• 제목/요약/키워드: Plant Protection Systems

검색결과 129건 처리시간 0.024초

Systems Engineering Approach to develop the FPGA based Cyber Security Equipment for Nuclear Power Plant

  • Kim, Jun Sung;Jung, Jae Cheon
    • 시스템엔지니어링학술지
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    • 제14권2호
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    • pp.73-82
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    • 2018
  • In this work, a hardware based cryptographic module for the cyber security of nuclear power plant is developed using a system engineering approach. Nuclear power plants are isolated from the Internet, but as shown in the case of Iran, Man-in-the-middle attacks (MITM) could be a threat to the safety of the nuclear facilities. This FPGA-based module does not have an operating system and it provides protection as a firewall and mitigates the cyber threats. The encryption equipment consists of an encryption module, a decryption module, and interfaces for communication between modules and systems. The Advanced Encryption Standard (AES)-128, which is formally approved as top level by U.S. National Security Agency for cryptographic algorithms, is adopted. The development of the cyber security module is implemented in two main phases: reverse engineering and re-engineering. In the reverse engineering phase, the cyber security plan and system requirements are analyzed, and the AES algorithm is decomposed into functional units. In the re-engineering phase, we model the logical architecture using Vitech CORE9 software and simulate it with the Enhanced Functional Flow Block Diagram (EFFBD), which confirms the performance improvements of the hardware-based cryptographic module as compared to software based cryptography. Following this, the Hardware description language (HDL) code is developed and tested to verify the integrity of the code. Then, the developed code is implemented on the FPGA and connected to the personal computer through Recommended Standard (RS)-232 communication to perform validation of the developed component. For the future work, the developed FPGA based encryption equipment will be verified and validated in its expected operating environment by connecting it to the Advanced power reactor (APR)-1400 simulator.

수력 발전기 제어시스템의 계자상실 모델링과 시뮬레이션 (Modeling and Simulation of Loss of Excitation of Hydro Generator Control System)

  • 박철원
    • 전기학회논문지P
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    • 제63권2호
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    • pp.74-80
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    • 2014
  • Generator protection device has to detects an internal fault conditions in generator and abnormal operating conditions must be due to the hazards. Loss of excitation may cause generator itself failure as well as serious operating problem in power system, and then requires an appropriate response of generator protection device. Details modeling of generator control system and analysis of transient states in generator are important for optimal operation in power plants. In addition, the fault simulation data are also used for testing the characteristics of IED. In this paper, the hydro generator control system using PSCAD/EMTDC, visual simulation for power systems, was modeled. The generator control system which is composed of generator, turbine, exciter, governor was implemented. The parameters of generator control system model were obtained from field power plant. Loss of excitation simulations were performed while varying the fixed load. Several signals analysis were also performed so as to analyze transients phenomena.

고효율 전기 방식용 정류기를 이용한 유류탱크의 원 방식 제어 시스템 개발 (The Development of Remote Corrosion Monitoring and Control System for Oil Tank by using the High Efficiency CP Rectifier)

  • 배정효;하태현;이현구;김대경
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2002년도 추계학술대회 논문집 전기기기 및 에너지변환시스템부문
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    • pp.249-252
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    • 2002
  • Recently, the advanced countries are using the corrosion monitoring system in a chemical plant and an oil tank in order to protect the corrosion because it leads to a big accident, pollution of soil. and lose of money Generally. the owners of the facilities adopt CP(Cathodic Protection) systems to protect the corrosion also. However, a CP system for oil tank was not considered in Korea Moreover they didn't adopted a corrosion monitoring system. In this paper, we have been developed not only the remote automatic corrosion monitoring but also the remote corrosion control system using the high efficiency CP rectifier. This results should be used to operate the CP system effectively and economically. And also it will be possible to extend the expectation life of the Oil tanks.

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Analysis of the Likelihood of Internal Radiation Exposure When Decommissioning a Nuclear Power Plant in Korea

  • Jiung Kim;Tae Young Kong;Seongjun Kim;Jinho Son;Changju Song;Jaeok Park;Seungho Jo;Hee Geun Kim
    • 방사선산업학회지
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    • 제18권2호
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    • pp.141-145
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    • 2024
  • In Publication No. 66 of the International Commission on Radiological Protection, an activity median aerodynamic diameter (AMAD) of 5 ㎛ is considered in internal exposure dose assessment owing to inhalation of radionuclides in a workplace. However, analysis of aerosols generated during dismantling experiments, such as in the oxy-cutting of a reactor vessel conducted in Korea, revealed that the radioactive aerosols have AMAD ranging from 0.024 to 0.064 ㎛. Such extremely fine aerosols can induce internal exposure if inhaled. In particular, alpha radionuclides in aerosols can lead to significantly higher levels of radiation exposure than beta and gamma radionuclides, thus highlighting the need to establish appropriate internal exposure radiation protection programs and monitoring systems that specifically address alpha radionuclides when decommissioning nuclear power plants in Korea.

