• 제목/요약/키워드: Coolant Circulation

검색결과 74건 처리시간 0.025초

열파이프가 부착된 평판형 태양열 집열기의 열전달 특성에 대한 실험적 고찰 (An Experimental Study on the Heat Transfer Characteristics for a Flat Plate Solar Collector with a Heat Pipe)

  • 김철주;임광빈
    • 대한기계학회논문집
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    • 제17권5호
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    • pp.1237-1245
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    • 1993
  • 본 연구에서는 그 동안 본 실험실에서 태양열 집열기용으로 개발한 에탄올 열파이프를 집열판에 설치하여 집열기 모델을 설계 제작하였다. 그리고 실제 태양 복사하에서 집열기의 집열과 열이송과정에 대한 특성을 검토함으로써 열파이프의 적 응성을 확인하였다. 특히 열파이프의 시동 및 작동상태, 집열판내의 열유동과정 그리고 집열기의 집열효율에 관하여 고찰하였다.

SBLOCA AND LOFW EXPERIMENTS IN A SCALED-DOWN IET FACILITY OF REX-10 REACTOR

  • Lee, Yeon-Gun;Park, Il-Woong;Park, Goon-Cherl
    • Nuclear Engineering and Technology
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    • 제45권3호
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    • pp.347-360
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    • 2013
  • This paper presents an experimental investigation of the small-break loss-of-coolant accident (SBLOCA) and the loss-of-feedwater accident (LOFW) in a scaled integral test facility of REX-10. REX-10 is a small integral-type PWR in which the coolant flow is driven by natural circulation, and the RCS is pressurized by the steam-gas pressurizer. The postulated accidents of REX-10 include the system depressurization initiated by the break of a nitrogen injection line connected to the steam-gas pressurizer and the complete loss of normal feedwater flow by the malfunction of control systems. The integral effect tests on SBLOCA and LOFW are conducted at the REX-10 Test Facility (RTF), a full-height full-pressure facility with reduced power by 1/50. The SBLOCA experiment is initiated by opening a flow passage out of the pressurizer vessel, and the LOFW experiment begins with the termination of the feedwater supply into the helical-coil steam generator. The experimental results reveal that the RTF can assure sufficient cooldown capability with the simulated PRHRS flow during these DBAs. In particular, the RTF exhibits faster pressurization during the LOFW test when employing the steam-gas pressurizer than the steam pressurizer. This experimental study can provide unique data to validate the thermal-hydraulic analysis code for REX-10.

Development and validation of transient analysis module in nodal diffusion code RAST-V with Kalinin-3 coolant transient benchmark

  • Jaerim Jang;Deokjung Lee
    • Nuclear Engineering and Technology
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    • 제56권6호
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    • pp.2163-2173
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    • 2024
  • This study introduces a transient analysis module developed for RAST-V and validates it using the Kalinin-3 benchmark problem. For the benchmark analysis, RAST-V standalone and STREAM/RAST-V calculations were performed. STREAM supplies the few-group constants and RAST-V conducts a 3D core simulation utilizing few-group cross-sectional data. To improve accuracy, the main solver was developed based on the advanced semi-analytic nodal method. To evaluate the computational capability of the transient analysis module in RAST-V, Kalinin-3 benchmark is employed. Kalinin-3 represents a coolant transient benchmark that offers experimental data during the deactivation of the Main Circulation Pumps. Consequently, the transient calculations reflected the changes in the reactor flow rate. Benchmark comprising steady-state and transient calculations. During the steady state, the STREAM/RAST-V combination demonstrated a 30 ppm root mean square difference from 0 to 128.50 EFPD. For the transient calculations, STREAM/RAST-V showed power differences within ±7 % over a range of 0-300 s. Axial offset differences were within ±3 %, and the RMS difference in radial power ranged within 2.596 % at both 0 and 300 s. Overall, this study effectively demonstrated the newly developed transient solver in RAST-V and validated it using the Kalinin-3 benchmark problem.

