raising the level and quality of life of the relevant contingents of the Russian population; as well as the creation of the necessary conditions for the successful development of nuclear energy in the Russian Federation.

scholarly journals Termination of the nuclear and radiation legacy of Russia: scientific basis for the radiation-hygienic regulation

2019 ◽  
Vol 12 (3) ◽  
pp. 114-119
Author(s):  
I. K. Romanovich
Keyword(s):  
Social Protection ◽  
Radiation Safety ◽  
Natural Radionuclides ◽  
Scientific Basis ◽  
Federal Law ◽  
Nuclear Facilities ◽  
The Public ◽  
The Past ◽  
The Social ◽  
Zone Of Influence

For the provision of the radiation safety of the public during the termination of the nuclear and radiation legacy within the boundaries of the Federal Targeted Program “Provision of the nuclear and radiation safety for 2016-2020 and up to 2030”, the following documents were developed: draft of the sanitary rules “Hygienic requirements for the remediation of the facilities and territories contaminated by man-made and natural radionuclides due to the past activities of the facilities of nuclear and non-nuclear branches of industry” and three methodical guidelines on the survey of the remediated territories, buildings and structures and assessment of the doses of the public residing in the zone of influence of the nuclear legacy facilities. The sanitary rules were based on the directions of the future use of the remediated territories, buildings and structures as well as on the radiation-hygienic safety criteria. It was assumed that dose criteria for the public considering the quota (0.3 mSv/year) is applied for remediated sites of the nuclear facilities (radiation facilities). The remediation of the radioactively contaminated areas with the residing public is based on the requirements of the Federal Law № 1244-1, 15.05.1991 “On the social protection of the citizens exposed due to the Chernobyl NPP accident”. Originally the drafts of documents were developed considering the approval in 2019 of the new Norms of the Radiation Safety – 2019, harmonized with the international recommendations and standards. Due to prolongation of the existing Norms of the Radiation Safety 99//2009 for the extra five years, the drafts of the regulations are adapted to the existing NRB 99/2009 and OSPORB 99/2010.

ANALYSIS OF THE RADIOLOGICAL SAFETY CONTROL LEVEL VERSUS THE EXPOSURE OF RADIATION WORKERS IN SOUTH KOREA FROM 2008–17

2018 ◽  
Vol 184 (1) ◽  
pp. 98-108
Author(s):  
Sang-Tae Kim ◽  
Jaeryong Yoo
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Radiation Safety ◽  
Safety Management ◽  
Control Level ◽  
Radioactive Isotopes ◽  
Safety Control ◽  
Level Versus ◽  
Radiation Workers

Abstract In this study, the radiation exposure of workers at workplaces registered and licensed between 2008 and 2017 for the production/sale/use of radioactive isotopes (RI) and radioactive generators (RG) was analysed to evaluate the quality of radiation safety management controls in use. The number of facilities using RIs increased by ~26% from 2008 to 2017 whereas the number of facilities using RGs increased by ~166% over the same period. There were 33 029 radiation workers in all fields in 2008, and the number increased by ~32% to 43 467 by 2017. However, the collective effective dose of radiation received by workers decreased in all industries except for those working in nuclear power plants. In other words, the quality of radiation safety management improved over that same time period due to the systematic, continuous introduction of safety mechanisms by the regulatory authority.

A dose constraint proposal for members of the public taking into account multi-unit nuclear power plants in Korea

2014 ◽  
Vol 52 (5) ◽  
pp. 739-747 ◽  
Author(s):  
Tae Young Kong ◽  
Hee Geun Kim ◽  
Jong Hyun Ko ◽  
Gamal Akabani ◽  
Goung Jin Lee
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
The Public ◽  
Dose Constraint

Cyber Security Assessment of NPP I&C Systems

2020 ◽  
pp. 221-238
Author(s):  
Oleksandr Klevtsov ◽  
Artem Symonov ◽  
Serhii Trubchaninov
Keyword(s):  
Control Systems ◽  
Cyber Security ◽  
Nuclear Power ◽  
Power Plants ◽  
Cyber Attacks ◽  
Security Assessment ◽  
Nuclear Facilities ◽  
Security Risks ◽  
Cyber Threats ◽  
And Control

