• Title/Summary/Keyword: 원자력 발전소

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Scale Thickness Measurement of Steam Generator Tubing Using Eddy Current Signal of Bobbin Coil (보빈코일 와전류신호를 이용한 증기발생기 세관 스케일 두께 측정)

  • Kim, Chang-Soo;Um, Ki-Soo;Kim, Jae-Dong
    • Journal of the Korean Society for Nondestructive Testing
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    • v.32 no.5
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    • pp.545-550
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    • 2012
  • Steam generator is one of the major components of nuclear power plant and steam generator tubes are the pressure boundary between primary and secondary side, which makes them critical for nuclear safety. As the operating time of nuclear power plant increases, not only damage mechanisms but also scaled deposits on steam generator tubes are known to be problematic causing tube support flow hole blockage and heat fouling. The ability to assess the extent and location of scaled deposits on tubes became essential for management and maintenance of steam generator and eddy current bobbin data can be utilized to measure thickness of scale on tubes. In this paper, tube reference standards with various thickness of scaled deposit has been set up to provide information about the overall deposit condition of steam generator tubes, providing essential tool for steam generator management and maintenance to predict and prevent future damages. Also, methodology to automatically measure scale thickness on tubes has been developed and applied to field data to estimate overall scale amount.

Design of Uni-directional Optical Communication Structure Satisfying Defense-In-Depth Characteristics against Cyber Attack (사이버공격에 대비한 심층방호 특성을 만족하는 단방향 광통신 구조 설계)

  • Jeong, Kwang Il;Lee, Joon Ku;Park, Geun Ok
    • KIPS Transactions on Computer and Communication Systems
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    • v.2 no.12
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    • pp.561-568
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    • 2013
  • Instrumentation and control system in nuclear power plant performs protecting, controling and monitoring safety operation of Nuclear Power Plant. As cyber attack to the control equipment of instrumentation and control system can cause reactor shutdown and radiation release, it is required to design the instrumentation and control system considering cyber security in accordance with regulatory guides and industrial standards. In this paper, we proposed a design method of uni-directional communication structure which is required in the design of defense-in-depth model according to regulatory guides and industrial standards and we implemented a communication board with the proposed method. This communication board was tested in various test environments and test items and we concluded it can provide uni-directional communication structure required to design of defense-in-depth model against cyber attack by analyzing the results. The proposed method and implemented communication board were applied in the design of SMART (system-integrated modular advanced reactor) I&C (instrumentation and control) systems.

Anti-Corrosion Properties of TiN-Coated Bolt for Application to Nuclear Power Plants Located Near Coastal Areas (해안에 인접한 원자력발전소에 적용하기 위한 체결볼트의 TiN박막 코팅처리를 한 체결볼트의 방식특성)

  • Lee, Su-Been;Lee, Jin-Woo;Park, Soo-Jeong;Kim, Yun-Hae
    • Journal of Ocean Engineering and Technology
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    • v.30 no.5
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    • pp.356-360
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    • 2016
  • Recently, the lifetime extension of nuclear power plants has been considered. Thus, it is necessary to consider facility safety management and economic management. However, when the bolts in nuclear power plants are replaced and the turbines of nuclear power plant are disassembled, numerous problems are found in relation to stuck bolts in clamping parts. In order to solve these problems, a hybrid vacuum chamber was first designed and manufactured. It can perform arc ion plating and sputtering, which were used to deposit Ti/TiN on an A913 B7 bolt. X-ray diffraction (XRD) and scanning electron microscopy (SEM) analyses were conducted to determine the composition and characteristics of the bolt, and tests were conducted to determine how long the bolt could endure under various conditions in a nuclear power plant. The SEM and XRD results clearly showed a continual and even coating layer. When this TiN-coated bolt is used in a nuclear power plant, the lifetime can be extended compared to a conventional bolt, but it is necessary to determine what additional properties are required.

Removal of Cesium using Carbonyl iron-Prussian blue complex material in water (카보닐 철-프러시안 블루 합성체를 통한 수중의 세슘 제거)

