• 제목/요약/키워드: A/A Reactor System

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연구용 원자로의 정지봉 장치 성능에 미치는 인자 분석과 성능 시험 (Performance test and factor analysis on the performance of shutoff units with the research reactor)

  • 김경련;김석범;고재명;문균영;박종호
    • 한국유체기계학회 논문집
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    • 제10권2호
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    • pp.41-45
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    • 2007
  • The shutoff unit was designed to provide rapid insertion of neutron absorbing material into the reactor core to shutdown the reactor quickly and also to withdraw the absorber slowly to avoid a log-rate trip. Four shutoff units were installed on the HANARO reactor but the half-core test facility was equipped with one shutoff unit. The reactor trip or shutdown is accomplished by four shutoff units by insertion of the shutoff rods. The shutoff rod(SOR) is actuated by a directly linked hydraulic cylinder on the reactor chimney, which is pressurized by a hydraulic pump. The rod is released to drop by gravity, when triplicate solenoid valves are de-energized to vent the cylinder. The hydraulic pump, pipe and air supply system are provided to be similar with the HANARO reactor. The shutoff rod drops for 647mm stroke within 1.13 seconds to shut down the reactor and it is slowly inserted to the full down position, 700mm, with a damping. We have conducted the drop test of the shutoff rod in order to show the performance and the structural integrity of operating system of the shutoff unit. The present paper deals with the 647mm drop time and the withdrawal time according to variation of the pool water temperature, the water level and the core flow.

Automatic Inspection of Reactor Vessel Welds using an Underwater Mobile Robot guided by a Laser Pointer

  • Kim, Jae-Hee;Lee, Jae-Cheol
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2004년도 ICCAS
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    • pp.1116-1120
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    • 2004
  • In the nuclear power plant, there are several cylindrical vessels such as reactor vessel, pressuriser and so on. The vessels are usually constructed by welding large rolled plates, forged sections or nozzle pipes together. In order to assure the integrity of the vessel, these welds should be periodically inspected using sensors such as ultrasonic transducer or visual cameras. This inspection is usually conducted under water to minimize exposure to the radioactively contaminated vessel walls. The inspections have been performed by using a conventional inspection machine with a big structural sturdy column, however, it is so huge and heavy that maintenance and handling of the machine are extremely difficult. It requires much effort to transport the system to the site and also requires continuous use of the utility's polar crane to move the manipulator into the building and then onto the vessel. Setup beside the vessel requires a large volume of work preparation area and several shifts to complete. In order to resolve these problems, we have developed an underwater mobile robot guided by the laser pointer, and performed a series of experiments both in the mockup and in the real reactor vessel. This paper introduces our robotic inspection system and the laser guidance of the mobile robot as well as the results of the functional test.

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Evaluation of a Sodium-Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor

  • Ahn, Sang June;Ha, Kwi-Seok;Chang, Won-Pyo;Kang, Seok Hun;Lee, Kwi Lim;Choi, Chi-Woong;Lee, Seung Won;Yoo, Jin;Jeong, Jae-Ho;Jeong, Taekyeong
    • Nuclear Engineering and Technology
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    • 제48권4호
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    • pp.952-964
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    • 2016
  • The prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Korea Atomic Energy Research Institute. This reactor uses sodium as a reactor coolant to transfer the core heat energy to the turbine. Sodium has chemical characteristics that allow it to violently react with materials such as a water or steam. When a sodium-water reaction (SWR) occurs due to leakage or breakage of steam generator tubes, high-pressure waves and corrosive reaction products are produced, which threaten the structural integrity of the components of the intermediate heat-transfer system (IHTS) and the safety of the primary heat-transfer system (PHTS). In the PGSFR, SWR events are included in the design-basis event. This event should be analyzed from the viewpoint of the integrities of the IHTS and fuel rods. To evaluate the integrity of the IHTS based on the consequences of the SWR, the behaviors of the generated high-pressure waves are analyzed at the major positions of a failed IHTS loop using a sodium-water advanced analysis method-II code. The integrity of the fuel rods must be consistently maintained below the safety acceptance criteria to avoid the consequences of the SWR. The integrity of the PHTS is evaluated using the multidimensional analysis of reactor safety-liquid metal reactor code to model the whole plant.