액체금속 피동냉각유동모사 실증설비의 개발 (Development of Liquid Metal Passive Cooling Flow Simulation System)

  • 류경하;김재형;이태현;이상혁;반병민
    • 대한기계학회논문집 C: 기술과 교육
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    • 제3권4호
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    • pp.257-264
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    • 2015
  • 원자력 발전이 중요한 에너지 공급역할을 담당하기 위해서는 안전성을 확보하고, 사용 후 핵연료 문제를 해결하여야 한다. 이와 같은 문제를 해결하기 위한 방안으로 소듐이나 납비스무스 공융합금 등과 같은 액체금속을 냉각재로 이용하는 방안이 연구되고 있다. 본 논문에서는 액체금속 유동모사 실증 설비 개발을 위한 설계변수 검토, 설계 해석, 구조재의 선정 및 설비 개발 결과를 서술하였다. 설비의 개발은 열수력 해석코드의 해석을 통해 수행되었고 충분한 자연순환 유량을 갖는 설비제작 기술을 확보하였다.

Study on the influence of flow blockage in severe accident scenario of CAP1400 reactor

  • Pengcheng Gao;Bin Zhang ;Jishen Li ;Fan Miao ;Shaowei Tang ;Sheng Cao;Hao Yang ;Jianqiang Shan
    • Nuclear Engineering and Technology
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    • 제55권3호
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    • pp.999-1008
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    • 2023
  • Deformed fuel rods can cause a partial blockage of the flow area in a subchannel. Such flow blockage will influence the core coolant flow and further the core heat transfer during the reflooding phase and subsequent severe accidents. Nevertheless, most of the system analysis codes simulate the accident process based on the assumed flow blockage ratio, resulting in inconsistencies between simulated results and actual conditions. This paper aims to study the influence of flow blockage in severe accident scenario of the CAP1400 reactor. First, the flow blockage model of ISAA code is improved based on the FRTMB module. Then, the ISAA-FRTMB coupling system is adopted to model and calculate the QUENCH-LOCA-0 experiment. The correctness and validity of the flow blockage model are verified by comparing the peak cladding temperature. Finally, the DVI Line-SBLOCA accident is induced to analyze the influence of flow blockage on subsequent CAP1400 reactor core heat transfer and core degradation. From the results of the DVI Line-SBLOCA accident analysis, it can be concluded that the blockage ratio is in the range of 40%-60%, and the position of severe blockage is the same as that of cladding rupture. The blockage reduces the circulation area of the core coolant, which in turn impacts the heat exchange between the core and the coolant, leading to the early failure and collapse of some core assemblies and accelerating the core degradation process.

열을 발생하는 Debris층에서의 강제대류 Dryout 열유속 (Forced Flow Dryout Heat Flux in Heat Generating Debris Bed)

  • Cha, Jong-Hee;Chung, Moon-Ki
    • Nuclear Engineering and Technology
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    • 제18권4호
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    • pp.273-280
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    • 1986
  • 이 연구의 목적은 가혹한 사고후 손상된 원자로심을 모의한 열을 발생하는 데브리층에서의 강제대류 드라이아웃 열유속을 실험적으로 얻고져 한 것이다. 이 연구에서 냉각재 순환장치를 사용하여 대기압하에서 냉각재가 상향 강제대류하는 유도 가열된 강구 입자층에서의 드라이아웃 열유속을 얻었다. 이 실험에서는 주로 강제대류 드라이아웃에 대한 질량유속.입자크기.입자층의 높이 및 냉각재의 서브클링의 영향이 관찰되었다. 실험은 입자직경이 1.5, 2.5, 3.0 및 4.0mm의 탄소강입자를 55mm 내경의 Pyrex 유리용기에 넣어 고주파유도 전류를 통해 가열하여 이루어졌다. 냉각재로서 증류수를 질량유속 0~3.5kg/$m^2$s로 변화시키어 공금하고 층의 높이는 55mm와 110mm, 냉각재 유입온도는 2$0^{\circ}C$와 8$0^{\circ}C$로 변화시켰다. 주요 실험결과는 다음과 같다. (1) 드라이아웃 열유속은 상향 강제 대류 질량유속과 입자크기내의 증가에 따라 증가한다. (2) 질량유속이 없는 경우 드라이아웃 열유속은 기존 연구결과와 같이 입자직경에 의존한다. (3) 얕은 입자층에서의 드라이아웃 열유속은 깊은 입자층의 것보다 얼마간 높다.

