• Title/Summary/Keyword: Nuclear facilities

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A Study on the Problems and Improvement of the Safety Management Law of Nuclear Facilities -Focused on Safety Management of Aquatic Products- (원자력시설 안전관리 법제의 문제점과 개선방안 연구 -수산물의 안전관리를 중심으로-)

  • Lee, Woo-Do
    • The Journal of Fisheries Business Administration
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    • v.50 no.2
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    • pp.23-40
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    • 2019
  • The main purpose of this study is to analyze and examine the problems of the law systems of the safety and maintenance of nuclear facilities and to propose the improvements with respect to the related problems especialy focused on safety management of aquatic products. Therefore, the results of the paper would be helpful to build an effective management law system of safety and maintenance of nuclear facilities and fisheries products. The research methods are longitudinal and horizontal studies. This study compares domestic policies with foreign policies of nuclear plants and aquatic products. Using the above methods, examining the current system of nuclear-related laws and regulations, we have found that there exist 13 Acts including "Nuclear Safety Act", etc. Safety laws related on nuclear facilities have seven Acts including "Nuclear Safety Act", "the Act on Physical Protection and Radiological Emergency", "Radioactive waste control Act", "Act on Protective Action Guidelines against Radiation in the Natural Environment", "Special Act on Assistance to the locations of facilities for disposal low and intermediate level radioactive waste", "Korea Institute of Nuclear Safety Act". "Act on Establishment and Operation of the Nuclear Safety and Security Commission". The seven laws are composed of 119 legislations. They have 112 lower statute of eight Presidential Decrees, six Primeministrial Decrees and Ministrial Decrees, 92 administrative rules (orders), 6 legislations of local self-government aself-governing body. The concluded proposals of this paper are as follows. Firstly, we propose that the relationship between the special law and general law should be re-established. Secondly, the terms with respect to law system of safety and maintenance of nuclear plants should be redefined and specified. Thirdly, it is advisable to re-examine and re-establish the Law System for Safety and Maintenance of Nuclear Facilities. and environmental rights like the French Nuclear Safety Legislation. Lastly, inadequate legislation on the aquatic pollution damage should be re-established. It is necessary to ensure sufficient transparency as well as environmental considerations in the policy decisions of the Korean government and legislation of the National Assembly. It is necessary to further study the possibilities of accepting the implications of the French legal system as a legal system in Korea. In conclusion, the safety management of nuclear facilities is not only focused on the secondary industry and the tertiary industry centering on power generation and supply, but also on the primary industry, which is the food of the people. It is necessary to prevent damage to be foreseen. Therefore, it is judged that there should be no harm to the people caused by contaminated marine products even if the "Food Safety Law for Prevention of Radiation Pollution Damage" is enacted.

Geological Safety Evaluation and Monitoring of Nuclear Facility Sites in South Korea

  • Lee, Hyunwoo;Woo, Hyeon Dong;Chun, Hyun Ju;Im, Chang-Bock
    • The Journal of Engineering Geology
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    • v.24 no.4
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    • pp.609-613
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    • 2014
  • The Korean Peninsula, located at the southeastern tip of the Eurasian Plate, is known to be tectonically stable, and no critical evidence has yet been found that would override the safety design of nuclear facilities in South Korea. Because a nuclear power plant, like other major social overhead capital facilities, could cause great damage to both the environment and society through an unexpected tectonic event, even one of extremely low probability, like the Fukushima accident, a defense-in-depth safety approach is required in geological and geotechnical site safety evaluation for nuclear projects. This paper introduces the regulatory procedures that are in place to confirm nuclear site safety and site monitoring (e.g., earthquakes and groundwater) systems applied to nuclear facilities in order to reduce inherent uncertainties within the site safety review of geological and seismological issues related with a NPP project.

Calculation of the fission products for neutron-induced fission of 235U

  • Changqi Liu;Kai Tao;Liming Huang;Dejun E;Xiaohou Bai;Zhanwen Ma
    • Nuclear Engineering and Technology
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    • v.56 no.5
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    • pp.1895-1901
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    • 2024
  • The fission model, G4ParaFissionModel, was enhanced in this study, mainly focusing on refining the energy dependence of the peak-to-valley ratio in the mass distribution and the energy dependence of the average total kinetic energy (TKE). The enhanced model was employed to investigate the characteristics of fission products from 235U(n, f) reaction. The calculated results, including fission yield, TKE distribution, prompt fission neutron and gamma spectra, were compared with both evaluated and experimental data. The comparison shows that these physical observables related nuclear data, which are of importance for developments of the nuclear power and physics, can be reasonably well reproduced.