Development of Simplified DNBR Calculation Algorithm using Model-Based Systems Engineering Methodology

  • Awad, Ibrahim Fathy;Jung, Jae Cheon
    • 시스템엔지니어링학술지
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    • 제14권2호
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    • pp.24-32
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    • 2018
  • System Complexity one of the most common cause failure of the projects, it leads to a lack of understanding about the functions of the system. Hence, the model is developed for communication and furthermore modeling help analysis, design, and understanding of the system. On the other hand, the text-based specification is useful and easy to develop but is difficult to visualize the physical composition, structure, and behaviour or data exchange of the system. Therefore, it is necessary to transform system description into a diagram which clearly depicts the behaviour of the system as well as the interaction between components. According to the International Atomic Energy Agency (IAEA) Safety Glossary, The safety system is a system important to safety, provided to ensure the safe shutdown of the reactor or the residual heat removal from the reactor core, or to limit the consequences of anticipated operational occurrences and design basis accidents. Core Protection Calculator System (CPCS) in Advanced Power Reactor 1400 (APR 1400) Nuclear Power Plant is a safety critical system. CPCS was developed using systems engineering method focusing on Departure from Nuclear Boiling Ratio (DNBR) calculation. Due to the complexity of the system, many diagrams are needed to minimize the risk of ambiguities and lack of understanding. Using Model-Based Systems Engineering (MBSE) software for modeling the DNBR algorithm were used. These diagrams then serve as the baseline of the reverse engineering process and speeding up the development process. In addition, the use of MBSE ensures that any additional information obtained from auxiliary sources can then be input into the system model, ensuring data consistency.

발전기 가속에너지를 이용한 고장파급방지장치 운전조건 완화용 전기저장장치 적정용량 산정방안 (Required Capacity Assessment of Energy Storage System for Relieving Operation Condition of SPS Using Generator Acceleration Energy)

  • 송승헌;최우영;권한나;국경수
    • 전기학회논문지
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    • 제68권1호
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    • pp.1-7
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    • 2019
  • Due to the highly concentrated power plants integrated through the limited transmission lines in Korea, a Special Protection System(SPS) has been applied to stabilize the power systems by instantly tripping the pre-determined generators in a large-scaled power plant when a fault occurs on the drawing transmission lines. Moreover, power outputs of those generators are constrained to avoid any activation of Under Frequency Load Shedding(UFLS) even after those generators are tripped by SPS action. For this, this paper proposes a method for calculating the required capacity of Energy Storage System(ESS) expected to relieve the operating constraints to generators using its fast response for controlling power system frequency. The proposed method uses the generator acceleration energy to derive the stable condition during the SPS action. In addition, its effectiveness is verified by the case studies adopting actual SPS operations in Korean power systems.

A new perspective towards the development of robust data-driven intrusion detection for industrial control systems

  • Ayodeji, Abiodun;Liu, Yong-kuo;Chao, Nan;Yang, Li-qun
    • Nuclear Engineering and Technology
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    • 제52권12호
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    • pp.2687-2698
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    • 2020
  • Most of the machine learning-based intrusion detection tools developed for Industrial Control Systems (ICS) are trained on network packet captures, and they rely on monitoring network layer traffic alone for intrusion detection. This approach produces weak intrusion detection systems, as ICS cyber-attacks have a real and significant impact on the process variables. A limited number of researchers consider integrating process measurements. However, in complex systems, process variable changes could result from different combinations of abnormal occurrences. This paper examines recent advances in intrusion detection algorithms, their limitations, challenges and the status of their application in critical infrastructures. We also introduce the discussion on the similarities and conflicts observed in the development of machine learning tools and techniques for fault diagnosis and cybersecurity in the protection of complex systems and the need to establish a clear difference between them. As a case study, we discuss special characteristics in nuclear power control systems and the factors that constraint the direct integration of security algorithms. Moreover, we discuss data reliability issues and present references and direct URL to recent open-source data repositories to aid researchers in developing data-driven ICS intrusion detection systems.

