• Title/Summary/Keyword: Energy plant

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A CYBER SECURITY RISK ASSESSMENT FOR THE DESIGN OF I&C SYSTEMS IN NUCLEAR POWER PLANTS

  • Song, Jae-Gu;Lee, Jung-Woon;Lee, Cheol-Kwon;Kwon, Kee-Choon;Lee, Dong-Young
    • Nuclear Engineering and Technology
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    • v.44 no.8
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    • pp.919-928
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    • 2012
  • The applications of computers and communication system and network technologies in nuclear power plants have expanded recently. This application of digital technologies to the instrumentation and control systems of nuclear power plants brings with it the cyber security concerns similar to other critical infrastructures. Cyber security risk assessments for digital instrumentation and control systems have become more crucial in the development of new systems and in the operation of existing systems. Although the instrumentation and control systems of nuclear power plants are similar to industrial control systems, the former have specifications that differ from the latter in terms of architecture and function, in order to satisfy nuclear safety requirements, which need different methods for the application of cyber security risk assessment. In this paper, the characteristics of nuclear power plant instrumentation and control systems are described, and the considerations needed when conducting cyber security risk assessments in accordance with the lifecycle process of instrumentation and control systems are discussed. For cyber security risk assessments of instrumentation and control systems, the activities and considerations necessary for assessments during the system design phase or component design and equipment supply phase are presented in the following 6 steps: 1) System Identification and Cyber Security Modeling, 2) Asset and Impact Analysis, 3) Threat Analysis, 4) Vulnerability Analysis, 5) Security Control Design, and 6) Penetration test. The results from an application of the method to a digital reactor protection system are described.

Validation of a Real-Time Dose Assessment System over Complex Terrain (복잡한 지형상에서 실시간 피폭해석 시스템 검증)

  • Suh, Kyung-Suk;Kim, Eun-Han;Hwang, Won-Tae;Choi, Young-Gil;Han, Moon-Hee;Jung, Sung-Tae
    • Journal of Radiation Protection and Research
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    • v.24 no.1
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    • pp.31-38
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    • 1999
  • A real-time dose assessment system(FADAS : Following Accident Dose Assessment System) has been developed for the real-time accident consequence assessment against a nuclear accident. Field tracer experiment near Younggwang nuclear power plant was performed to improve the accuracy of developed system and to parameterize the site-specific parameters into the FADAS. The mean values and turbulent components of wind profile obtained through field experiment have been reflected to FADAS with site-specific conditions. The simulated results of diffusion model agreed well with the measured data through tracer experiment. The developed system is being used as a basic module of emergency preparedness system in Korea. The diffusion model which can be reflected site-specific parameters will be improved through field experiments continuously.

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Selection of 5-Methyltryptophan and S-(2-Aminoethyl)-L-Cysteine Resistant Microspore-Derived Rice Cell Lines Irradiated with Gamma Rays

  • Kim, Dong-Sub;Lee, In-Sok;Jang, Cheol-Seong;Hyun, Do-Yoon;Lee, Sang-Jae;Seo, Yong-Weon;Lee, Young-Il
    • Journal of Plant Biotechnology
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    • v.5 no.1
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    • pp.33-41
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    • 2003
  • Microspore-derived cell lines resistant to 5-methyltryptophan (5MT, a tryptophan analog) or S-(2-aminoethyl)-L-cysteine (AEC, a Iysine analog) were selected in rice by in vitro mutagenesis. For selection of 5MT or AEC resistant cell lines, suspension-cultured cells were irradiated with gamma rays. Thirteen 5MT resistant cell lines were selected and they were able to grow stably at 2 times higher 5MT concentration. A feedback insensitive form of anthranilate synthesis, the pathway specific control enzyme for tryptophan synthesis, was detected from the 5MT resistant lines. Contents of the free amino acids in five resistant lines (MR12-1 to MR12-5) showed a 7.4 to 46.6 times greater level than that in the control culture. Tryptophan, phenylalanine, and tyrosine levels in the shikimate pathway were 28.1 and 22.5 times higher in MR12-3 and MR12 4, respectively, than that measured in the control cells. Four AEC resistant cell lines were isolated from cultures grown on medium containing 1 mM AEC, They were able to grow stably with 2 mM AEC, while sensitive calli were inhibited by 0.5 mM AEC. Aspartate kinase activities of the resistant lines were insensitive to the natural inhibitor, Iysine, and accumulated 2.2 to 12.9-fold higher levels of free Iysine than that of the control cells. Especially, the levels of aspartate, asparagine, and methionine in the aspartate pathway showed higher accumulation in the AEC resistant lines than that in the control cells.