A Study on the Improvement of Cybersecurity Training System in Nuclear Facilities (원자력 시설 사이버보안 훈련체계 개선 방안 연구)

  • Kim, Hyun-hee;Lee, Daesung
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2022.05a
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    • pp.187-188
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    • 2022
  • As information processing technology develops with the trend of the times, the possibility of cyber threats to nuclear facilities is increasing. In the 2000s, there was a growing perception that cyberattacks on nuclear facilities were needed, and in fact, a cybersecurity regulatory system for nuclear power plants began to be established to prepare for cyberattacks. In Korea, in order to prepare for cyber threats, in 2013 and 2014, the Act on Protection and Radiation Disaster Prevention, Enforcement Decree, and Enforcement Rules of Nuclear Facilities, etc., and notices related to the Radioactive Disaster Prevention Act were revised. In 2015, domestic nuclear operators prepared information system security regulations for each facility in accordance with the revised laws and received approval from the Nuclear Safety Commission for implementation of information system security regulations divided into seven stages. In 2019, a special inspection for step-by-step implementation was completed, and since 2019, the cybersecurity system of operators has been continuously inspected through regular inspections. In this paper, we present some measures to build improved training to suit the steadily revised inspection of the nuclear facility cybersecurity system to counter cyber threats to the ever-evolving nuclear facilities.

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Development of Real-Time Active Type Seals (실시간 능동형 타입 격납장치 개발)

  • Jung-ki Shin;Heekyun Baek;Yongju Lee
    • Journal of Radiation Industry
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    • v.18 no.1
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    • pp.9-14
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    • 2024
  • In order to thoroughly verify the denuclearization of the Korean Peninsula, it is urgent to develop technology capabilities to monitor, detect, collect, analyze, interpret, and evaluate nuclear activities using nuclear materials and secure nuclear transparency. The IAEA is actively using seal technology to maximize the efficiency of safety measures, and currently uses metal cap, paper, COBRA, and EOSS as seal devices. Unlike facilities that comply with safety measures requirements, such as domestic nuclear facilities, facilities subject to denuclearization are likely to have various risk environments that make it difficult to apply safety measures, and there is a high possibility that continuity of knowledge (COK) such as damage, malfunction, and power loss will not be maintained. This study aims to develop a real-time active seal device that can be applied in such special situations to enable immediate response in the event of a similar situation. To this end, the main functions of the real-time seal device were derived and applied, and a commercialized seal device and operation software. The real-time seal technology developed through this study can be applied to all nuclear facilities in South Korea, especially used as storage equipment for dry cask storage facilities of heavy water reactor's after fuel, and it is believed that unnecessary radiation exposure by inspectors can be minimized.

The Improvement of China's Nuclear Safety Supervision Technical Support Ability

  • Han Wu;Guoxin Yu;Xiangyang Zheng;Keyan Teng
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.4
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    • pp.523-531
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    • 2022
  • The International Atomic Energy Agency (IAEA) entails independent decision-making for the safety supervision of civil nuclear facilities. To evaluate and review the safety of nuclear facilities, the national regulatory body usually consults independent institutions or external committees. Technical Support Organizations (TSOs) include national laboratories, research institutions, and consulting organizations. Support from professional organizations in other countries may also be required occasionally. Most of the world's major nuclear power countries adopt an independent nuclear safety supervision model. Accordingly, China has continuously improved upon the construction of such a system by establishing the National Nuclear Safety Administration (NNSA) as the decision-making department for nuclear and radiation safety supervision, six regional safety supervision stations, the Nuclear and Radiation Safety Center (NSC), a nuclear safety expert committee, and the National Nuclear and Radiation Safety Supervision Technology R&D Base, which serves as the test, verification, and R&D platform for providing consultation and technical support. An R&D system, however, remains to be formed. Future endeavors must focus on improving the technical support capacity of these systems. As an enhancement from institutional independence to capability independence is necessary for ensuring the independence of China's nuclear safety regulatory institution, its regulatory capacity must be improved in the future.

