• 제목/요약/키워드: flow reactor

검색결과 1,593건 처리시간 0.028초

Numerical Study on Flow and Heat Transfer in a CVD Reactor with Multiple Wafers

  • Jang, Yeon-Ho;Ko, Dong Kuk;Im, Ik-Tae
    • 반도체디스플레이기술학회지
    • /
    • 제17권4호
    • /
    • pp.91-96
    • /
    • 2018
  • In this study temperature distribution and gas flow inside a planetary type reactor in which a number of satellites on a spinning susceptor were rotating were analyzed using numerical simulation. Effects of flow rates on gas flow and temperature distribution were investigated in order to obtain design parameters. The commercial computational fluid dynamics software CFD-ACE+ was used in this study. The multiple-frame-of-reference was used to solve continuity, momentum and energy conservation equations which governed the transport phenomena inside the reactor. Kinetic theory was used to describe the physical properties of gas mixture. Effects of the rotation speed of the satellites was clearly seen when the inlet flow rate was small. Thickness of the boundary layer affected by the satellites rotation became very thin as the flow rate increased. The temperature field was little affected by the incoming flow rate of precursors.

두 대의 펌프가 병렬로 설치된 장치의 유량 특성 (FLOW CHARACTERISTICS OF A SYSTEM WHICH HAS TWO PARALLEL PUMPS)

  • 박정근;박종호;박용철
    • 한국전산유체공학회지
    • /
    • 제17권4호
    • /
    • pp.1-8
    • /
    • 2012
  • During a reactor normal operation, two parallel 50% capacity cooling pumps circulate primary coolant to remove the fission reaction heat of the reactor through heat exchangers cold by a cooling tower. When one pump is failure, the other pump shall continuously circulate the coolant to remove the residual heat generated by the fuels loaded in the reactor after reactor shutdown. It is necessary to estimate how much flow rate will be supplied to remove the residual heat. We carried out a flow network analysis for the parallel primary pumps based on the piping network of the primary cooling system in HANARO. As result, it is estimated that the flow rate of one pump increased about 1.33 times the rated flow of one pump and was maintained within the limit of the cavitation critical flow.

Moving reactor model for the MULTID components of the system thermal-hydraulic analysis code MARS-KS

  • Hyungjoo Seo;Moon Hee Choi;Sang Wook Park;Geon Woo Kim;Hyoung Kyu Cho;Bub Dong Chung
    • Nuclear Engineering and Technology
    • /
    • 제54권11호
    • /
    • pp.4373-4391
    • /
    • 2022
  • Marine reactor systems experience platform movement, and therefore, the system thermal-hydraulic analysis code needs to reflect the motion effect on the fluid to evaluate reactor safety. A moving reactor model for MARS-KS was developed to simulate the hydrodynamic phenomena in the reactor under motion conditions; however, its applicability does not cover the MULTID component used in multidimensional flow analyses. In this study, a moving reactor model is implemented for the MULTID component to address the importance of multidimensional flow effects under dynamic motion. The concept of the volume connection is generalized to facilitate the handling of the junction of MULTID. Further, the accuracy in calculating the pressure head between volumes is enhanced to precisely evaluate the additional body force. Finally, the Coriolis force is modeled in the momentum equations in an acceleration form. The improvements are verified with conceptual problems; the modified model shows good agreement with the analytical solutions and the computational fluid dynamic (CFD) simulation results. Moreover, a simplified gravity-driven injection is simulated, and the model is validated against a ship flooding experiment. Throughout the verifications and validations, the model showed that the modification was well implemented to determine the capability of multidimensional flow analysis under ocean conditions.