Study on the Gas-Liquid Mixing Characteristics in Reactor System Using Ejector

  • Jin, Zhen-Hua;Utomo, Tony;Chung, Han-Shik;Jeong, Hyo-Min;Shin, You-Sik;Lee, Sang-Chul
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2007년도 춘계학술대회B
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    • pp.2708-2713
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    • 2007
  • The aim of this paper is further studies to achieve deeper understanding in this field. First investigate the influence of operating conditions and design parameters on the hydrodynamics and the mass transfer properties of a loop reactor. This paper provides a literature review on the ejectors applications in the mixing system. A number of studies are grouped and discussed in several topics such as the background, theory of ejector, mixing characteristics, optimization of the system. Since the high efficiencies reactor using ejector widely used in gas-liquid system, especially in a number of chemical and biochemical processes. This is due to their high efficiency in gas dispersion resulting in high mass transfer rate and low power requirements. Thus ejector has been applied to the mixing system. An investigation on hydrodynamics and mass transfer characteristics of gas-liquid ejector has been carried out using three-dimensional CFD modeling.

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가압경수로 원자로용기와 제어봉 구동장치의 동적 상호작용 (Dynamic Interactions between the Reactor Vessel and the CEDM of the Pressurized Water Reactor)

  • ;김천욱
    • 소음진동
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    • 제7권5호
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    • pp.837-845
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    • 1997
  • 본 연구에서는 가압경수로의 핵심부품인 원자로용기와 제어봉구동장치사이의 동적 상호작용의 영향을 평가하였다. 원자로용기와 제어봉구동장치를 단순 수학모델화하여 단순조화 기저가진에 대한 정상상태 주파수응답을 구하고, 응답을 최소화할 수 있는 설계변수를 제시하였다. 단순 수학모델의 적합성을 입증하기 위하여 원자로용기와 제어봉구동장치의 유한요소 모델에 대하여 ANSYS 코드를 사용하여 해석한 후 정상상태응답을 수학모델로 구한 응답과 비교하였다. 또한 기존설계와 최적화설계에 대하여 지진사고 시간이력해석을 각각 수행함으로써, 본 연구에서 제시한 최적설계변수가 내진설계에 대하여도 적용할 수 있음을 확인하였다.

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Voltage Sags Impact on CAR and SOR of HANARO

  • Kim, Hyung-Kyoo;Jung, Hoan-Sung;Wu, Jong-Sup
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 2004년도 추계학술발표회 발표논문집
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    • pp.657-658
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    • 2004
  • The reactor protection system (RPS) of HANARO is a safety class system. The reactor is tripped by dropping four shut off rods (SOR). The SOR system consists of a SOR, hydraulic pump, hydraulic cylinder, solenoid valves and a power supply unit which has the AC coil contactor as a switching component. The hydraulic pump lifts up the SOR. The SOR drops by loss of the hydraulic pressure in the hydraulic circuit at the occurrence of voltage sags or interruptions. From this experiment, we knew that the magnitude of the voltage sag which impacts on this system is 70V, 500msec. The reactor regulation system (RRS) of HANARO has four CARs which are connected to the driver through a magnetic clutch. The CAR drops by loss of electromagnetic force of the magnetic clutch when the deeper voltage sags to lower than 10V, 500msec.

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연구용원자로에서 수조수관리계통 운전에 따른 수조수 온도 해석 (Analysis on Pool Temperature Variation along Pool Water Management System Operation in Research Reactor)

