• 제목/요약/키워드: Horizontal Reactor

검색결과 103건 처리시간 0.023초

Reflood Experiments with Horizontal and Vertical Flow Channels

  • Chung, Moon-Ki;Lee, Seung-Hyuck;Park, Choon-Kyung;Lee, Young-Whan
    • Nuclear Engineering and Technology
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    • 제12권3호
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    • pp.153-162
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    • 1980
  • 냉각재상실사고의 재관수 단계중 연료봉 피복재의 온도거동 및 열전달 기구를 파악하는 것은 비상노심냉각계통 및 원자로의 안전성해석에 중요하다. 냉각재유동채널의 방위가 rewetting과정에 미치는 영향을 연구하기 위하여 수직 및 수경 유동채널을 이용한 실험을 수행하였으며, 노심이 수평압력관으로 구성되어 있는 CANDU원자로에 관한 실험을 중점적으로 수행하여 그 결과를 수직채널의 결과와 비교 하였다. 또한 rewetting현상을 육안관찰가기 위해 환상형 테스트부 및 외부에서 가열되는 석영관을 사용하였다. 실험결과로써 수평채널에서의 rewetting 속도는 유동의 층상 현상에 크게 영향을 받으나 그 평균값은 수직채널리 경우와 큰차이없음을 알 수 있었다.

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Dosimetrical Analysis of Reactor Leakage Gamma-rays by Means of Scintillation Spectrometry

  • Jun, Jae-Shik
    • Nuclear Engineering and Technology
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    • 제5권4호
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    • pp.291-309
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    • 1973
  • TRIGA Mark II와 III 원자로의 여러가지 가동조건에 있어서 노벽으로 부터의 누설 ${\gamma}$선에 의한 조사선양률을 3"$\times$3"원통형 NaI(T1) 섬광계수기와 400 channel파 고분석장치로 측정하였는데 측정된 spectrum으로부터 조사선양률을 산출하는데는 실제적면에서 복잡하기 짝이 없는 response matrix 방법대신 정도가 좋으면서도 비교적 그 과정이 단순한 Moriuchi의 specturm -조사선양률 환산 이론을 적용하였다. 연구결과에 따르면 노심에서 발생된 누설 ${\gamma}$선의 기본적인 spectrum 형태는 원자로의 열출력이나 차장벽에 의한 강도의 감쇠에 별로 영향을 받지 않고 있으며 원자로 누설${\gamma}$선에 의란 전조사선양률의 공기중에서의 감쇠는 폭 넓은 energy분포에도 불구하고 지수함수적 감쇠를 하고 있음이 판명되있다. 이 전조사선양률은 원자로의 열출력에 대체로 비례하고 있으나 TRIGA Mark III과 같은 가동형노심의 경우는 측정된 spectrum이 매우 다양한바, 그로부터 산출된 전조사선양률의 크기에는 관계없이, spectrum 분해방법을 적용하여 노심에서 발생된 누설 ${\gamma}$선과 원자로가동중 발생되는 여지 ${\gamma}$선의 기여를 판별 해석하는데 성공하였다.

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INVESTIGATION OF THE CNS HOLE SHAPE AND A PROPOSED INSTALLATION METHOD FOR A VACUUM CHAMBER FOR THE HANARO REACTOR

  • Cho Yeong-Garp;Kim Young-Ki;Lee Kye-Hong;Choung Yun-Hang
    • Nuclear Engineering and Technology
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    • 제38권5호
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    • pp.455-458
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    • 2006
  • The HANARO reactor has a vertical hole for a cold neutron source (CNS) in the heavy-water reflector tank, i.e., the CNS hole, which was considerably deformed during its welding to the horizontal cold neutron (CN) beam tube. This paper presents an investigation of the form of the CNS hole for the optimal design of the a vacuum chamber for the CNS. In addition, the installation method of the vacuum chamber into the CNS hole for minimizing the water thickness between the vacuum chamber and the nose of the CN beam tube is proposed.