SMART 유동분포시험장치 노심모의기에서의 횡방향 유동 특성 (Cross Flow Characteristics of the Core Simulator in SMART Reactor Flow Distribution Test Facility)

  • 윤정;김영인;정영종;이원재
    • 한국유체기계학회 논문집
    • /
    • 제15권4호
    • /
    • pp.5-11
    • /
    • 2012
  • To identify the flow characteristics of the SMART reactor, a flow distribution model test and a numerical simulation are performed in KAERI. Among several part of the SMART reactor, the fuel assemblies are simulated using simulators because of the complexity. The geometries of the core in the SMART reactor and simulator are different, but some similarities are maintained such as the ratio of pressure drop in the vertical and cross directions. There are cross flow holes in each core simulator to reproduce the cross flow of SMART fuel assemblies. To know the flow characteristics of the cross flow, numerical analysis is performed. As the cross flow area is decreased, the pressure drop between inlet and outlet is decreased. Also, when the flow imbalance between two core simulators is constant, the cross flow area does not significantly affect the cross flow.

중성자 신호이용 원자로 내부 구조물 감시시스템 구성 (Composition of Diagnostic System for Reactor Internal Structures Using Neutron Noise)

  • 박종범;김종봉;박진호
    • 대한전기학회:학술대회논문집
    • /
    • 대한전기학회 2002년도 하계학술대회 논문집 D
    • /
    • pp.2252-2254
    • /
    • 2002
  • The Reactor internal structures which consist of many complex components are subjected to flow-induced vibration due to high temperature and pressure in Reactor coolant system. The above flow-induced vibration causes degradation of structural integrity of the Reactor and may result in loosing mechanical binding component which might impact other equipment and component or cause flow blockage. It is important to analyze reactor noise signal for the early detection of potential problem or failure in order to diagnosis reactor integrity in the point of view of safety and plant economics. Detailed composition of diagnostic system reactor internal structures using neutron noise(RIDS).

  • PDF

다중블록실험과 전산유체해석을 통한 블록형 초고온가스로의 노심우회유량 평가 (ASSESSMENT of CORE BYPASS FLOW IN A PRISMATIC VERY HIGH TEMPERATURE REACTOR BY USING MULTI-BLOCK EXPERIMENT and CFD ANALYSIS)

  • 윤수종;이정훈;김민환;박군철
    • 한국전산유체공학회지
    • /
    • 제16권3호
    • /
    • pp.95-103
    • /
    • 2011
  • In the block type VHTR core, there are inevitable gaps among core blocks for the installation and refueling of the fuel blocks. These gaps are called bypass gap and the bypass flow is defined as a coolant flows through the bypass gap. Distribution of core bypass flow varies according to the reactor operation since the graphite core blocks are deformed by the fast neutron irradiation and thermal expansion. Furthermore, the cross-flow through an interfacial gap between the stacked blocks causes flow mixing between the coolant holes and bypass gap, so that complicated flow distribution occurs in the core. Since the bypass flow affects core thermal margin and reactor efficiency, accurate prediction and evaluation of the core bypass flow are very important. In this regard, experimental and computational studies were carried out to evaluate the core bypass flow distribution. A multi-block experimental apparatus was constructed to measure flow and pressure distribution. Multi-block effect such as cross flow phenomenon was investigated in the experiment. The experimental data were used to validate a CFD model foranalysis of bypass flow characteristics in detail.

안내관 제트유동 억제시의 하나로 원형 조사공의 냉각특성 (The Cooling Characteristics for Circular Irradiation Hole under Suppressing Jet Flow at Guide Tube in HANARO)

  • 우상익;박용철
    • 한국전산유체공학회:학술대회논문집
    • /
    • 한국전산유체공학회 2004년도 춘계 학술대회논문집
    • /
    • pp.208-213
    • /
    • 2004
  • The HANARO, multi-purpose research reactor, 30 MWth open-tank-in- pool type, is under normal operation since it reached the initial critical in February 1995. The HANARO is planning to produce a fission moly-99 of radio isotopes, a mother nuclide of Tc-99m, a medical isotope and is under developing a target handling tool for loading and unloading it in a circular flow tube (OR-5). A guide tube is extended from the reactor core to the top of the reactor chimney for easily un/loading a target under the reactor normal operation. But active coolant through the core can be quickly raised up to the top of the chimney through the guide tube by jet flow. This paper is described an analytical analysis to calculate the hole size of a orifice inserted in the circular irradiation hole and to study the flow characteristics through the guide tube under reactor normal operation and loading the target. As results, the results show that the hole size of orifice was 31 mm of the inner diameter to suppress the guide tube jet flow and the coolant safely cooled the target of fission moly after inserting the orifice to the flow tube.