  • Kim, Jong Kyu
    • Proceedings of the Korea Water Resources Association Conference
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    • 2019.05a
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    • pp.198-198
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    • 2019
  • 2011년 동일본 지역에서 발생한 지진으로 인하여 후쿠시마 다이이치에 위치한 원자력 발전소에서 다양한 방사성 물질들이 바다, 하천 그리고 대기와 같은 자연환경 속으로 유출되었다. 방사성 세슘(Cesuim, $Cs^{137}$)은 다양한 방사성 물질들 가운데 반감기(Half-life)가 30.17년으로 가장 긴 물질이다. 방사성 세슘이 환경 생태계로 한번 유출될 경우 긴 반감기과 널리 퍼지는 성질로 인하여 오랜 시간동안 넓은 지역에 막심한 피해를 초래하므로 효과적인 처리방법을 통해 안전하게 처리하는 것이 아주 중요하다. 세슘을 제거하기 위하여 물리적, 화학적, 생물학적 등 다양한 방법들을 통해 연구를 진행하고 있으며, 특히 세슘을 제거하는 아주 효과적인 방법 중 하나인 프러시안 블루(Prussian Blue, PB) 흡착제를 적용하는 방법이 많이 주목받고 있다. 그러나 프러시안 블루는 미세한 분말입자로서 수처리에 사용하게 되면 처리 후 발생되는 슬러지들을 수중으로 부터 분리하기 어려운 한계점을 가지고 있다. 최근 연구에서는 프러시안 블루의 적용 한계점를 극복하기 위하여 자성체(Magnetic substance)를 물리적 지지체로 이용하여 외부 자기장을 통해 수중으로 분리하는 방법들이 연구되고 있다. 자성체란 외부 자기장이 주어지게 되면 입자들 표면에 자성력을 띄는 물질들을 말한다. 본 연구에서는 자성체 종류들 가운데 가장 높은 자성력을 지닌 강자성체(Ferromagnetic Substance)를 물리적 지지체로 하여 산화과정, 실란과정, 합성과정을 거쳐 강자성체 입자의 표면에 프러시안 블루를 합성한 새로운 형태에 합성체를 제조하고, 제조된 합성체를 이용하여 수중에 존재하는 세슘 제거 능력을 평가하였다. 제조된 합성체의 물리적 특성을 분석하기 위하여 SEM, XRD를 이용하여 합성체 입자의 표면 분석을 진행하였다. 합성체의 세슘 제거 능력을 평가하기 위하여 임의 제조된 0.5mg/L의 세슘 농도를 가진 원수 100ml에 제조된 새로운 형태의 합성체 1g을 투입한 뒤 1분간의 반응시간 동안 반응한 이후 잔류 세슘을 측정한 결과 수중의 존재하는 세슘에 대해 99.9%의 세슘 제거율을 기록하였다. 자가분리(Magnetic Seperate)의 원리를 이용하여 수중으로부터 회수율을 측정한 결과, 99%의 합성체 회수율을 얻었다. 실험결과를 통해 외부자기장이 주어지게 되면 수중으로부터 합성체를 대부분 분리하여 회수할 수 있다고 판단된다. 본 연구를 통해 개발된 새로운 형태의 합성체는 수중의 세슘 처리 공정에서 사용자가 직접 접촉하지 않고 세슘제거 및 외부자기장을 통해 수중으로부터 분리가 가능한 합성체라고 판단된다.

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Electrical Degradation Properties of EPR Cable Partially Irradiated by $^{60}Co-{\gamma}$ Rays (부분적으로 $^{60}Co-{\gamma}$선 조사된 EPR 케이블의 절연열화 특성에 관한 연구)

  • Lee, Sung-Ill
    • Elastomers and Composites
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    • v.33 no.4
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    • pp.238-245
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    • 1998
  • In this paper, the electric property was investigated for insulation diagnosis of radiation of EPR electric power cables by partially irradiation with $^{60}Co-{\gamma}$ rays. As the rate of radiation increased from 100Mrad to 200Mrad, charging current and discharging current were increased from $1.03{\times}10^{-7}$(A) to $4.3{\times}10^{-9}$(A). In addition, we found charging current and discharging current of cables subjected to 50% and 16.7% irradiation changed the length of the part 1/2 to 1/6 as in comparison with cables degraded by 100% irradiation. For 22m and 66m of cables which had not been degraded yet, we realized the value of charging current and discharging current of 66m cables is three times higher than 22m cables. From these results, it is demonstrated that the possibility of utilizing charging current and discharging current as the diagnosis method of insulation degradation with irradiating EPR cables by $^{60}Co-{\gamma}$ rays.

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Design of Class and Causality Model for Diagnosis System of an Emergency Generator in Nuclear Plant (원전 비상 발전기의 고장진단시스템을 위한 클래스 및 인과관계 모형 설계)

  • Ha, Chang-Seung;Part, Jong-Il
    • Journal of the Korea Society of Computer and Information
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    • v.11 no.3
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    • pp.125-132
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    • 2006
  • The construction of an emergency generator's diagnosis system for the preparation of emergency in nuclear plant is vital. To construct a knowledge base of the diagnosis system, the classes and a causality model should be designed. In order to design those elements, at first. object of the diagnosis system should be defined. After the investigation of normal and abnormal states. the external knowledge such as entities and activities is extracted, that the operational principle of the system. For the conversion of the extracted external knowledge to the internal one, the entities are defined as classes and the activities converted into the causality. Through the recursive configuration of the causality and proper examination, the diagnosis knowledge applicable to the knowledge base is completed. In this paper, it is possible to construct a knowledge base with high portability since the independence of design model is considered through the decision table.