Study on the Decommissioning of Small Nuclear Facility through Analyzing Foreign Decommissioning Practices (국외 해체 사례 분석을 통한 국내 소규모 방사선이용시설 해체에 관한 연구)

  • Kwon, Dayeong;Kim, Yongmin
    • Journal of the Korean Society of Radiology
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    • v.9 no.3
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    • pp.125-130
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    • 2015
  • RI & RG are used in various field such as medical field, industrial field, agricultural and food&life field. The number of small nuclear facilities is on the increase. We need to take an interest in decommissioning of small nuclear facility and predict the occurring problem from facility decommissioning. Because of the relatively low radiation risk, the preparation of the small nuclear facility dismantling is often neglected. As the accident in Goiania, Brazil showed, the impact of the decommissioning of small nuclear facilities is not less than the large nuclear facilities although it may seem dangerless. Therefore, we analyzed the each institutional characteristics of the decommissioning of small nuclear facilities through foreign case study on this research. Also, we proposed several considerations on decommissioning such as reuse of facility and source, lack of space, stakeholder involvement and failures of protection. Through these study, we tried to make guideline of the small nuclear facilities decommissioning.

An Approach to Framework of Dealing with Improving the Complexity and Uncertainty for Decommissioning Safety Assessment of a Nuclear Facility

  • Jeong, Kwan-Seong;Lee, Kune-Woo;Lim, Hyeon-Kyo
    • International Journal of Safety
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    • v.8 no.1
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    • pp.24-31
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    • 2009
  • An effective assessment for decommissioning safety of nuclear facilities requires basic knowledge about possible risks, characteristics of potential hazards, and comprehensive understanding of the associated cause-effect relationships within a decommissioning for nuclear facility. This paper proposes an approach to develop the hierarchical structure and hazards of dealing with improving the complexity and uncertainty for decommissioning safety assessment of nuclear facilities and the resolutions are proposed to improve the complexity and uncertainty for decommissioning safety assessment of nuclear facilities. These resolutions can provide a comprehensive view of the risks in the decommissioning activities of a nuclear facility.

A study on security oversight framework for Korean Nuclear Facility regulations

  • So Eun Shin;Heung Gyu Park;Ha Neul Na;Young Suk Bang;Yong Suk Lee
    • Nuclear Engineering and Technology
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    • v.56 no.2
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    • pp.426-436
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    • 2024
  • Nuclear security has been emphasized to ensure the safety of the environment and humans, as well as to protect nuclear materials and facilities from malicious attacks. With increasing utilization of nuclear energy and emerging potential threats, there has been a renewed focus on nuclear security. Korea has made efforts to enhance the regulatory oversight processes, both for general and specific legislative systems. While Korea has demonstrated effective nuclear security activities, continuous efforts are necessary to maintain a high level of security and to improve regulatory efficiency in alignment with international standards. In this study, the comprehensive regulatory oversight framework for the security of Korean nuclear facilities has been investigated. For reference, the U.S. regulatory oversight frameworks for nuclear facilities, with a focus on nuclear security, and the motivations of changes in regulatory oversight framework have been identified. By comparing these regulatory programs and frameworks, insights and considerations for enhancing nuclear security regulations have been identified. A comprehensive security inspection program tailored for the Korean regulatory oversight framework has been proposed, and has been preliminarily applied to hypothetical conditions for further discussion.

Development of the framework for quantitative cyber risk assessment in nuclear facilities

  • Kwang-Seop Son;Jae-Gu Song;Jung-Woon Lee
    • Nuclear Engineering and Technology
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    • v.55 no.6
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    • pp.2034-2046
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    • 2023
  • Industrial control systems in nuclear facilities are facing increasing cyber threats due to the widespread use of information and communication equipment. To implement cyber security programs effectively through the RG 5.71, it is necessary to quantitatively assess cyber risks. However, this can be challenging due to limited historical data on threats and customized Critical Digital Assets (CDAs) in nuclear facilities. Previous works have focused on identifying data flows, the assets where the data is stored and processed, which means that the methods are heavily biased towards information security concerns. Additionally, in nuclear facilities, cyber threats need to be analyzed from a safety perspective. In this study, we use the system theoretic process analysis to identify system-level threat scenarios that could violate safety constraints. Instead of quantifying the likelihood of exploiting vulnerabilities, we quantify Security Control Measures (SCMs) against the identified threat scenarios. We classify the system and CDAs into four consequence-based classes, as presented in NEI 13-10, to analyze the adversary impact on CDAs. This allows for the ranking of identified threat scenarios according to the quantified SCMs. The proposed framework enables stakeholders to more effectively and accurately rank cyber risks, as well as establish security and response strategies.