  • PDF

Semi-batch Jet Loop Reactor에서 연소 배가스중 CO2를 이용한 알칼리 폐수 중화 (Neutralization of Synthetic Alkaline Wastewater with CO2 in a Semi-batch Jet Loop Reactor)

  • 손민기;성호진;이제근
    • 한국연소학회지
    • /
    • 제18권2호
    • /
    • pp.17-22
    • /
    • 2013
  • In this study, we tested the absorption of $CO_2$ in combustion gas into an alkaline wastewater to simultaneously control $CO_2$ and wastewater. During the experiment, we investigated the effects of operating parameters on neutralization characteristics of the wastewater by using $CO_2$ in a bench-scale semi-batch jet loop reactor (0.1 m diameter and 1.0 m in height). The operating parameters investigated in the study are gas flow rate of 1.0-2.0 L/min, liquid recirculation flow rate of 4-32 L/min, and liquid temperature of $20-25^{\circ}C$. It was shown that the initial pH of wastewater rapidly decreased with increased gas flow rate for a given liquid recirculation flow rate. This was due to the increase in the gas holdup and the interfacial area at higher gas flow rate in the reactor. At constant gas flow rate, the time required to neutralize the wastewater initial pH of 10.1 decreased with liquid recirculation flow rate ($Q_L$), reached a minimum value in the range of $Q_L$ = 16-24 L/min, and then increased with further increase in $Q_L$. Further, the time required to neutralize the wastewater was shortened at higher temperatures.

Semi-batch Jet Loop Reactor에서 연소 배가스중 CO2를 이용한 알칼리 폐수 중화 (Neutralization of Synthetic Alkaline Wastewater with CO2 in a Semi-batch Jet Loop Reactor)

  • 손민기;성호진;이제근
    • 한국연소학회지
    • /
    • 제18권3호
    • /
    • pp.38-43
    • /
    • 2013
  • In this study, we tested the absorption of $CO_2$ in combustion gas into an alkaline wastewater to simultaneously control $CO_2$ and wastewater. During the experiment, we investigated the effects of operating parameters on neutralization characteristics of the wastewater by using $CO_2$ in a bench-scale semi-batch jet loop reactor (0.1 m diameter and 1.0 m in height). The operating parameters investigated in the study are gas flow rate of 1.0-2.0 L/min, liquid recirculation flow rate of 4-32 L/min, and liquid temperature of $20-25^{\circ}C$. It was shown that the initial pH of wastewater rapidly decreased with increased gas flow rate for a given liquid recirculation flow rate. This was due to the increase in the gas holdup and the interfacial area at higher gas flow rate in the reactor. At constant gas flow rate, the time required to neutralize the wastewater initial pH of 10.1 decreased with liquid recirculation flow rate ($Q_L$), reached a minimum value in the range of $Q_L$ = 16-24 L/min, and then increased with further increase in $Q_L$. Further, the time required to neutralize the wastewater was shortened at higher temperatures.

Experimental investigation of jet pump performance used for high flow amplification in nuclear applications

  • Vimal Kotak;Anil Pathrose;Samiran Sengupta;Sugilal Gopalkrishnan;Sujay Bhattacharya
    • Nuclear Engineering and Technology
    • /
    • 제55권10호
    • /
    • pp.3549-3558
    • /
    • 2023
  • The jet pump can be used in a test device of a nuclear reactor for high flow amplification as it reduces inlet flow requirement and thereby size of the process components. In the present work, a miniature jet pump was designed to meet high flow amplification greater than 3. Subsequently, experiments were carried out using a test setup for design validation and performance evaluation of the jet pump for different parameters. It was observed that a minimum pressure of 0.6 bar (g) was required for the secondary fluid inside the jet pump to ensure cavitation free performance at high amplification. Spacing between the nozzle tip and the mixing chamber entry point had significant effect on the performance of the jet pump. Variation in primary flow, temperature and area ratio also affected the performance. It was observed that at high flow amplification, the analytical solution differed significantly from experimental results due to very large velocities encountered in the miniature size jet pump.