The chapter is devoted to the issues of cyber security assessment of instrumentation and control systems (I&C systems) of nuclear power plants (NPP). The authors examined the main types of potential cyber threats at the stages of development and operation of NPP I&C systems. Examples of real incidents at various nuclear facilities caused by intentional cyber-attacks or unintentional computer errors during the maintenance of the software of NPP I&C systems are given. The approaches to vulnerabilities assessment of NPP I&C systems are described. The scope and content of the assessment and periodic reassessment of cyber security of NPP I&C systems are considered. An approach of assessment to cyber security risks is described.

INTERCOMPARISON ON INTERNAL DOSE ASSESSMENT FOR NUCLEAR POWER PLANTS IN KOREA

2019 ◽  
Vol 186 (4) ◽  
pp. 524-529
Author(s):  
Si Young Kim
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Dose Assessment ◽  
Assessment Procedure ◽  
Internal Dose ◽  
Nuclear Facilities ◽  
International Intercomparison ◽  
Selection Of

Abstract The intercomparison test is a quality assurance activity performed for internal dose assessment. In Korea, the intercomparison test on internal dose assessment was carried out for nuclear facilities in May 2018. The test involved four nuclear facilities in Korea, and seven exposure scenarios were applied. These scenarios cover the intake of 131I, a uranium mixture, 60Co and tritium under various conditions. This paper only reviews the participant results of three scenarios pertinent to the operation of nuclear power plants and adopts the statistical evaluation method, used in international intercomparison tests, to determine the significance values of the results. Although no outliers were established in the test, improvements in the internal dose assessment procedure were derived. These included the selection of intake time, selection of lung absorption type according to the chemical form and consideration of the contribution of previous intake.

scholarly journals Importance of Advanced Planning of Manufacturing for Nuclear Industry

2016 ◽  
Vol 7 (2) ◽  
pp. 42-49
Author(s):  
Nick Shykinov ◽  
Robert Rulko ◽  
Dariusz Mroz
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Regulatory Compliance ◽  
Pressure Vessels ◽  
Nuclear Industry ◽  
Project Schedule ◽  
Nuclear Facilities ◽  
Project Completion ◽  
Advanced Planning ◽  
And Performance

Abstract In the context of energy demands by growing economies, climate changes, fossil fuel pricing volatility, and improved safety and performance of nuclear power plants, many countries express interest in expanding or acquiring nuclear power capacity. In the light of the increased interest in expanding nuclear power the supply chain for nuclear power projects has received more attention in recent years. The importance of the advanced planning of procurement and manufacturing of components of nuclear facilities is critical for these projects. Many of these components are often referred to as long-lead items. They may be equipment, products and systems that are identified to have a delivery time long enough to affect directly the overall timing of a project. In order to avoid negatively affecting the project schedule, these items may need to be sourced out or manufactured years before the beginning of the project. For nuclear facilities, long-lead items include physical components such as large pressure vessels, instrumentation and controls. They may also mean programs and management systems important to the safety of the facility. Authorized nuclear operator training, site evaluation programs, and procurement are some of the examples. The nuclear power industry must often meet very demanding construction and commissioning timelines, and proper advanced planning of the long-lead items helps manage risks to project completion time. For nuclear components there are regulatory and licensing considerations that need to be considered. A national nuclear regulator must be involved early to ensure the components will meet the national legal regulatory requirements. This paper will discuss timing considerations to address the regulatory compliance of nuclear long-lead items.