A Two-Strain Mixture of Rhizobacteria Elicits Induction of Systemic Resistance Against Pseudomonas syringae and Cucumber Mosaic Virus Coupled to Promotion of Plant Growth on Arabidopsis thaliana

  • Ryu Choong-Min;Murphy John F.;Reddy M.S.;Kloepper Joseph W.
    • Journal of Microbiology and Biotechnology
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    • 제17권2호
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    • pp.280-286
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    • 2007
  • We evaluated a commercial biopreparation of plant growth-promoting rhizobacteria (PGPR) strains Bacillus subtilis GB03 and B. amyloliquefaciens IN937a formulated with the carrier chitosan (Bio Yield) for its capacity to elicit growth promotion and induced systemic resistance against infection by Cucumber Mosaic Virus (CMV) and Pseudomonas syringae pv. tomato DC3000 in Arabidopsis thaliana. The biopreparation promoted plant growth of Arabidopsis hormonal mutants, which included auxin, gibberellic acid, ethylene, jasmonate, salicylic acid, and brassinosteroid insensitive lines as well as each wild-type. The biopreparation protected plants against CMV based on disease severity in wild-type plants. However, virus titre was not lower in control plants and those treated with biopreparation, suggesting that the biopreparation induced tolerance rather than resistance against CMV. Interestingly, the biopreparation induced resistance against CMV in NahG plants, as evidenced by both reduced disease severity and virus titer. The biopreparation also elicited induced resistance against P. syringae pv. tomato in the wild-type but not in NahG transgenic plants, which degrade endogenous salicylic acid, indicating the involvement of salicylic acid signaling. Our results indicate that some PGPR strains can elicit plant growth promotion by mechanisms that are different from known hormonal signaling pathways. In addition, the mechanism for elicitation of induced resistance by PGPR may be pathogen-dependent. Collectively, the two-Bacilli strain mixture can be utilized as a biological inoculant for both protection of plant against bacterial and viral pathogens and enhancement of plant growth.

원자력발전소 화재방호 규제 개선 방향에 관한 연구 (A Study on Proposals for Improving the Fire Protection Regulations for Nuclear Power Plants)

  • 마진수;권경옥
    • 한국화재소방학회논문지
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    • 제24권4호
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    • pp.116-122
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    • 2010
  • 원자력발전소는 심층화재방어 개념에 따라 화재 발생시 발전소 외부로 방사능의 누출을 억제하고, 발전소의 안전정지 기능이 유지될 수 있도록 설계, 건설, 운영되어야 한다. 해외의 원전건설 국가는 이러한 원자력발전소의 안전정지 기능의 목적을 달성하기 위하여 원자력발전소에 대한 통합된 화재방호 규제요건을 가지고 있으나, 우리나라의 경우, 원자력발전소의 화재방호계통을 적용하기 위한 강제 요건으로서 소방관계법과 원자력법을 동시에 적용하는 비합리적인 규제지침을 가지고 있다. 화재방호설비에 관하여 원자력발전소 운영에 오랜 경험을 가진 미국, 캐나다 및 일본의 기술적으로 단일화된 원자력발전소의 화재방호 규제체계를 제시하였고, 우리나라도 화재방호설비는 원자력법에 의한 화재하중에 따른 화재위험도분석 결과를 설계에 반영하여 소방관계법에서는 예외조항으로 인정받을 수 있어야 함을 제안하였다.

Effects of Top-Dressed N on Rice Growth in a No-Till Direct-Sown Rice-Vetch Cropping Systems

  • Cho, Young-Son;Choe, Zhin-Ryong
    • 한국유기농업학회지
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    • 제7권2호
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    • pp.189-195
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    • 1999
  • Under the no-till direct-sown rice-vetch cropping systems, where whole chopped rice straw were returned to the paddy surface at combine harvest and whole-plant of Chinese Milk Vetch(Astragalus sinicus L.) was submerged after direct-sowing, three levels of nitrogen top-dressed(0, 2, 4 kg N/10a) without basal N and two levels of sowing rate were applied into the paddy field in expectation of the enhancement of nitrogen efficiency and protection of agricultural environment in reduced N-fertilizer level. A cultivar, Dongjin, was direct-sown on May 30, 1996. Characteristics of rice growth and physicochemical properties of rice plant were observed. Under the system, reduced total N(4 kg N/10a) resulted in high panicle numbers. N-top dressed toward at later growth stages enhanced the ratio of panicle-producing tillers and at spikelet numbers per panicle. As N-level increases, DM yields of leaf and stem at heading were increased. Maximum grain yield was obtained at 4kg N/10a and major attributed factors to grain yield in this case were the number of grains per unit area and the ratio of ripened grain.

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