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Comparison on Safety Features among HTGR's Reactor Cavity Cooling Systems (RCCSs)

  • Kuniyoshi Takamatsu;Shumpei Funatani
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.832-845
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    • 2024
  • Reactor cavity cooling systems (RCCSs) comprising passive safety features use the atmosphere as a coolant, which cannot be lost. However, their drawback is that they are easily affected by atmospheric disturbances. To realize the commercial application of the two types of passive RCCSs, namely RCCSs based on atmospheric radiation and atmospheric natural circulation, their safety must be evaluated, that is, they must be able to remove heat from the reactor pressure vessel (RPV) surface at all times and under any condition other than under normal operating conditions. These include both expected and unexpected natural phenomena and accidents. Moreover, they must be able to eliminate the heat leakage emitted from the RPV surface during normal operation. However, utilizing all of the heat emitted from the RPV surface increases the degree of waste heat utilization. This study aims to understand the characteristics and degree of passive safety features for heat removal by comparing RCCSs based on atmospheric radiation and atmospheric natural circulation under the same conditions. It was concluded that the proposed RCCS based on atmospheric radiation has an advantage in that the temperature of the RPV could be stably maintained against disturbances in the ambient air.

마그네슘합금 판재의 온간 디프 드로잉성에 관한 연구 (A Study on the Warm Deep Drawability of Mg- Alloy Sheet Metal)

  • 이용길;김종호;이종섭
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2003년도 추계학술대회논문집
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    • pp.117-120
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    • 2003
  • Warm deep drawing which is one of the new forming technologies to improve formability of sheet metal is applied to the cylindrical cup drawing of Mg-alloy sheet metal. In experiments the temperature of die and blank holder is varied from room temperature to $300^{\circ}C$, while the punch is cooled by circulation of coolant to increase the fracture strength of workpiece on the punch corner area. Test material chosen for experiments is AZ31 magnesium sheet metal. Teflon film as a lubricant is used on both sides of a workpiece. The limit drawing ratio as well as thickness distributions of drawn cups are investigated and validity of warm deep drawing process is also discussed.

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액화질소를 이용한 고정도 하드 터닝 (Precision Hard Turning with Cryogenic Cooling)

  • 박영우;김기수
    • 한국정밀공학회:학술대회논문집
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    • 한국정밀공학회 2001년도 춘계학술대회 논문집
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    • pp.1048-1051
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    • 2001
  • This paper presents an analytical and experimental study of a cryogenic machining for precision hard turning. A cryogenic circulation system is designed and mounted on the top of the tool insert. The machining process used is facing operation on a CNC turning center with dry and cryogenic conditions. The tool temperature and cutting forces are measured by the K-type thermocouple and by a three-component Kistler dynamometer, respectively. Both data are fed into the data acquisition program through an A/D card. Surface roughness and form accuracy of the machined surface are measured by WYKO NT2000. It is also found that surface roughness and form accuracy with cryogenic cooling are better than those with no coolant.

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윤활-구조물 연계해석을 이용한 왕복동형 압축기의 피스톤 거동해석 (Coupled Oil-Structure Analysis for Piston Motion in Reciprocating Compressors)

  • 문승주;조진래;류성헌
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 춘계학술대회
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    • pp.513-518
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    • 2003
  • The piston slap phenomenon is one of the major noise source of reciprocating compressors used in household electric appliances. In response to public demand, strict regulations are increasingly being imposed on the allowable noise level which is caused mostly by household electric appliances. In this paper, the dynamic behavior of suction and discharge valves are analytically calculated and the lubricant behavior between piston and cylinder are investigated using two-dimensional Reynolds equation. And the piston slap caused by the piston secondary motion is investigated by the finite element method.

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