• 제목/요약/키워드: Thermal Phenomena

검색결과 727건 처리시간 0.036초

다공성 매질 접근법을 적용한 하이브리드 로켓 N2O 촉매 점화기의 열적 현상 (Thermal Phenomena of an N2O Catalyst Bed for Hybrid Rockets Using a Porous Medium Approach)

  • 유우준;김수종;김진곤;장석필
    • 한국항공우주학회지
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    • 제34권9호
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    • pp.89-96
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    • 2006
  • 본 연구에서는 소형 위성용 하이브리드 로켓 점화장치에 적용되는 N2O 촉매 베드의 유동 및 열적 현상에 대한 이론적인 고찰을 하였다. 허니콤 형상을 가지는 촉매 베드 내의 열적 현상을 분석하기 위해서 다공성 매질 접근법을 사용하였다. 유동장은 Brinkman- extended Darcy 모델을 사용하였고, 온도장은 One-equation 모델을 사용하여 촉매 베드 내에서 유동장 및 온도장에 대한 해석해들을 구하였다. 다공성 매질 접근법을 적용한 모델의 해석해와 기존 실험결과를 비교하여 본 모델의 정확성을 검증하였다. 해석해에 근거하여 N2O 촉매 베드에 영향을 미치는 중요한 변수들이 촉매 베드의 기공률, 유효 체적비, 촉매 베드와 기공의 직경비, 공급열, 그리고 펌핑파워임을 확인하였으며 촉매 베드 내에서의 열적현상에 대한 중요 변수들의 효과를 연구하였다.

RELAP5/MOD2 코드에 의한 대형냉각재 상실사고 모사실험 L2-3의 열수력 현상 예측 (Prediction of Thermal-Hydraulic Phenomena in the LBLOCA Experiment L2-3 Using RELAP5/MOD2)

  • Bang, Young-Seok;Chung, Bub-Dong;Kim, Hho-Jung
    • Nuclear Engineering and Technology
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    • 제23권1호
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    • pp.56-65
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    • 1991
  • RELAP5/MOD2 Cycle 36.04코드를 이용하여 LOFT대형냉각재 상실사고 모사실험 L2-3를 계산함으로써 코드의 대형냉각재상실사고에 관련된 열수력현상 예측능력을 평가하였다. 기본계산에서 원자로 압력용기는 이중노심유로와 분리강수관 모델로 모사되었다. 기본계산의 결과 계통의 전반적인 수력학적 거동과 감압기간동안 노심 고출력 부위에서의 열적 거동은 비교적 타당하게 예측되었다. 한편 과냉각-이상유동의 천이 기간동안 임계유량모델, 고질량유속에서의 임계열유속 상관식, 감압기간중의 재접수(Blowdown Rewet)의 판정기준등 코드의 모델/상관식의 부분적 결함이 발견되었다. 이 결함들에 의해 냉각재 재고량이 과대 평가되어 재환수기간의 노심의 열적거동 예측의 정확도가 감소되었다. RELAP5/MOD2 Cycle 36.04로 부터 개선된 코드를 사용한 계산 결과 재접수 현상의 예측 정확도를 개선할 수 있었다.

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$C_{22}$-quinolium(TCNQ) LB막의 고전게 전기전도 현상 (Electrical conduction phenomena of $C_{22}$--quinolium(TCNQ) langmuir-blodgett films under the high-electric field)

  • 신동명;김태완;홍언식;송일식;유덕선;강도열
    • E2M - 전기 전자와 첨단 소재
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    • 제7권2호
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    • pp.138-144
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    • 1994
  • Electrical conduction phenomena of $C_{22}$-quinolium(TCNQ) Langmuir- Blodgett(LB) films are reported through a study of current-voltage(I-V) characteristics along a perpendicular direction. The I-V characteristics were investigated by applying a step or a pulse voltage to the specimen as well as changing temperatures in the range of 20-250[.deg. C] It show an ohmic behavior in low-electric field, and a nonohmic behavior in high-electric field. This nonohmic behavior has been interpreted in terms of a conduction mechanism of space-charge limited current and Schottky effect. When the electric field is near the strength of 10$_{6}$ V/cm, there occur anomalous phenomena similar to breakdown. When step or pulse voltage is applied, the breakdown voltage shifts to the higher one as the step or pulse time width becomes shorter. To see the influence of temperature, current was measured as a function of temperature under the several bias voltages, which are lower than that of breakdown. It shows that the current increases to about 103 times near 60-70[.deg. C], and remains constant for a while up to around 150[.deg. C] and then suddenly drops. We have also performed a DSC(differential scanning calorimetry) measurement with $C_{22}$-quinolium(TCNQ) powder in the range of 30-300[.deg. C]. These results imply that the anomalous phenomena occuring in the high electric field are caused by the electrical and internal thermal effect such as a joule heating.ating.

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350MW급 화력 발전소 증기터빈의 오일 휩 현상 및 대책 (Oil Whip Phenomena and Countermeasure on Steam Turbine in 350MW Load Thermal Power Plant)

  • 구재량;김연환;배용채;김계연
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2001년도 추계학술대회논문집 II
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    • pp.1015-1019
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    • 2001
  • There are several bearing systems at the large steam-turbines in thermal power plant. The bearing system is one of the most important parts of rotating machinery. The steam turbine vibrations mainly depend on the bearing oil and the shaft alignment condition. This paper describes on the steam turbine abnormal vibration due to the oil whip in terms of the shaft alignment in the thermal power plant.