Decontamination and Provenance Tracking

2003 ◽  
Author(s):  
David Bradbury ◽  
George R. Elder ◽  
John C. Ritchie ◽  
Robert G. Ward
Keyword(s):  
Electricity Generation ◽  
Nuclear Power ◽  
Nuclear Industry ◽  
Public Confidence ◽  
Nuclear Facilities ◽  
The Public ◽  
Nuclear Plants ◽  
Potential Benefits ◽  
Continued Use ◽  
Contamination Levels

Decommissioning of retired nuclear plants and facilities demands the proper management of the process, both for economic reasons and for retaining public confidence in the continued use of nuclear power for electricity generation. There are significant potential benefits, both economic and environmental, in recycling materials from retired nuclear facilities for new uses rather than disposing of them as radioactive waste. Although it is technically possible to decontaminate many retired nuclear components to reduce contamination levels to below those appropriate for free release into the public domain, there is some public unease at the prospect of formerly contaminated materials passing into unrestricted public use. Greater support for recycle can be achieved by converting decontaminated materials into products for new controlled uses, particularly within the nuclear industry. Irrespective of the future of nuclear power, the industry has a need for many new items such as waste containers, replacement components etc. Good economics can be achieved by decontaminating the materials and then using existing non-radioactive manufacturing facilities for fabrication of new components. Provided that materials have first been decontaminated to below unrestricted release levels, there is no objection in principle to using non-radioactive facilities for recycling and manufacturing activities, so long as the materials are properly tracked to prevent their uncontrolled release. Surface decontamination has an important role to play in these activities. Efficient and economic decontamination processes are needed to prepare materials for recycle. The EPRI DFDX Process is a process for achieving these objectives. Recent progress with this process is described.

The Regulatory Framework for Safe Decommissioning of Nuclear Power Plants in Korea

2013 ◽  
Author(s):  
Sangmyeon Ahn ◽  
Jungjoon Lee ◽  
Chanwoo Jeong ◽  
Kyungwoo Choi
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Regulatory Framework ◽  
International Standards ◽  
Current Status ◽  
Nuclear Facilities ◽  
Safety Requirement ◽  
Regulatory Review ◽  
Safety Standards

We are having 23 units of nuclear power plants in operation and 5 units of nuclear power plants under construction in Korea as of September 2012. However, we don’t have any experience on shutdown permanently and decommissioning of nuclear power plants. There are only two research reactors being decommissioned since 1997. It is realized that improvement of the regulatory framework for decommissioning of nuclear facilities has been emphasized constantly from the point of view of IAEA’s safety standards. It is also known that IAEA will prepare the safety requirement on decommissioning of facilities; its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA’s Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we focus on identifying the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA’s safety standards in order to achieve our goal. And then the plan is established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. It is expected that if the things will go forward as planned, the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards.

Study on a Methodology of Human Factor Engineering Operating Experience Review for Nuclear Power Plant

2010 ◽  
Author(s):  
Danying Gu ◽  
Shuhui Zhang ◽  
Zhonghe Ning
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Human Factor ◽  
Operating Experience ◽  
Sources Of Information ◽  
Nuclear Facilities ◽  
Human Factor Engineering ◽  
Design Procedures ◽  
Function Allocation ◽  
Review Criterion

The reviewing of operating experience at nuclear power plants (NPP) is not only critically important to safe and reliable operations, but also useful to guide the design of new plants which are similar to the current one under review. How to identify and analyze the safety-related operating experience and then implement a more extensive review is a vital and challengeable issue. In this paper, a methodology of human factor engineering (HFE) operating experience review (OER) is proposed for NPP. The need for the application of HFE in the life cycle activities of NPP and other nuclear facilities has been demonstrated by plant operating histories and regulatory and industry reviews. As a very important element of HFE, the OER is performed from the beginning of the design process. The main purpose of performing an OER is to verify that the applicant has identified and analyzed HFE-related safety problems and issues in previous designs that are similar to the current one. In this way, negative features associated with predecessor designs may be avoided in the current NPP design while retaining positive features. The research of OER concentrates on the aspect of review criterion, scope and implementation procedure of the HFE-related operating experience. As the NRC requirement, the scope of operating experience can be divided into six types in accordance with sources of information. The implementation procedures of USA and China are introduced, respectively. The resolution of HFE OER issues involve function allocation, changes in automation, HSI equipment design, procedures, training, and so forth. The OER conclusions can contribute to other HFE activities and improve the safety, reliability and usability of the HSI design in NPP.

Sign in / Sign up

Export Citation Format

Share Document