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Evaluation of Filling Performance of Steel Concrete Panel (SCP) Mock-up Member with Low-binder based High-fluidity Concrete (저분체 기반 고유동 콘크리트의 Steel Concrete Panel Mock-up 부재 충전 성능 평가)

  • Park, Gi Joon;Park, Jung Jun;Kim, Sung Wook
    • KSCE Journal of Civil and Environmental Engineering Research
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    • v.39 no.4
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    • pp.477-483
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    • 2019
  • Recently, precast type SCP modules are being used instead of PSC structures in order to reduce the construction period and costs of special structures such as nuclear power plants and LNG storage tanks. The inside of the SCP module is connected with a stud for the integral behavior of the steel and concrete, and the use of high fluidity concrete is required. High fluidity concrete generally has a high content of binder, which leads to an increase in hydration heat and shrinkage, and a problem of non-uniform strength development. Therefore, in this study, fluidity and passing performance of high fluidity concrete according to material properties are investigated to select optimum mix design of low binder based high fluidity concrete. Mechanical properties of high fluidity concrete before and after pumping are examined using pump car. The filling performance of SCP mock-up members was evaluated by using high fluidity concrete finally.

Improved Anti-Jamming Frame Error Rate and Hamming Code Repetitive Transmission Techniques for Enhanced SATURN Network Reliability Supporting UAV Operations (UAV 운영 신뢰성 개선을 위한 SATURN 통신망 항재밍 프레임 오율과 해밍코드 반복 전송 향상 기술)

  • Hwang, Yoonha;Baik, Jungsuk;Gu, Gyoan;Chung, Jong-Moon
    • Journal of Internet Computing and Services
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    • v.23 no.3
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    • pp.1-12
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    • 2022
  • As the performance of Unmanned Aerial Vehicles (UAVs) are improving and the prices are lowering, it is expected that the use of UAVs will continuously grow in the future. It is important to always maintain control signal and video communication to operate remote UAVs stably, especially in military UAV operations, as unexpected jamming attacks can result in fatal UAV crashes. In this paper, to improve the network reliability and low latency when supporting UAV operations, the anti-jamming performance of Second generation Anti-jam Tactical UHF Radio for NATO (SATURN) networks is analyzed and enhanced by applying Forward Error Correction (FEC) and Minimum Shift Keying (MSK) modulation as well as Hamming code based multiple transmission techniques.

Soil Washing Technology for Sr and Cs-contaminated Soil Near Nuclear Power Plants using Calcium and Potassium Based Solutions (칼슘 및 칼륨 용액을 이용한 원자력발전소 주변 스트론튬과 세슘 오염토양 세척기술 연구)

  • Song, Hojae;Nam, Kyoungphile
    • Journal of Soil and Groundwater Environment
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    • v.27 no.2
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    • pp.76-86
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    • 2022
  • Calcium (Ca) and potassium (K) were introduced to remove Sr and Cs in soil, respectively. Four factor and three level Box-Bhenken design was employed to determine the optimal washing condition of Ca- and K-based solutions, and the ranges tested were 0.1 to 1 M of Ca or K, L/S ratio of 5 to 20, washing time of 0.5 to 2 h, and pH of 2 to 7. The optimal washing condition determined was 1 M of Ca or K, L/S ratio of 20, washing time of 1 h, and pH of 2, and Ca-based and K-based solutions showed 68 and 81% removal efficiency for Sr and Cs, respectively in soil. For comparison, widely used conventional washing agents such as 0.075 M EDTA, 0.01 M citric acid, 0.01 M oxalic acid, and 0.05 M phosphoric acid were tested, and they showed 25 to 30% of Sr and Cs removal efficiency. Tessier sequential extraction was employed to identify the changes in chemical forms of Sr and Cs during the washing. In contrast to the conventional washing agents, Ca-based and K-based solutions were able to release relatively strongly bound forms of Sr and Cs such as Fe/Mn-oxide and organic matter bound forms, suggesting the involvement of direct substitution mechanism, probably due to the physicochemical similarities between Sr-Ca and Cs-K.

Adsorption of Cesium from an Aqueous Solution Using Activated Carbon Impregnated with triethylenediamine (TEDA) (Triethylenediamine (TEDA)로 첨착된 활성탄소를 이용한 수용액에서 세슘의 흡착)

  • Jong-Soo Choi;Suk Soon Choi;Choong Jeon;Tae-Young Jeong;Jeong Hyub Ha;Jae-Hoon Lee
    • Journal of the Korea Organic Resources Recycling Association
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    • v.31 no.3
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    • pp.65-71
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    • 2023
  • Cesium discharged from nuclear power plants requires technology for safely treating, due to its harmfulness to the human body. In this work, activated carbon impregnated with triethylenediamine (TEDA) process was applied to effectively remove cesium dissolved in aqueous solution. The surfaces on the activated carbon were chemically modified with various TEDA concentrations (2.5, 5.0, 7.5, 10.0, and 12.5%) and the optimal TEDA concentration was obtained to be 5.0% by the assessment for cesium removal efficiency. In addition, when 5.0% TEDA-impregnated activated carbon was used to treat 5.0 and 10.0 mg/L of cesium, the removal efficiency was 71.5% and 61.1%, respectively. Also, it was found to be the chemical adsorption from the adsorption kinetics experiment by temperature change. A novel remediation technology developed in this study could be practically employed for removing cesium contained in surface and ground water.