• Title/Summary/Keyword: Reactor monitoring

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A Study on the Effect of Bioceramics as Biochemosorption Material in Sequencing Batch Reactor (연속회분식 반응조에서 생화학흡착제로서 바이오세라믹의 영향에 관한 연구)

  • Lee, Seunghwan;Islam, M.S.;Kang, Meea
    • Journal of Korean Society of Water and Wastewater
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    • v.20 no.3
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    • pp.367-375
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    • 2006
  • Sequencing Batch Reactor (SBR) is well adopted for community wastewater treatment for its simplicity, performance and various advantageous treatment options. SBR is now drawing attention for its process modification such as coupled with membrane bioreactor, reverse osmosis or applying different media to achieve high removal efficiency. This study focused on the improved efficiency of carbon, nitrogen and phosphorous removal by applying zeolite materials called bioceramics to the SBR. Two laboratory-scale SBR units were operated in the same operating conditions - one with bioceramics called Bioceramic SBR (BCSBR) and the other without bioceramics used as control. Routine monitoring of COD, TP, $NH_3-N$, $NO_3-N$ was performed throughout this study. COD removal was about 80% to 100% and phosphorous removal was about 60% in the process whereas $NH_3-N$ removal efficiency was found to be 99.9% in the BCSBR unit. Addition of bioceramics also improved sludge characteristics such as sludge dewaterability, specific gravity and particle size. BCSBR can withstand high ammonia shock loading leading to the better treatment capacity of high ammonia containing wastewater. The cause of improved removal efficiencies within the biological reactor could be attributed to the biochemosorption mechanisms of bioceramics. Absorption/adsorption or desorption capacity of bioceramics was tested through laboratory experiments.

Effects of superimposed cyclic operation on corrosion products activity in reactor cooling system of AP-1000

  • Mahmood, Fiaz;Hu, Huasi;Lu, Guichi;Ni, Si;Yuan, Jiaqi
    • Nuclear Engineering and Technology
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    • v.51 no.4
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    • pp.1109-1116
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    • 2019
  • It is essential to predict the radioactivity distribution around the reactor cooling system (RCS) during obligatory cyclic operation of AP-1000. A home-developed program CPA-AP1000 is upgraded to predict the response of activated corrosion products (ACPs) in the RCS. The program is written in MATLAB and it uses state of the art MCNP as a subroutine for flux calculations. A pair of cyclic power profiles were superimposed after initial full power operation. The effect of cyclic operation is noticed to be more prominent for in-core surfaces, followed by the primary coolant and out-of-core structures. The results have shown that specific activity trends of $^{56}Mn$ and $^{24}Na$ promptly follow the power variations, whereas, $^{59}Fe$, $^{58}Co$, $^{99}Mo$ and $^{60}Co$ exhibit a sluggish power-following response. The investigations pointed out that promptly power-following response of ACPs in the coolant is vital as an instant radioactivity source during leakage incidents. However, the ACPs with delayed power-following response in the out-of-core components are perceived to cause a long-term activity. The present results are found in good agreement with those for a reference PWR. The results are useful for source term monitoring and optimization of work procedures for an innovative reactor design.

RPV 상하부에서 발생되는 금속파편의 충격위치 평가

  • 최재원;이일근;송영중;구인수;박희윤
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.166-171
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    • 1997
  • LPMS(Loose Part Monitoring System)는 원자로 및 냉각재계통내에서 발생하는 금속파편의 검출 및 분석을 위하여 사용되는 진단 장비이다. 본 논문에서는 RPV(Reactor Pressure Vessel)의 상부헤드(closure head)와 하부헤드(lower head)에서의 금속파편의 충격위치를 평가하는 LPMS를 위한 새로운 기법을 제안하고, Mock-up에서의 실험을 통하여 그 효용성을 검증하였다. 즉, 수정된 원교차법을 제안하고, 이를 반구로 모델링된 RPV의 상ㆍ하부헤드에 존재하는 금속파편의 위치평가에 적용하므로써 정확한 충격위치를 찾을 수 있음을 보였다. 이들 결과는 충격물질의 질량이나 에너지를 계산하는데 정확한 정보를 제공해 줄 수가 있다.

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Development of Guidelines for seismic isolation Design of LMR (액체금속로 면진설계를 위한 지침서 개발)

  • Yoo, Bong;Koo, Gyeong-Hoi;Lee, Jae-Han
    • Proceedings of the Earthquake Engineering Society of Korea Conference
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    • 1998.04a
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    • pp.147-154
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    • 1998
  • The purpose of this paper is to propose the draft guidelines of seismic isolation design of Liquid Metal Reactor (LMR) using high damping laminated rubber bearings. The scopes of guidelines include design requirements of a seismically isolated system and components, seismic isolator, isolation system, interface system between seismic isolation and non-seismic isolation part, qualification and acceptance tests of seismic isolator, seismic isolation reliability, and seismic safety and monitoring system. Proposed guidelines shall be revised to extend to general design guideline for nuclear facilities by further research and discussions.

