• 제목/요약/키워드: Reactor monitoring

검색결과 204건 처리시간 0.028초

Status of Loose Part Monitoring Technology and Facility in Domestic Nuclear Power Plant (국내 원전의 금속파편 감시기술 및 설비 현황)

  • Kim, Tae-Ryong;Lee, Jun-Shin;Sohn, Seok-Man
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 한국소음진동공학회 2000년도 춘계학술대회논문집
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    • pp.670-678
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    • 2000
  • Loose parts monitoring system(LPMS) is one of the important monitoring systems for the safe and efficient operation of the nuclear reactor, since it is LPMS that can early detect loose parts which may cause a significant damage in facilities or components of the plant. Nuclear power plants in Korea have recently experienced several loose part alarms due to the metallic impact and it is expected that the frequency of the loose part will be increased along the aging of the plants. In this paper, the status of loose parts monitoring technologies and facilities in Korean nuclear power plants is presented for the establishment of LPMS installation plan in some nuclear reactors which are not yet equipped with LPMS. Sensor specification, location and mounting method for loose parts monitoring were reviewed. As a result, the location and the mounting method of the properly chosen sensor was recommended. Data acquisition algorithms and discriminating rules of loose part impact signals were also reviewed. Actual alarm cases occurred by true impact signal and false impact signal were stated here.

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MATHEMATICAL MODEL OF SULFUR UTILIZING AUTOTROPHIC DENITRIFICATION IN AN UP-FLOW PACKED-BED REACTOR BASED ON BIOMASS DISTRIBUTION

  • Park, Woo-Shin;Ahn, Yoeng-Hee;Jung, Kyung-Ja;Tatavarty, Rameshwar;Kim, In-S.
    • Environmental Engineering Research
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    • 제10권4호
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    • pp.191-198
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    • 2005
  • A novel technology for the removal of nitrogen from wastewater, an autotrophic denitrification process with sulfur particles, has been developed. A respirometer was employed to monitor the nitrogen gas produced in the reactor, while 4',6-diamidino-2-phenylindole staining was employed to investigate the biomass distribution in terms of cell number according to the reactor height. From the respirometric monitoring, the denitrification reaction was defined as a first order reaction. The reactor was divided into 7 sections and biomass was analyzed in each section where cell number was ranged from $4.8\;{\times}\;10^6\;to\;8.7\;{\times}\;10^7$ cells/g dry weight of sulfur. Cells placed mostly in the lower layer ( < 10 cm of height). A function for biomass distribution was obtained with non-linear regression. Then a mathematical model has been developed by combining a plug-flow model with the biomass distribution function. The model could make a vertical profile of the up-flow packed-bed reactor resulting in a reasonable comparison with measured nitrate concentration with 5% of error range.

Development of Cyanide Sensor Using S. cerevisiae (S. cerevisiae를 이용한 시안센서의 개발)

  • 김종민;이현우
    • KSBB Journal
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    • 제11권6호
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    • pp.669-675
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    • 1996
  • Two types of cyanide sensor system were constructed for monitoring river water simply. One is membrane type flow system composed of S. cerevisiae coated membrane and oxygen electrode, the other is reactor type flow system composed of S. cevevisiae immobilized reactor and two oxygen electrode. S. cerevisiae and oxygen electrode were used for detecting cyanide compounds. These sensors are based on the inhibition of cyanides on the respiration activity of S. cerevisiae. Membrane type sensor system could detect cyanides ranging 0.10∼1.00ppm, and the respiration activity of S. cerevisiae continued for a day. Reactor type sensor system composed of immobilized chitopearl HP-5020 with S. cerevisiae could detect cyanides in the range of 0.10∼1.00ppm, and maintained 90% respiration activity for sixteen days. It was found that the optimum reactor size exist for the reactor type biosensor when respirating activity inhibition is used for detection of cyanides.