화학기상 성장법에 의한 실리콘 부착에 관한 수치해석 (Numerical Analysis of Silicon Deposition in CVD Reactor)

  • 김인;백병준;윤정모;이철로
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2000년도 추계학술대회논문집B
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    • pp.359-364
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    • 2000
  • The fluid flow, heat transfer and the local mass fi-action of chemical species in the chemical vapor deposition(CVD) manufacturing process are numerically studied. The deposition of silicon from dilute silane is hydrogen carrier gas in a horizontal CVD reactor is investigated. The effect of inlet carrier gas velocity, mass fraction of silane, susceptor angle on the deposition thickness and uniformity was represented.

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2-D 반응기를 이용한 선로 하부 토양 내 유류 확산에 관한 연구 (A Study on Oil Diffusion in the Soil under Railroad Track using 2-D Reactor)

  • 강해숙;권태순;정우성;이재영;조영민;전용삼
    • 한국철도학회:학술대회논문집
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    • 한국철도학회 2008년도 추계학술대회 논문집
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    • pp.982-984
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    • 2008
  • Generally, the soil around railroad is contaminated by the leakage of oil during its maintenance or the operation of rolling stock. Because the railroad soil is located under ballast and is hardened with the designated strength due to safety, the characteristics of the polluted site are different. In this study, the phenomena of oil diffusion in the railroad site was investigated using 2-D reactor. The used oil was lubricant. As a result, the maximum diffusion depth of lubricant was about 9.5 cm due to its high viscosity and the hardened soil. The lubricant was diffused by gravity more than by horizontal migration. In the future, these results can be applied to develop a remediation method for the contaminated railroad soil.

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동심축 이중관 구조에서 유동기인진동 특성 고찰 (Investigation of FIV Characteristics on a Coaxial Double-tube Structure)

  • 송기남;김용완;박상철
    • 대한기계학회논문집A
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    • 제33권10호
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    • pp.1108-1118
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    • 2009
  • A Very High Temperature Gas Cooled Reactor (VHTR) has been selected as a high energy heat source of the order of $950^{\circ}C$ for nuclear hydrogen generation, which can produce hydrogen from water or natural gas. A primary hot gas duct (HGD) as a coaxial double-tube type cross vessel is a key component connecting a reactor pressure vessel and an intermediate heat exchanger in the VHTR. In this study, a structural sizing methodology for the primary HGD of the VHTR is suggested in order to modulate a flow-induced vibration (FIV). And as an example, a structural sizing of the horizontal HGD with a coaxial double-tube structure was carried out using the suggested method. These activities include a decision of the geometric dimensions, a selection of the material, and an evaluation of the strength of the coaxial double-tube type cross vessel components. Also in order to compare the FIV characteristics of the proposed design cases, a fluid-structure interaction (FSI) analysis was carried out using the ADINA code.

SMART 유동혼합헤더집합체의 동수력 질량 특성 고찰 (Investigation of Hydrodynamic Mass Characteristic for Flow Mixing Header Assembly in SMART)

  • 이규만;안광현;이강헌;이재선
    • 한국압력기기공학회 논문집
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    • 제16권1호
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    • pp.30-36
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    • 2020
  • In SMART, the flow mixing header assembly (FMHA) is used to mix the coolant flowing into the reactor core to maintain a uniform temperature. The FMHA is designed to have enough stiffness so the resonance with reactor internal structures does not occurs during the pipe break and the seismic accidents. Since the gap between the FMHA and the core support barrel assembly is very narrow compared with the diameter of FMHA, the hydrodynamic mass effect acting on the FMHA is not negligible. Therefore the hydrodynamic mass characteristics on the FMHA are investigated to consider the fluid and structure interaction effects. The result of modal analysis for the dry and underwater conditions, the natural frequency of primary vibration mode for the horizontal direction is reduced from 136.67 Hz to 43.76 Hz. Also the result of frequency response spectrum seismic analysis for the dry and underwater conditions, the maximum equivalent stress are increased from 13.89 MPa to 40.23 MPa. Therefore, reactor internal structures located in underwater condition shall consider carefully the hydrodynamic mass effects even though they have sufficient stiffness required for performing its functions under the dry condition.

