• Title/Summary/Keyword: nuclear organizations

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Human resource planning for authorized inspection activity

  • Lee, Seung-hee;Field, Robert Murray
    • Nuclear Engineering and Technology
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    • v.51 no.2
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    • pp.618-625
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    • 2019
  • When newcomer countries consider a nuclear power programme, it is recognized that the most important organizations are the Nuclear Energy Programme Implementing Organization (NEPIO), the regulator, and an operating organization. Concerning the number of construction delays these days, one of the essential organizations is an Authorized Inspection Agency (AIA). According to World Nuclear Industry Status Report, all of the reactors under construction in eight out of the thirteen countries have experienced delays. Globally, the Flamanville 3 project and Sanmen Unit 1 are 6.5 years and 5 years late respectively. One of the major reasons of delay is due to inappropriate manufacturing and inspection on safety class components. The recommendations are made to develop such an organization: (i) find existing inspection organizations in relevant industries, (ii) contract with expatriates who have experience on nuclear inspection, (iii) develop a legislative framework to authorize the inspection organization with enforcement, (iv) include a contract clause in the BIS for developing the AIA, (v) hold training programmes from vendor country, (vi) during manufacturing and construction, domestic AIA shall be involved.

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.

Aging of Korean Nuclear Manpower and Implications of Manpower Policy: Statistical Analysis on Nuclear Organizations (한국 원자력 인력의 고령화와 인력정책의 함의: 원자력 관련기관 인력통계 분석)

  • Chung, Bum-Jin;Ko, Kyung-Min
    • Journal of Energy Engineering
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    • v.21 no.1
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    • pp.1-17
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    • 2012
  • In Korea, there are increasing concerns on nuclear manpower demand and supply due to construction of domestic nuclear power plants and exporting nuclear power plant. In addition, aging of nuclear manpower is another important concern for stable nuclear manpower demand and supply. A shortage of skilled high-quality human resources resulted in massive retirements of senior workers may seriously undermine Korean nuclear competitiveness. This paper analyzed current state of aging of nuclear manpower based on statistical analysis on Korean nuclear organizations. The data used in this paper is manpower statistics of domestic nuclear organizations surveyed in 2001 and 2010. This paper analyzed trends of manpower change for 10 years and based on these analyses, has reviewed the level of the aging nuclear manpower by surveyed organization and integrated. Finally, this paper suggested to direction of manpower recruitment to cope with aging nuclear manpower and alternatives to find a solution to problems of nuclear manpower demand and supply.

Pilot Experiment for Named Entity Recognition of Construction-related Organizations from Unstructured Text Data

  • Baek, Seungwon;Han, Seung H.;Jung, Wooyong;Kim, Yuri
    • International conference on construction engineering and project management
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    • 2022.06a
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    • pp.847-854
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    • 2022
  • The aim of this study is to develop a Named Entity Recognition (NER) model to automatically identify construction-related organizations from news articles. This study collected news articles using web crawling technique and construction-related organizations were labeled within a total of 1,000 news articles. The Bidirectional Encoder Representations from Transformers (BERT) model was used to recognize clients, constructors, consultants, engineers, and others. As a pilot experiment of this study, the best average F1 score of NER was 0.692. The result of this study is expected to contribute to the establishment of international business strategies by collecting timely information and analyzing it automatically.

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Development and strengthening of the nuclear and radiation safety infrastructure for nuclear power program of Bangladesh

  • Islam, Md. Shafiqul;Faisal, Shafiqul Islam;Khan, Sadia
    • Nuclear Engineering and Technology
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    • v.53 no.5
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    • pp.1705-1716
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    • 2021
  • Bangladesh, as a newcomer country, is expecting to start her nuclear power journey by 2022. Due to evident reasons, newcomer nuclear countries face several key challenges concerning the development of national nuclear safety infrastructure. The paper investigates the status of the 7 key safety infrastructure issues out of the 19 and readiness of the supportive organizations, laboratories, and workforces following the International Atomic energy Agency's status evaluation guide at milestone 3 and foreign countries' practice. Much progress has been achieved at phase 3 regarding the establishments of a few Acts, a regulator, and an operator. However, comprehensive regulatory frameworks, skilled workforces, establishments of a few supportive organizations, and laboratories for managing environmental radioactivity, radiological accidents, and radioactive wastes are yet to ready. Several suggestions are made for establishing and expediting radiation monitoring laboratories, a radiological emergency management center, a radioactive waste management company, and technical support organizations for the safety infrastructure. To avoid perceived risks, policymakers and competent authorities need to emphasize creating an optimized safety infrastructure before commissioning and operating the 1st nuclear power plant safely, securely, and cost-sustainably.