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Operating Characteristics of a 0.25 MW Methanation Pilot Plant with Isothermal Reactor and Adiabatic Reactor (등온반응기와 단열반응기 조합으로 구성된 0.25 MW급 메탄합성 파일롯 공정 운전특성)

  • Kim, Suhyun;Yoo, Youngdon;Kang, Sukhwan;Ryu, Jaehong;Kim, Jinho;Kim, Munhyun;Koh, Dongjun;Lee, Hyunjung;Kim, Gwangjun;Kim, Hyungtaek
    • Clean Technology
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    • 제19권2호
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    • pp.156-164
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    • 2013
  • In this study, we analyzed the operational characteristics of a 0.25 MW methanation pilot plant. Isothermal reactor controled the heat released from methanation reaction by saturated water in shell side. Methanation process consisting of isothermal reactor and adiabatic reactor had advantages with no recycle compressor and more less reactors compared with methanation process with only adiabatic reactors. In case that $H_2$/CO ratio of syngas was under 3, carbon deposition occurred on catalyst in tube side of isothermal reactor and the pressure of reactors increased. In case that $H_2$/CO ratio was maintained around 3, no carbon deposition on catalyst in tube side of isothermal reactor was found by monitoring the differential pressure of reactors and by measuring the differential pressure of several of tubes filled with catalyst before and after operating. It was shown that CO conversion and $CH_4$selectivity were over 99, 97%, respectively, and the maximum $CH_4$productivity was $695ml/h{\cdot}g-cat$.

Fault Diagnosis for Agitator Driving System in a High Temperature Reduction Reactor

  • Park Gee Young;Hong Dong Hee;Jung Jae Hoo;Kim Young Hwan;Jin Jae Hyun;Yoon Ji Sup
    • Nuclear Engineering and Technology
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    • 제35권5호
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    • pp.454-470
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    • 2003
  • In this paper, a preliminary study for development of a fault diagnosis is presented for monitoring and diagnosing faults in the agitator driving system of a high temperature reduction reactor. In order to identify a fault occurrence and classify the fault cause, vibration signals measured by accelerometers on the outer shroud of the agitator driving system are firstly decomposed by wavelet transform (WT) and the features corresponding to each fault type are extracted. For the diagnosis, the fuzzy ARTMAP is employed and thereby, based on the features extracted from the WT, the robust fault classifier can be implemented with a very short training time - a single training epoch and a single learning iteration is sufficient for training the fault classifier. The test results demonstrate satisfactory classification for the faults pre-categorized from considerations of possible occurrence during experiments on a small-scale reduction reactor.

Reactor Neutron Noise Analysis using AR Spectral Estimation (AR 스펙트럼 추정법을 이용한 원자로 중성자 잡음 신호 해석)

  • Sim, Cheul-Muu;Hwang, Tae-Jin;Baik, Heung-Ki
    • The Journal of the Acoustical Society of Korea
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    • 제16권5호
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    • pp.83-91
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    • 1997
  • A reactor vibration monitoring has been performed using neutron noise obtained from excore detectors for the safety operation, Traditionally, the spectral estimator based on Fourier analysis has been widely used in the noise analysis of the reactor system. If the bias is too severe, the resolution would not be adequate for a given application. One major motivation for the current interests in the parametric approach to spectral estimation is the apparent higher resolution achievable with these modern techniques. In considering an unbias, a consistency, an efficency, and a minimum lower bound of the statictic estimation, an AR model is appropriate for noise spectral estimation with sharp peaks but not deep valley. In order to select an appropriate model order, the lag value of autocorrleaton function is applied. Burg method to trace the vibration mode of RPV internal is the most sucuessful.

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A Study on Design of the Trip Computer for ECC System Based on Dynamic Safety System

  • Kim, Seog-Nam;Seong, Poong-Hyun
    • Nuclear Engineering and Technology
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    • 제32권4호
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    • pp.316-327
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    • 2000
  • The Emergency Core Cooling System in current nuclear power plants typically has a considerable number of complex functions and largely cumbersome operator interfaces. Functions for initiation, switch-over between various phases of operation, interlocks, monitoring, and alarming are usually performed by relays and analog comparator logic which are difficult to maintain and test. To improve problems of an analog based ECC (Emergency Core Cooling) System, the trip computer for ECCS based on Dynamic Safety System (DSS) is implemented. The DSS is a computer based reactor protection system that has fail-safe nature and performs a dynamic self-testing. The most important feature of the DSS is the introduction of test signal that send the system into a tripped state. The test signals are interleaved with the plant signals to produce an output which switches between a tripped and health state. The dynamic operation is a key feature of the failsafe design of the system. In this work, a possible implementation of the DSS using PLC is presented for a CANDU Reactor. ECC System of the CANDU Reactor is selected as the reference system.