  • 최정운;이선일;박기정;서경우
    • 대한기계학회논문집 C: 기술과 교육
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    • 제5권2호
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    • pp.135-143
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    • 2017
  • 국내 유일의 연구용원자로인 하나로(Hi-flux Advanced Neutron Application ReactOr)는 다목적으로 중성자를 이용하기 위해 개방형 수조 내 노심이 존재하는 구조이며, 노심에서 발생되는 핵분열 열을 제거하기 위한 일차 냉각계통, 그리고 연결된 유체계통이 구비되어 있다. 원자로 수조 상부 근방에서 진행되는 방사성 작업 시 작업자의 방사능 피폭을 최소화하기 위해 수조고온층계통에 의해 상부에 고온층이 형성되어 있으며, 다소 저온 영역에 있는 방사능 가스 및 이물질이 상부로 올라오는 것을 방지하기 위해 수조수 온도를 $50^{\circ}C$이하로 제한하고 있으며 이를 위해 수조수관리계통이 연결되어 있다. 수조수관리계통의 구비된 판형열교환기의 열용량을 정상운전 조건에서 260 kW가 되도록 설계하여 각 수조에서 발생되는 열원을 제거하는지에 대해 평가하였고, 원자로 운전 모드와 관계없이 정상적으로 유체계통이 운전된다면 각 수조의 수조수 온도는 제한치 이하를 유지하고 있음을 확인하였다.

생물막 담체를 이용한 실험실 규모 $A_{2}O$공법의 시스템 변형에 따른 고도처리 성능 평가에 관한 연구 (The Study on Evaluating Performances of Lab Sacle-Advanced $A_{2}O$ with Changing System Using Biofilm Process)

  • 김민식;강구영
    • 상하수도학회지
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    • 제26권2호
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    • pp.209-218
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    • 2012
  • Recently, as reinforced water quality standards for wastewater has been announced, more efficient and more powerful wastewater treatment processes are required rather than the existing activated sludge process. In order to meet this demands, we evaluate Task 1-4 about lab scale $A_{2}O$ process using biofilm media. Task 1, 2, and 3 use 'Module A' which has 4 partitions (Anoxic/Anerobic/Oxic/Oxic). Task 4 uses 'Module B' which has 2 partitions including a denitrification reactor with an Inclined plug flow reactor (IPFR) and a nitrification reactor with biofilm media. The denitrification reactor of Module B is designed to be upward flow using IPFR. The result of evaluating at each Task has shown that attached growth system has better capacity of removal efficiency for organic matter and nitrogen with the exception of phosphorus. Task 4 which has the most outstanding removal efficiency has 90.5% of $BOD_{5}$ removal efficiency, 97.8% of ${NH_4}^{+}-N$ removal efficiency, 65% of T-N removal efficiency and 92% of T-P removal efficiency with additional chemical phosphorus removal system operated at HRT 9hr, Qi:Qir 1:2, and BOD/T-N ratio 2.7.

충전층 반응기와 고정화 TiO2/UV를 이용한 Rhodamine B의 광촉매 탈색 (Photocatalytic Decolorization of Dye Using Packed-bed Reactor and Immobilized TiO2/UV System)

  • 김동석;박영식
    • 한국환경과학회지
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    • 제16권3호
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    • pp.255-260
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    • 2007
  • The photocatalytic decolorization of Rhodamine B (RhB) was studied using packed-bed reactor and immobilized $TiO_2/UV$ System. The 20 W UV-A, UV-B and UV-C lamps were employed as the light source. The effect of shape and surface polishing extent of reflector, distance between the reactor and reflector, reactor material were investigated. The results showed that the order of the initial reaction constant with reflector shape was round > polygon > W > rhombus. The optimum distance between the reactor and reflector was 2 cm. The initial reaction constant of quartz reactor was 1.46 times higher than that of tile PVDF reactor.

Modeling and Analysis of a Gas Sweeping Process for Polycarbonate Polymerization

  • Kim, Dae-Hyung;Ha, Kyoung-Su;Rhee, Hyun-Ku;Song, Kwnag-Ho
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2001년도 ICCAS
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    • pp.100.3-100
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    • 2001
  • This article deals with the development of a mathematical model for the finishing polycarbonate polymerization process using a horizontal rotating disk-ring reactor with counter-current gas sweeping and the performance analysis of the reactor system by using the model. Here we intend to propose a model describing the reactor system consisting of two phases, in which by-product phenol is removed from the polymer of high molecular weight compatible with the products of commercial grades. The vapor phase is represented by a tanks-ln-series model while the polymer melt phase is regarded as a plug flow reactor.

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