• 제목/요약/키워드: Fuel assembly

검색결과 663건 처리시간 0.05초

수치해석을 이용한 마스트집합체 내 핵연료 집합체의 열수력적 안전성 연구 (Numerical study on the thermal-hydraulic safety of the fuel assembly in the Mast assembly)

  • 김영수;윤병조;김휘융;전재영
    • 에너지공학
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    • 제24권1호
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    • pp.149-163
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    • 2015
  • 본 연구에서는 전산유체역학(Computational Fluid Dynamics, CFD) 해석코드를 사용하여 마스트집합체의 열수력적 안전성에 대한 연구를 수행하였다. 이를 위해 자연대류 벤치마크 문제를 선정하여 CFD 코드의 물리모델을 선정 및 해석 능력을 검증하고 이를 이용하여 마스트집합체에 대한 자연대류 열전달 해석을 수행하였다. 본 연구에서는 Betts et al.의 사각 수직공동에서 난류 자연대류 실험결과를 대상으로 CFD 해석을 수행하여 자연대류 조건에 적용하기 위한 난류 모델로 표준 $k-{\omega}$ 모델을 선정하였다. 이렇게 도출된 난류모델을 CFD코드에 적용하여 Bates et al.에 의해 수행된 PNL(Pacific Northwest Laboratory)의 $2{\times}6$ 번들 실험과 이에 대한 Kwon et al.의 MATRA, Fluent 코드의 해석과 비교 계산을 수행하여 CFD코드의 부수로조건 자연대류 열전달 해석 능력을 검증하였다. 최종적으로 도출된 $k-{\omega}$ 난류 모델을 사용하여 마스트집합체 및 핵연료 집합체에 대한 자연대류 해석을 수행하였다. 해석 결과 수조 내부 및 부수로 내에서 안정적인 자연대류 유동이 발생함을 확인하였으며, 본 유동 조건에서 핵비등이탈비를 계산함으로써 열수력적 안전성을 정량적으로 평가하였다.

핵 연료봉 표면보호를 위한 수용성 건식 윤활제 개발 (Development of a Water-soluble Dry Lubricant for Nuclear Fuel Rod Protection)

  • 정근우;김영운;이상봉;홍종승;한상재;오명호
    • Tribology and Lubricants
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    • 제30권6호
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    • pp.343-349
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    • 2014
  • Currently, in order to resist the scratching of the fuel rod surface while fabricating the fuel assembly of the light-water nuclear reactor, we use a solution of nitrocellulose, an explosive material, as a dry lubricant along with its solvent. However, the demand for developing safe and harmless aqueous alternative materials for environment-conservation and field-worker safety has increased. In this study, we demonstrate the preparation of a novel aqueous resin composite using a formulation of aqueous polymeric resin, alcoholic solvent, and water. Subsequently, we characterize this composite on the basis of hardness, adhesive property, and water solubility using plates similar to the fuel rod material. The insertion test of a fuel rod coated with the YS-3 composite shows load values of $18.8-20.5kg/cm^2$, which is comparable with $18.8-20.5kg/cm^2$ of the nitrocellulose coating agent. In addition, the depth and width of longitudinal scratches caused by the YS-3 composite test are 50% higher than those of the standard. We can develop a harmless and safe aqueous dry lubricant to replace the existing NC products through field testing of 264 pieces of fuel rods, after producing 350 kg of the YS-3 prototype. The scratch test for the rod surface showed that weight of chip of YS-3 prototype was smaller than that of NC before and after solvent treatment, indicating the properties of YS-3 prototype was comparable to the counterpart.