Development of Optimal Thermal Transfer Calculation Algorithm by Composition of Thermal Transfer Mechanism among Integrated Energy Operators (집단에너지 사업자간의 열연계 메커니즘 구성에 의한 최적 열연계 산정 알고리즘 개발)

  • Kim, Yongha;Kim, Seunghee;Hyeon, Seungyeon
    • Journal of Energy Engineering
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    • v.26 no.4
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    • pp.57-66
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    • 2017
  • Since the heat is not as fast as the electric power and the loss is relatively large compared to the electric power, it is not realistic to operate the thermal transfer system with on operation center like electric power trading. In the case of the Korea District Heating Corporation, where all the thermal transfer are currently being made, only two or four adjacent heat-generating power plants are being the heat trading. Therefore, In this paper, we concluded that it is appropriate to divide the integrated operation center for heat trading into several regions, to operate the hub integrated operation power plant in each region to reflect the characteristics of the heat medium and proposed the thermal transfer mechanism among integrated energy operators. Then, we have developed an algorithm that can optimize the heat transaction for the proposed mechanism and applied it to the actual operators to verify the usefulness of the proposed algorithm.

Investigation of the refined safety factor for berthing energy calculation

  • Kim, Sang Woo;Lee, Seung Jae;Kim, Young Tae;Kim, Do Kyun
    • Structural Engineering and Mechanics
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    • v.75 no.6
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    • pp.785-797
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    • 2020
  • As the growth of world trade has surged rapidly over the past years, the number is expected to continue growing over the coming years. Although the transportation costs can be reduced by using larger vessels, however, new berthing structures have to be constructed in order to cater for the larger vessels. This leads to a need for researching on designing a better berthing structure. For optimization of berthing structure design, we need to provide a better estimation of berthing energy than the previous methods in the existing guidelines. In this study, several berthing parameters were collected from previous works and researches. Moreover, the scenarios were selected efficiently by using a sampling technique. First, the berthing energy was calculated by executing 150 numerical simulations. Then, the numerical simulation results were compared with the results calculated by existing methods quantitatively to investigate the sensitivity of the berthing parameters and the accuracy of existing methods. The numerical method results have shown some deviation with respect to the existing method results in which the degree of deviation varies with the methods and the tendency of differences is dependent on certain berthing parameters. Then, one of the existing methods which has shown a small deviation was selected as a representative method and applied with several safety factors to obtain a suitable safety factor for the design.

Numerical Simulation for the Field Tracer Experiment over the Kori Nuclear Power Plant (고리 원전주변에서 야외 확산실험 모사)

  • Suh, Kyung-Suk;Kim, Eun-Han;Whang, Won-Tae;Jeong, Hyo-Joon;Han, Moon-Hee
    • Journal of Radiation Protection and Research
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    • v.29 no.3
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    • pp.205-212
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    • 2004
  • Three-dimensional wind field and atmospheric dispersion models have been developed for estimating the concentration distributions of radioactive materials released into atmosphere. The field tracer experiment near the Kori nuclear power plant located over complex terrain was carried out for validating the atmospheric dispersion model. The wind fields were one of the most important factors for calculating the concentration. Therefore several numerical simulations using the measured wind data were performed to get more accurate concentration distributions compared with the analyzed values of the tracer gas. The calculated concentration distributions agreed well in the case of the usage of the more measured wind data in wind field model.

Model for assessing the contamination of agricultural plants by accidentally released tritium (삼중수소 사고유출로 인한 농작물 오염 평가 모델)

  • Keum, Dong-Kwon;Lee, Han-Soo;Kang, Hee-Suk;Choi, Young-Ho;Lee, Chang-Woo
    • Journal of Radiation Protection and Research
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    • v.30 no.1
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    • pp.45-54
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    • 2005
  • A dynamic compartment model was developed to appraise the level of the contamination of agricultural plants by accidentally released tritium from nuclear facility. The model consists of a set of inter-connected compartments representing atmosphere, soil and plant. In the model three categories of plant are considered: leafy vegetables, grain plants and tuber plants, of which each is modeled separately to account for the different transport pathways of tritium. The predictive accuracy of the model was tested through the analysis of the tritium exposure experiments for rice-plants. The predicted TFWT(tissue free water tritium) concentration of the rice ear at harvest was greatly affected by the absolute humidity of air, the ratio of root uptake, and the rate of rainfall, while its OBT(organically bound tritium) concentration the stowing period of the ear, the absolute humidity of air and the content of hydrogen in the organic phase. There was a good agreement between the model prediction and the experimental results lot the OBT concentration of the ear.

