• 제목/요약/키워드: Core Flow

검색결과 1,171건 처리시간 0.026초

Study on the effect of flow blockage due to rod deformation in QUENCH experiment

  • Gao, Pengcheng;Zhang, Bin;Shan, Jianqiang
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.3154-3165
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    • 2022
  • During a loss-of-coolant accident (LOCA) in the pressurized water reactor (PWR), there is a possibility that high temperature and internal pressure of the fuel rods lead to ballooning of the cladding, which causes a partial blockage of flow area in a subchannel. Such flow blockage would influence the core coolant flow, thus affecting the core heat transfer during a reflooding phase and subsequent severe accident. However, most of the system analysis codes simulate the accident process based on the assumed channel blockage ratio, resulting in the fact that the simulation results are not consistent with the actual situation. This paper integrates the developed core Fuel Rod Thermal-Mechanical Behavior analysis (FRTMB) module into the self-developed severe accident analysis code ISAA. At the same time, the existing flow blockage model is improved to make it possible to simulate the change of flow distribution due to fuel rod deformation. Finally, the ISAA-FRTMB is used to simulate the QUENCH-LOCA-0 experiment to verify the correctness and effectiveness of the improved flow blockage model, and then the effect of clad ballooning on core heat transfer and subsequent parts of core degradation is analyzed.

Mitigation of Flooding under Externally Imposed Oscillatory Gas Flow

  • Lee, Jae-Young;Chang, Jen-Shih
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1995년도 추계학술발표회논문집(1)
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    • pp.475-479
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    • 1995
  • During the hypothetical loss of coolant accident in the nuclear power plant the emergency core cooling water could not penetrate to the reactor core when the steam flow rate from the reactor core exceeds CCFL (Countercurrent flow limitation). The CCFL generated by earlier investigators are developed under the steady gas flow. However the flow instability in the reactor loop could generate oscillatory steam flow, hence their applicability under oscillating flow should be investigated. In this work, an experimental investigation of countercurrent flow in the vertical flow channel has been conducted under oscillatory gas flow. Pulsation of gas under oscillatory flow disturbs the flow pattern significantly and prevents flooding (CCFL) when its minimum value is less than the threshold gas flow rate value.

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종횡비 가 낮은 직각밀폐용기내 의 Prandtl 수 가 큰 유체 의 자연대류 에 관한 실험적 연구 (High prandtl number natural convection in a low-aspect ratio rectangular enclosure)

  • 이진호;황규석;현명택
    • 대한기계학회논문집
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    • 제9권6호
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    • pp.750-756
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    • 1985
  • 본 연구에서는 종횡비 0.1이고 상.하 수평경계면이 단열된 직각밀폐용기내에 서 Pr수가 1보다 큰 물(Pr=6.97, 20.deg. C) 및 실리콘 오일(Pr=1086.42, 20.deg. C)의 양단의 온도차에 의한 자연대류에서 아직 충분히 연구되지 않은 코어형상에 주안점을 두고 실 험적으로 관찰, 조사하였으며 그 결과를 Lee의 이론적인 예측과도 비교, 검토해 보았 다.

대역 공평성 보장을 위한 Core-Stateless 기법 연구 (A Study of Core-Stateless Mechanism for Fair Bandwidth Allocation)

  • 김화숙;김상화;김영부
    • 한국통신학회논문지
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    • 제28권4C호
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    • pp.343-355
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    • 2003
  • 라우터에서 공평 대역 할당은 네트워크 폭주 상황에 반응하여 흐름을 제어하는 트래픽을 그렇지 않은 트래픽으로부터 보호한다. 그러나 Weighted Fair Queueing, Flow Random Early Drop 등의 전통적인 공평 대역 할당 방법은 상태 관리나 버퍼 관리, 스케쥴링 등을 흐름 단위로 수행하므로 초고속 네트워크의 백본에서 사용되는 경우 구현의 복잡성 뿐 아니라 흐름의 증가에 따른 네트위크의 확장성과 견고성을 확보하기 위해 코어 라우터에서의 흐름단위 관리를 배제하는 Core-stateless 메커니즘들이 제안되었다. Core-Stateless Fair Queueing 과 Rainbow Fair Queueing 등은 Core-Stateless 네트워크에서 근접한 공평 대역 할당 메커니즘들에 비해 단순해진 패킷 레이블 할당 방법과 패킷 폐기 방법을 사용하여 실제 구현 가능성을 높인 새로운 Core-stateless 알고리즘인 Simple Layered Fair Queueing (SLFQ) 를 제안하고 몇가지 형태의 시뮬레이션과 그 결과를 다른 메커니즘의 결과와 비교하면서 대역 공평성 보장 정도를 확인한다. 마지막으로 제안된 알고리즘의 향후 응용 가능성을 제시한다.

트러스코어형 샌드위치 판구조물의 진동파워흐름에 관한 연구 (A Study on Vibration Power Flow of Truss Core Type Sandwich Plate Structure)

  • 구경민;김동영;홍도관;박일수;안찬우;한근조
    • 한국정밀공학회:학술대회논문집
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    • 한국정밀공학회 2002년도 추계학술대회 논문집
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    • pp.863-866
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    • 2002
  • In this study, we tried to grasp the characteristic of vibration power flow for the truss core type sandwich plate structure. As the result of the finite element analysis, this paper shows that the vibration power flow characteristic of truss core type sandwich plate structure is understood and the vibration power flow of upper plate according to the mode shape of structure is various. Also it presents the vibration power flow is affected by reinforced structure.