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A Mobile Robot for Remote Inspection of Radioactive Waste (방사선폐기물 원격감시용 이동로봇)

  • 서용칠;김창회;조재완;최영수;김승호
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.430-432
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    • 2004
  • Tele-operation and remote monitoring techniques are essential and important technologies for the inspection and maintenance of the radioactive waste. A mobile robot has been developed for the application of remote monitoring and inspection of nuclear facilities, where human access is limited because of the high-level radioactive environments, The mobile robot was designed with reconfigurable crawler type of wheels attached on the front and rear side in order to pass through the ditch, The extendable mast, mounted on the mobile robot, car be extended up to 8 m vertically. The robust controller for radiation is designed in focus on electric components to prevent abnormal operation in a highly radioactivated area during reactor operation, This robot system will enhance the reliability of nuclear power facilities, and cope with the unexpected radiation accident.

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Coordinated Voltage-Reactive Power Control Schemes Based on PMU Measurement at Automated Substations

  • Choi, Yun-Hyuk;Kang, Sang-Gyun;Lee, Byongjun
    • Journal of Electrical Engineering and Technology
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    • v.10 no.4
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    • pp.1400-1407
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    • 2015
  • This paper deals with methodology to control an automatic substation system. The control system can predict the power system condition by a voltage stability index (VSI). The strategies in this paper is called as Voltage-Reactive Power Control (VRPC), which regulates an abnormal voltage of a target substation by using coordination between tap changers and shunt capacitor/reactor. This method is efficient for better voltage profile. The monitoring substation includes whole of substations around the contingency event. The control quantities of the monitoring substations are decided by the calculation of the VSI, called as a Z-index. Case studies with BC Hydro-Quebec system are presented to illustrate this approach using real-time simulator.

Development of Fault Monitoring Technique for Agitator Driving System

  • Park, Gee-yong;Park, Byung-suk;Yoon, Ji-sup;Hong, Dong-hee;Jin, Jae-hyun
    • 제어로봇시스템학회:학술대회논문집
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    • 2002.10a
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    • pp.32.1-32
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    • 2002
  • The fault monitoring technique is presented for identifying the status of the agitator driving system in thermal reduction reactor. For identifying a fault such as bearing defect or clearance blocking, Wavelet transform (WT) is applied to vibration signals and features are extracted. For classification, the fuzzy ARTMAP is employed. With the features from WT, a single training epoch and a single learning iteration are sufficient for the fuzzy ARTMAP to classify the faults. The test results show the perfect classification though some features extracted from the test data are distorted against those in the training data

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The Estimation Method of the Impact Position Using the Envelope of Impact Signal (충격 신호의 포락선을 이용한 충격 위치 추정기법)

  • Lee Wee-Hyuk;Woo Kyoung-Hang;Choi Won-Ho;Lee Jae-Kook
    • Journal of Institute of Control, Robotics and Systems
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    • v.12 no.7
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    • pp.650-657
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    • 2006
  • The LPMS (Loose Part Monitoring Systems) are used widely for detecting the impact position in the nuclear reactor. There are some major methods to detect impact position in LPMS such as the triangular method, the rectangular method, the circular intersection method and so on. The time difference of these methods are calculated using S0-mode and A0-mode waves of each sensor. In this paper, we propose a method to detect impact position using the enveloped waves of acquired signals. The result of this paper show that the position detecting accuracy and reducing the processing time are proposed method is improved than traditional methods.

A Dual Radiation Monitoring System Ror Robot Working in High Radiation Field (고방사선장내 작업 로봇용 이중 방사선 감지 시스템)

  • Lee Nam-Ho;Cho Jai-Wan;Kim Seung-Ho
    • The Transactions of the Korean Institute of Electrical Engineers D
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    • v.54 no.9
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    • pp.556-558
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    • 2005
  • The effect of high irradiation on inspection systems in a nuclear power plant can be severe, especially to electronic components such as control hoards. The effect may lead to a critical malfunction or trouble to a underwater robot for inspection and maintenance of nuclear reactor. However, if information on the total accumulated dose on the sensitive parts of the robot is available, a prediction of robot's behavior in radiation environments becomes possible. To know how much radiation the robot has encountered, a dosimeter to measure the total accumulated dose is necessary. This paper describes the development effort of a dual radiation monitoring system using a SiC diode as a dose-rate meter and a p-type power MOSFET as a dose meter. This attempt using two sensors which detect same radiation improves reliability and stability at high intensity radiation detection in nuclear facilities. It uses the concept of diversity and redundancy.

Monitoring Performance of Camera under the High Dose-rate Gamma Ray Environment (고선량율 감마선 환경하에서의 카메라 관측성능)

  • Cho, Jai-Wan;Jeong, Kyung-Min
    • The Transactions of The Korean Institute of Electrical Engineers
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    • v.61 no.8
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    • pp.1172-1178
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    • 2012
  • In this paper, the gamma ray irradiation test results of the CCD cameras are described. From the low dose-rate (2.11 Gy/h) to the high dose-rate (150 Gy/h) level, which is the same level when the hydrogen explosion was occurred in the 1~3 reactor unit of the Fukushima nuclear power plant, the monitoring performance of the cameras owing to the speckles are evaluated. The numbers of speckles, generated by gamma ray irradiation, in the image of cameras are calculated by image processing technique. And the legibility of the sensor indicator (dosimeter) owing to the numbers of the speckles is presented.