Nitrate Removal by Pseudomonas fluorescens K4 Isolated from a Municipal Sewage Treatment Plant

  • Lee, O-Mi;Oh, Jong-Hyeok;Hwang, Doo-Seong;Choi, Yun-Dong;Chung, Un-Soo;Park, Jin-Ho;Kim, Min-Ju;Jeong, Seong-Yun;Lee, Sang-Joon
    • Journal of Environmental Science International
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    • v.16 no.11
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    • pp.1219-1223
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    • 2007
  • The removal of nitrogen compounds from a wastewater is essential and it is often accomplished by bio-logical process. An aerobic nitrate-removing bacterium was isolated from a municipal sewage treatment plant and soil. On the basis of its morphological, cultural and physiological characteristics and 16S rRNA sequencing data, this strain was identified as Pseudomonas fluorescens, and named as P. fluorescens K4. The optimal conditions of the initial pH and temperature of media for its growth were $7.0{\sim}8.0$ and $30^{\circ}C$, respectively. P. fluorescens K4 was able to remove 99.9% of nitrate after 24 h in a culture. The strain could grow with a nitrate concentration up to 800 mg/l and was able to remove 99.9% of nitrate after 104 h of incubation. The optimal electron donor was sodium citrate for a nitrate removal. The strain K4 showed a capability of a complete nitrate removal when the initial C/N ratio was 1.0. An effect of the initial seed concentration was observed for a cell of 10% (v/v) for a nitrate removal. Especially P. fluorescens K4 could completely remove 200 mg/l ammonium for 3 days.

Plant Cooldown Test Simulation After Steam Generator U-Tube Rupture under Onsite Power Available Without Safety Injection (증기발생기 세관파열사고 후 소외전원 가용 및 비상냉각수 주입 배제 조건하에서의 발전소냉각에 관한 실험 모사)

  • Kim, Du-Ill;Kim, Hee-Cheol;Auh, Geun-Sun;Kim, Joon-Sung;Park, Jae-Don
    • Nuclear Engineering and Technology
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    • v.27 no.4
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    • pp.483-490
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    • 1995
  • The objective of the PKL III A 4.4 experiment is to examine that the plant could be controlled by manually operative actions "after Steam Generator Tube Rupture under Offsite Power Available without Safety Injection". In order to verify the limitation and ability of the system code NLOOP in the expeiment simulation, the behaviors of the PKL III facility obtained in the experiment are compared with the results of NLOOP code. NLOOP code, which is originally developed to simulate the transients of the Westinghouse type PWRs by KAERI/SIEMENS, modified properly to simulate the PKL III facility. Particular attention is given to the RCS mass How rate of the natural circulation in loops and the termination behavior of the natural circulation in the isolated loop. The comparisons between the experimental and calculational results show the simulation ability and problems of the code. the code.

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JAEA'S VHTR FOR HYDROGEN AND ELECTRICITY COGENERATION : GTHTR300C

  • Kunitomi, Kazuhiko;Yan, Xing;Nishihara, Tetsuo;Sakaba, Nariaki;Mouri, Tomoaki
    • Nuclear Engineering and Technology
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    • v.39 no.1
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    • pp.9-20
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    • 2007
  • Design study on the Gas Turbine High Temperature Reactor 300-Cogeneration (GTHTR300C) aiming at producing both electricity by a gas turbine and hydrogen by a thermochemical water splitting method (IS process method) has been conducted. It is expected to be one of the most attractive systems to provide hydrogen for fuel cell vehicles after 2030. The GTHTR300C employs a block type Very High Temperature Reactor (VHTR) with thermal power of 600MW and outlet coolant temperature of $950^{\circ}C$. The intermediate heat exchanger (IHX) and the gas turbine are arranged in series in the primary circuit. The IHX transfers the heat of 170MW to the secondary system used for hydrogen production. The balance of the reactor thermal power is used for electricity generation. The GTHTR300C is designed based on the existing technologies of the High Temperature Engineering Test Reactor (HTTR) and helium turbine power conversion and on the technologies whose development have been well under way for IS hydrogen production process so as to minimize cost and risk of deployment. This paper describes the original design features focusing on the plant layout and plant cycle of the GTHTR300C together with present development status of the GTHTR300, IHX, etc. Also, the advantage of the GTHTR300C is presented.