경수로 연료용 지르칼로이-4 지지격자의 레이저용접부 조사 (Investigation of the Laser Welded Specimens of Zircaloy-4 Spacer Grids for PWR Fuel Assembly)

  • 김수성;송기남;윤경호;이강희
    • 대한용접접합학회:학술대회논문집
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    • 대한용접접합학회 2006년도 춘계 학술대회 개요집
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    • pp.39-41
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    • 2006
  • The weld quality of spacer grids in Pressurized Water Reactors(PWR) fuel is extremely important for the fuel assembly performance in the nuclear renter. The spacer grid welds are currently evaluated mainly by the metallographic examination although it reveals only cross-points which are welded by the laser beam. This experiment is also to compare the weldability of Zircaloy-4 spacer grids using by the GTA and laser beam. The effect of node geometries of spacer grids for GTAW and LBW has been studied and optimum conditions of spacer grid welding have been found. Microstructures and micro-hardness of GTA and laser beam welded zones have been also compared.

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An Experimental Study of Pressure Drop Correlations for Wire-Wrapped Fuel Assemblies

  • Chun, Moon-Hyun;Seo, Kyong-Won;Park, Seok-Ki;Nam, Ho-Yun
    • Journal of Mechanical Science and Technology
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    • 제15권3호
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    • pp.403-409
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    • 2001
  • The main objective of the present study is to perform an experimental evaluation of five existing correlations for the subchannel pressure drop analysis of a wire-wrapped fuel assembly. For this purpose, a series of water experiments have been performed using a helical wire-wrapped 19-pin fuel assembly for various test parameters. Four different test sections with different pitch to rod diameter ratios (P/D) and wire lead length to rod diameter ratios (H/D) have been fabricated. A series of pressure drop measurements were made to obtain friction factors for these four test sections. The new data along with existing data are used to evaluate existing correlations. Both the original and the simplified Cheng and Todreas correlations give the best agreement with experimental data for all flow regions.

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노내시험부 내부집합체에 대한 유체유발진동특성 (Characteristics of flow-induced vibration for inner assembly of in-pile test section)

  • 이한희;이종민;이정영
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2006년도 춘계학술대회논문집
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    • pp.250-253
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    • 2006
  • The in-pile Section (IPS) is subjected to flow-induced vibration(FIV) due to the flow of the primary coolant and then the structural integrity. The in-pile Section (IPS) of 3-pin Fuel Test Loop(FTL) shall be installed in the vortical hole call IR1 of HANARO reactor core. In order to verify the velocity and displacement both the inside region of IPS at the annular region of IPS, the vibration was measured by varing the flow rate on both regions. The displacements of fuel assembly in the in-pile Section (IPS) were found to be lower than the values of allowable design criteria.

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KALIMER 원자로 핵연료 교환기의 메커니즘 모델링 및 구조해석 (Mechanism Modeling and Structural Analysis of the Fuel Handling Machine in KALIMER Reactor)

  • 김석훈;이재한
    • 한국전산구조공학회:학술대회논문집
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    • 한국전산구조공학회 2002년도 가을 학술발표회 논문집
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    • pp.131-138
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    • 2002
  • The fuel handling machine handles the core assembly in refueling period of the reactor, it is necessary to predict the motion and structural integrity of it. The kinetic analysis of the fuel handling machine was carried out for the refueling motion. The reaction forces at the joints of machine were calculated with IDEAS code considering the weight of the machine and the loading force of the core assembly, Also, the structural analysis for the machine modeled by lumped-mass and beam elements was performed by using ANSYS code. The stresses and deformations were calculated for the equivalent static force based on the kinetic analysis and the seismic loads. The calculated displacements and stresses are quite low compared with allowable limits.

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고분자전해질형 연료전지의 성능해석 및 효율에 관한 연구 (TA Study on the Performance and the Efficiency in Polymer Electrolyte embrane Fuel Cell)

  • 김홍건;김유신;양성모;나석찬
    • 한국공작기계학회논문집
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    • 제14권4호
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    • pp.75-80
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    • 2005
  • An experimental study is carried out to investigate the performance and the efficiency humidifying Membrane Electrolyte Assembly and having the double-tied catalyst layers in a fuel cell system which is taken into account the physical and thermal concept. Subsequently, an electric output produced by PEMFC(Polymer Electrolyte Membrane Fuel Cell) is measured to assess the performance of a stack, and the efficiency is also evaluated according to the different situation in which unit cell is placed with and without the humidification of the MEA. It is found that the measured values of stack voltage and current are influenced by the stack temperature, humidification, and the double-tied catalyst layers which give more enhanced values to be applied to electric units.