Development of a Quantitative Resilience Model for Severe Accident Response Organizations of Nuclear Power Plants: Application of AHP Method (원자력발전소 중대사고 대응 조직에 대한 레질리언스 정량적 모델 개발: AHP 방법 적용)

  • Park, Jooyoung;Kim, Ji-tae;Lee, Sungheon;Kim, Jonghyun
    • Journal of the Korean Society of Safety
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    • v.35 no.1
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    • pp.116-129
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    • 2020
  • Resilience is defined as the intrinsic ability of a system to adjust its functioning prior to, during, or following changes and disturbances, so that it can sustain required operations or functions with the related systems under both expected and unexpected conditions. Resilience engineering is a relatively new paradigm for safety management that focuses on how to cope with complexity under pressure or disturbance to achieve successful functioning. This study aims to develop a quantitative resilience model for severe accident response organizations of nuclear power plants using the Analytic Hierarchy Process (AHP) method. First, we investigated severe accident response organizations based on a radiation emergency plan in the Korean case and developed a qualitative resilience model for the organizations with resilience-influencing factors, which have been identified in the author's previous studies. Then, a quantitative model for entire severe accident response organizations was developed by using the Analytic Hierarchy Process (AHP) method with a tool for System Dynamics. For applying the AHP method, several experts who are working on implementing, regulating or researching the severe accident response participated in collecting their expertise on the relative importance between all the possible relations in the model. Finally, a sensitivity analysis was carried out to discuss which factors have the most influenceable on resilience.

EDUCATION AND TRAINING IN RADIATION PROTECTION IN KOREA: CURRENT STATUS AND IMPROVEMENTS

  • Son, Miyeon;Kim, Hyunkee;Nam, Youngmi;Nam, Jongsoo;Lee, Ki-Bog
    • Nuclear Engineering and Technology
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    • v.44 no.7
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    • pp.825-830
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    • 2012
  • Radiation and its various industrial applications have been growing at approximately 10 percent per year for the past decade in Korea. As a result, the importance of the Education and Training (E&T) in radiation protection is of upmost importance. This paper is intended to investigate the present status of the E&T on radiation protection and safety in Korea and to draw up the improvements of the E&T courses required for building the national radiation safety infrastructure. For these purposes, the E&T data from the six major domestic organizations providing radiation protection training courses were investigated and analyzed. Each of the organizations is offering several kinds of E&T courses based on their own specific functions. These organizations have administrative facilities equipped with the latest technology for E&T in radiation protection. The E&T courses mainly cover the training courses for radiation workers, radiological emergency staff, license applicants, license holders, and regulatory staff. In 2010, a total of 58 E&T courses were carried out across six organizations. The conclusions make a number of observations highlighting challenges such as: establishing a formal feedback mechanism, introducing more practical training sessions, developing training courses tailored to the job categories and target audiences, and designing education and training courses in radiation protection that comply with current obligations as well as future requirements.

Trends on U.S. Cyber Security Event Notifications and its Implications

  • Byun, Ye-Eun;Shin, Ick-Hyun;Kwon, Kook-Heui;Kim, Sang-Woo
    • Proceedings of the Korea Information Processing Society Conference
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    • 2015.04a
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    • pp.449-451
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    • 2015
  • When cyber attacks are discovered in nuclear facilities, licensees are required to notify regulatory organizations for quick action. This also helps regulatory organizations to strengthen regulatory capabilities for cyber security. Currently the U.S. issued the final draft rule for Cyber Security Event Notifications. Domestic regulatory activities being at an early stage for cyber security need to implement law for Cyber Security Event Notifications. Since the current laws are focused on the aspect of safety, they are in need of more specific laws for cyber security.

Modeling cryptographic algorithms validation and developing block ciphers with electronic code book for a control system at nuclear power plants

  • JunYoung Son;Taewoo Tak;Hahm Inhye
    • Nuclear Engineering and Technology
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    • v.55 no.1
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    • pp.25-36
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    • 2023
  • Nuclear power plants have recognized the importance of nuclear cybersecurity. Based on regulatory guidelines and security-related standards issued by regulatory agencies around the world including IAEA, NRC, and KINAC, nuclear operating organizations and related systems manufacturing organizations, design companies, and regulatory agencies are considering methods to prepare for nuclear cybersecurity. Cryptographic algorithms have to be developed and applied in order to meet nuclear cybersecurity requirements. This paper presents methodologies for validating cryptographic algorithms that should be continuously applied at the critical control system of I&C in NPPs. Through the proposed schemes, validation programs are developed in the PLC, which is a critical system of a NPP's I&C, and the validation program is verified through simulation results. Since the development of a cryptographic algorithm validation program for critical digital systems of NPPs has not been carried out, the methodologies proposed in this paper could provide guidelines for Cryptographic Module Validation Modeling for Control Systems in NPPs. In particular, among several CMVP, specific testing techniques for ECB mode-based block ciphers are introduced with program codes and validation models.