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하나로 원형 조사공의 안내관 유동특성 (Flow Characteristics for Guide Tube of Circular Irradiation Hole in HANARO)

  • 박용철;우종섭
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2004년도 춘계학술대회
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    • pp.1835-1840
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    • 2004
  • The HANARO, a multi-purpose research reactor of 30 MWth, open-tank-in-pool type, has been under normal operation since its initial criticality in February, 1995. The HANARO is composed of inlet plenum, grid plate, core channel with flow tubes and chimney. The reactor core channel is located at about twelve meters (12 m) depth of the reactor pool and cooled by the upward flow that the coolant enters the lower inlet of the plenum,. rises up through the grid plate and the core channel and comes out from the outlet of chimney. 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 a jet flow. This paper describes an analytical analysis that is the study of the flow behavior through the guide tube under reactor normal operation and unloading the target. As results, it was conformed through the analysis results that the guide jet is suppressed under the top of the chimney after modifying the orifice diameter of 37.5 mm to 31 mm.

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Numerical Modeling of Tip Vortex Flow of Marine Propellers

  • Pyo, Sang-woo
    • Journal of Ship and Ocean Technology
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    • 제1권2호
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    • pp.19-30
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    • 1997
  • The accurate prediction of the flow and the pressure distribution near the tip of the blade is crucial in determining the tip vortex cavitation inception which usually occurs on the blade tip or inside the core of the tip vortex just downstream of the blade tip. An improved boundary element method is applied to the prediction of the flow around propeller blades, with emphasis at the tip region. In the method, the Blow adapted grid and a higher order panel method, which combines a hyperboloidal panel geometry with a hi-quadratic dipole distribution, are used in order to accurately model the trailing wake geometry and the highly rolled-up regions in the wake. The method is applied to several propeller geometries and the results have been found to agree well to the existing experimental data. Inviscid flow methods are able to predict the pressures at the tip as well as the shape of the trailing wake. On the other hand, they are unable to determine the flow inside the viscous core of the tip vortex, where cavitation inception often occurs. Thus, a method is presented that treats the flow inside the viscous core. The inner flow is treated with a 2-D Clavier-stokes solution without making any assumptions for axisymmetric flow and conicity of the flow along the tip trajectory. The method can thus allow the treatment of general propeller blade configurations. The velocity and pressure distributions inside the core are shown and compared to those from other numerical methods.

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An Experimental Investigation of Swirl Angle in a Horizontal Round Tube by Flow Visualization Method

  • Tae-Hyun Chang
    • Journal of Advanced Marine Engineering and Technology
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    • 제27권7호
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    • pp.879-888
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    • 2003
  • Swirling air flow in a horizontal round tube was experimentally studied for its visualization. The present investigation deals with swirl angle, flow visualization studies and accompanying vortex core behavior by using oil smoke and a hot wire anemometer for Re = 40,000 and 50000 at X/D = 41, 59 and 71. In the swirl air flow, a vortex core was formed at high swirl intensity along the test tube. The swirl angle and the vortex core depended on the swirl intensity along the test tube. The results of swirl angles measured by flow visualization and hot wire reasonably agree with those of previous studies.

SMART 유동혼합헤더집합체 열혼합 특성 해석 (CFD ANALYSIS FOR THERMAL MIXING CHARACTERISTICS OF A FLOW MIXING HEADER ASSEMBLY OF SMART)

  • 김영인;배영민;정영종;김긍구
    • 한국전산유체공학회지
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    • 제20권1호
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    • pp.84-91
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    • 2015
  • SMART adopts, very unique facility, an FMHA to enhance the thermal and flow mixing capability in abnormal conditions of some steam generators or reactor coolant pumps. The FMHA is important for enhancing thermal mixing of the core inlet flow during a transient and even during accidents, and thus it is essential that the thermal mixing characteristics of flow of the FMHA be understood. Investigations for the mixing characteristics of the FMHA had been performed by using experimental and CFD methods in KAERI. In this study, the temperature distribution at the core inlet region is investigated for several abnormal conditions of steam generators using the commercial code, FLUENT 12. Simulations are carried out with two kinds of FMHA shapes, different mesh resolutions, turbulence models, and steam generator conditions. The CFD results show that the temperature deviation at the core inlet reduces greatly for all turbulence models and steam generator conditions tested here, and the effect of mesh refinement on the temperature distribution at the core inlet is negligible. Even though the uniformity of FMHA outlet hole flow increases the thermal mixing, the temperature deviation at the core inlet is within an acceptable range. We numerically confirmed that the FMHA applied in SMART has an excellent mixing capability and all simulation cases tested here satisfies the design requirement for FMHA thermal mixing capability.

Simplified Technique for 3-Dimensional Core T/H Model in CANDU6 Transient Simulation

  • Lim, J.C.
    • 한국에너지공학회:학술대회논문집
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    • 한국에너지공학회 1995년도 춘계학술발표회 초록집
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    • pp.113-116
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    • 1995
  • Simplified approach has been adopted for the prediction of the thermal behavior of CANDU reactor core during power transients. Based on the assumption that the ratio of mass flow rate for each core channel does not vary during the transient, quasy-steady state analysis technique is applied with predicted core inlet boundary conditions(total mass flow rate and specific enthalpy). For restricted transient case, the presented method shows functionally reasonable estimation of core thermal behavior which could be implemented in the fast running reactor simulation program.

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