디젤 차량용 통합 연료히터와 시험챔버 구현 (Implementation of Composited Fuel Heater and Test Chamber for Diesel Cars)

  • 윤달환
    • 한국산학기술학회논문지
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    • 제14권5호
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    • pp.2375-2380
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    • 2013
  • 본 연구에서는 디젤 차량용 통합형 연료히터 및 성능검사 시스템을 구현한다. 센서와 히터가 분리된 연료히터를 히터내에 센서를 안착시켜 통합함으로써 일체형 통합히터를 개발하고 성능평가시험 시스템 개발을 통하여 시험한다. 디젤 차량은 겨울철 저온환경의 영향을 받아 엔진이 냉각될 경우 일정한 온도 이하로 내려가면 파라핀과 같은 반고체 상태인 왁싱(Waxing)물질을 형성하여 엔진시동이 잘 걸리지 않게 하는 원인이 된다. 이러한 저온시동성을 지원하기 위해 연료히터를 사용하며, 연료히터의 성능을 평가하는 시험챔버가 필요하다. 시험챔버에서 연료히터의 성능검사 항목으로 상온, 극저온, 극고온에서의 동작검사, 시험저항 설정에 따른 저항동작지연시간 및 전류동작지연시간, 온도변화에 따른 바이메탈 지연시간 검사, 블록히터의 전류 및 저항 검사, 히팅 운전검사 등을 수행한다. 이때 연료히터의 시험평가 및 평가 알고리즘을 제시한다.

Shape Optimization of the H-shape Spacer Grid Spring Structure

  • Yoon, Kyung-Ho;Kim, Hyung-Kyu;Kang, Heung-Seok;Song, Kee-Nam;Park, Ki-Jong
    • Nuclear Engineering and Technology
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    • 제33권5호
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    • pp.547-555
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    • 2001
  • In pressurized light water reactor fuel assembly, spacer grids support nuclear fuel rods both laterally and vertically. The fuel rods are supported by spacer grid springs and grid dimples that are located in the grid cell. The support system allows for some thermal expansion and imbalance of the fuel rods. The imbalance is absorbed by elastic energy to prevent coolant flow- induced vibration damage. Design requirements are defined and a design process is established. The design process includes mathematical optimization as well as practical design method. The shape of the grid spring is designed to maintain its function during the lifetime of the fuel assembly. A structural optimization method is employed for the shape design. Since the optimization is carried out in the linear range of finite element analysis, the optimum solution is verified by nonlinear analysis. A good design is found and the final design is compared with the initial conceptual design. Commercial codes are utilized for structural analysis and optimization.

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KSLV-I 조립콤플렉스 시스템 설계 (KSLV-I Assembly Complex System Design)

  • 진승보;박정주
    • 시스템엔지니어링학술지
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    • 제2권1호
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    • pp.37-41
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    • 2006
  • The KSLV-I satellite launch vehicle will be launched in a space center currently under construction. The Space Center which is an advance post base of space development of Korea is located on Oenaro island in Kohung, South Cholla Province. A Ground Complex of the Space Center consists of an AC(Assembly Complex), a LC(Launch Complex), and a MCC(Mission Control Center). Assembly and test facilities are located in the AC in which stage assembly, integrated assembly, check-up, certification test, and pre-launch test are made effectively. A launch pad, fuel supply facilities, a launch control center and associated supporting facilities are located in the LC, and the MCC has control over the space center. These ground complex facilities have diverse forms of an interface with mechanical device, electric device, and etc. These should also provide optimum condition and performance during launch operation processes of the launch vehicle. This paper introduces the result of R&D for the AC of the ground complex performed during system design period.

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