Effects of Thermal Contact Resistance on Film Growth Rate in a Horizontal MOCVD Reactor

  • Im Ik-Tae;Choi Nag Jung;Sugiyama Masakazu;Nakano Yoshiyaki;Shimogaki Yukihiro;Kim Byoung Ho;Kim Kwang-Sun
    • Journal of Mechanical Science and Technology
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    • 제19권6호
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    • pp.1338-1346
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    • 2005
  • Effects of thermal contact resistance between heater and susceptor, susceptor and graphite board in a MOCVD reactor on temperature distribution and film growth rate were analyzed. One-dimensional thermal resistance model considering thermal contact resistance and heat transfer area was made up at first to find the temperature drop at the surface of graphite board. This one-dimensional model predicted the temperature drop of 18K at the board surface. Temperature distribution of a reactor wall from the three-dimensional computational fluid dynamics analysis including the gap at the wafer position showed the temperature drop of 20K. Film growth rates of InP and GaAs were predicted using computational fluid dynamics technique with chemical reaction model. Temperature distribution from the three-dimensional heat transfer calculation was used as a thermal boundary condition to the film growth rate simulations. Temperature drop due to the thermal contact resistance affected to the GaAs film growth a little but not to the InP film growth.

On component isolation of conceptual advanced reactors

  • Shrestha, Samyog;Kurt, Efe G.;Prakash, Arun;Irfanoglu, Ayhan
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.2974-2988
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    • 2022
  • Implementation of component isolation in nuclear industry is challenging due to gaps in research and the lack of specific guidelines. In this study, parameters affecting component-level isolation of advanced reactor vessels are identified based on a representative numerical model with explicit consideration of nonlinear soil-structure interaction (SSI). The objective of this study is to evaluate the effectiveness of, and to identify potential limitations of using conventional friction pendulum bearings to seismically isolate vessels. It is found that slender vessels or components are particularly vulnerable to rotational accelerations at the isolation interface, which are caused by rotation of the sub-structure and by excitation of higher modes in the horizontal direction of the seismically isolated system. Component isolation is found to be more effective for relatively stiffer vessels and at sites with stiff soil. Considering that conventional isolators are deficient in resisting axial tension, it is observed that the optimum location for supporting a component to achieve seismic isolation, is at a cross-sectional plane passing through the center of mass of the vessel. These findings are corroborated by numerous simulations of the response of seismically isolated reactor vessels at different nuclear power plant sites subject to a variety of ground motions.

기-액 하이브리드 대기압 플라즈마 반응기 제작 및 특성 분석 (Fabrication and Characterization of Gas-liquid Hybrid Reactor Equipped with Atmospheric Pressure Plasma)

  • 권흥수;이원규
    • Korean Chemical Engineering Research
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    • 제60권3호
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    • pp.452-458
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    • 2022
  • 3가지 종류의 기-액 하이브리드 수평형, 수직형 그리고 needle-to-cylinder형 플라즈마 반응기가 제작되었다. 이들 반응기를 통하여 대기압 플라즈마 방전에서 발생하는 반응 활성종 생성과 전극 내의 전위차를 통한 세정성분의 기-액 활성화 반응을 일으키는 고효율 친환경 기반의 세정 개념을 제시하였다. 세정성능에 대한 효율성을 비교한 결과, needle-to-cylinder형 반응기가 가장 우수한 특성을 가졌다. 본 연구를 통해 기-액 하이브리드 대기압 플라즈마 반응기가 반도체 공정 등 초정밀 세정공정에 응용 가능성이 있음을 확인하였다.