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Diversity of Nitrifying and Denitrifying Bacteria in SMMIAR Process (완전침지형 회전매체공정 내 질산화 및 탈질 관련 미생물의 군집 분포)

  • Quan, Zhe-Xue;Lim, Bong-Su;Kang, Ho;Yoon, Kyung-Yo;Yoon, Yeo-Gyo
    • Journal of Korean Society on Water Environment
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    • 제22권6호
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    • pp.1014-1021
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    • 2006
  • SMMIAR (Submerged Moving Media Intermittent Aeration Reactor) Process is a very efficient system which remove ammonia to nitrogen gas in one reactor. In this study, we determined the diversity of ammonia oxidizing bacteria and denitrifying bacteria using specific PCR amplification and the clone library construction. An ammonia monooxygenase gene(amoA) was analyzed to investigate the diversity of nitrifiers. Most of amoA gene fragments (27/29, 93%) were same types and they are very similar (>99%) to the sequences of Nitrosomonas europaea and other clones isolated from anoxic ammonia oxidizing reactors. ANAMMOX related bacteria have not determined by specific PCR amplification. A nitrite reductase gene(nirK) was analyzed to investigate the diversity of denitrifying bacteria. About half (9/20, 45%) of denitrifiers were clustered with Rhodobacter and most of others were clustered with Mesorhizobium (6/20, 30%) and Rhizobium (3/20, 15%). All of these nirK gene clones were clustered in alpha-Proteobacteria and this result is coincide with other system which also operate nitrification and denitrification in one reactor. The molecular monitoring of the population of nitrifiers and denitrifiers would be helpful for the system stabilization and scale-up.

KINETICS OF AUTOTROPHIC DENITRIFICATION FOR THE BIOFILM FORMED ON SULFUR PARTICLES : Evaluation of Molecular Technique on Monitoring Biomass Growth

  • Kim, Sung-Youn;Jang, Am;Kim, I-Tae;Kim, Kwang-Soo;Kim, In-S.
    • Environmental Engineering Research
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    • 제10권6호
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    • pp.283-293
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    • 2005
  • Characteristics of sulfur-based autotrophic denitrification in a semi-continuous type reactor and the kinetic parameters were studied. Enriched autotrophic denitrifying culture was used for the reactor operation. Biomass growth on sulfur particles and in the liquid medium was monitored using the DAPI staining method. From the result of ion concentration changes and the biomass growth, maximum specific growth rate, ${\mu}_{max}$, and the half velocity constant, $K_M$, were estimated as $0.61\;d^{-1}$ and 3.66 mg/L, respectively. Growth yield coefficient, Y values for electron acceptor and donor were found as 0.49 gVSS/g N and 0.16 gVSS/g S. The biomass showed specific denitrification rate, ranging 0.86-1.13 gN/g VSS-d. A half-order equation was found to best simulate the denitrification process in the packed bed reactor operated in the semi-continuous mode.

The Dynamic Characteristics and Defect Analysis of Pressurized Water Reactor Internals (원자로 내부구조물의 동특성 및 결함해석)

  • Ahn, Chang-Gi;Park, Jin-Ho;Lee, Jeong-Han;Chae, Young-Chul;Song, Oh-Seop
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 한국소음진동공학회 2005년도 추계학술대회논문집
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    • pp.267-270
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    • 2005
  • Finite element model of pressurized water reactor internals were obtained using ANSYS software package to analyze dynamic characteristics. The pressure vessel, hold-down ring, alinement key, core support barrel(CSB), upper guide structure(UGS) and fluid gap were fully modeled using structural solid element(SOLID45) and fluid element(FLUID80) which is one of element types. Also modal analysis using the above finite element model has been performed. As a result, it was found that the fundamental beam mode natural frequency of the CSB were 8.2 Hz, the shell mode one 14.5 Hz. To verify the Finite Element Analysis(FEA), we compare the analysis result with experimental data that is obtained from the plant IVMS(internal Vibration Monitoring System). The experimental results are good agreement with the FEA model.

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