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Experimental assessment of thermal radiation effects on containment atmospheres with varying steam content

  • R. Kapulla;S. Paranjape;U. Doll;E. Kirkby;D. Paladino
    • Nuclear Engineering and Technology
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    • 제54권11호
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    • pp.4348-4358
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    • 2022
  • The thermal-hydraulics phenomena in a containment during an accident will necessarily include radiative heat transfer (i) within the gas mixture due to the high radiative absorption and emission of steam and (ii) between the gas mixture and the surrounding structures. The analysis of some previous PANDA experiments (PSI, Switzerland) demonstrated the importance of the proper modelling of radiation for the benefit of numerical simulations. These results together with dedicated scoping calculations conducted for the present experiments indicated that the radiative heat transfer is considerable, even for a very low amount of steam (≈2%). The H2P2 series conducted in the large-scale PANDA facility at the Paul-Scherrer-Institut (PSI) in the framework of the OECD/NEA HYMERES-2 project is intended to enhance the understanding of thermal radiation phenomena and to provide a benchmark for corresponding numerical simulations. Thus, the test matrix was tailored around the two opposite extremes: either gas compositions with small steam content such that radiative heat transfer phenomena can be neglected. Or gas mixtures containing larger amounts of steam, so that radiative heat transfer is expected to play a dominant role. The H2P2 series consists of 5 experiments designed to isolate the radiation phenomena from convective and diffusive effects as much as possible. One vessel with a diameter of 4 m and a height of 8 m was preconditioned with different mixtures of air / steam at room and elevated temperatures. This was followed by the build-up of a stable helium stratification at constant pressure in the upper part of the vessel. After that, helium was injected from the top into the vessel which leads to an increase of the vessel pressure and a corresponding elevation-dependent and transient rise of the gas temperature. It is shown that even the addition of small amounts of steam in the initial gas atmosphere considerably impacts the radiative heat transport throughout all phases of the experiments and markedly influences i) the monitored gas peak temperature, ii) the temperature history during the compression and iii) the following relaxation phase after the compression was stopped. These PANDA experiments are the first of its kind conducted in a large scale thermal-hydraulic facility.

압전적층판의 열-압전-탄성 동적 비선형 작동특성 (Thermopiezoelastic Nonlinear Dynamic Characteristics of Piezolaminated Plates)

  • 오일권
    • 한국소음진동공학회논문집
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    • 제15권7호
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    • pp.836-842
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    • 2005
  • Nonlinear dynamic characteristics of active piezolaminated plates are investigated with respect to the thermopiezoelastic behaviors. For largely deformed structures with small strain, the incremental total Lagrangian formulation is presented based on the virtual work principles. A multi-field layer-wise finite shell element is proposed for assuring high accuracy and non-linearity of displacement, electric and thermal fields. For dynamic consideration of thermopiezoelastic snap-through phenomena, the implicit Newmark's scheme with the Newton-Raphson iteration is implemented for the transient response of various piezolaminated models with symmetric or eccentric active layers. The bifurcate thermal buckling of symmetric structural models is first investigated and the characteristics of piezoelectric active responses are studied for finding snap-through piezoelectric potentials and the load-path tracking map. The thermoelastic stable and unstable postbuckling, thermopiezoelastic snap-through phenomena with several attractors are proved using the nonlinear time responses for various initial conditions and damping loss factors. Present results show that thermopiezoelastic snap-through phenomena can result in the difficulty of buckling and postbuckling control of intelligent structures.

Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform

  • Kim, Kyung Mo;Bang, In Cheol
    • Nuclear Engineering and Technology
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    • 제53권3호
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    • pp.776-792
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    • 2021
  • Conventional integral effect test facilities were constructed to enable the precise observation of thermal-hydraulic phenomena and reactor behaviors under postulated accident conditions to prove reactor safety. Although these facilities improved the understanding of thermal-hydraulic phenomena and reactor safety, applications of new technologies and their performance tests have been limited owing to the cost and large scale of the facilities. Various nuclear technologies converging 4th industrial revolution technologies such as artificial intelligence, drone, and 3D printing, are being developed to improve plant management strategies. Additionally, new conceptual passive safety systems are being developed to enhance reactor safety. A new integral effect test facility having a noticeable scaling ratio, i.e., the (UNIST reactor innovation loop (URI-LO), is designed and constructed to improve the technical quality of these technologies by performance and feasibility tests. In particular, the URI-LO, which is constructed using a transparent material, enables better visualization and provides physical insights on multidimensional phenomena inside the reactor system. The facility design based on three-level approach is qualitatively validated with preliminary analyses, and its functionality as a test facility is confirmed through a series of experiments. The design feature, design validation, functionality test, and future utilization of the URI-LO are introduced.

CORQUENCH 코드를 활용한 중수로 calandria vault에서의 MCCI 거동 분석 (Evaluation of MCCI Behaviors in the Calandria Vault of CANDU-6 Plants Using CORQUENCH Code)

  • 유선오
    • 한국압력기기공학회 논문집
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    • 제17권2호
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    • pp.90-100
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    • 2021
  • Molten corium-concrete interaction (MCCI) is one of the most important phenomena that can lead to the potential hazard of late containment failure due to basemat penetration during a severe accident. In this study, MCCI analytical models of the CORQUENCH code were prepared through verification calculations of several experiments, which had been performed using concrete types similar to those of the calandria vault floor in CANDU-6 plants. The behaviors of thermal-hydraulic variables related to MCCI phenomena were analyzed under the conditions of dry floor and water flooding during the severe accident stemming from a hypothetic station blackout. Uncertainty analyses on the ablation depth were also carried out. It was estimated that the concrete ablation was not interrupted due to the continuous MCCI process under the dry condition but was terminated within 24 hours under the water flooding condition. It was confirmed that the water flooding as a mitigating action was effective to achieve the quenching and thermal stabilization of the melt discharged from the calandria vessel, showing that the present models are capable of reasonably simulating MCCI phenomena in CANDU-6 plants. This study is expected to provide the technical bases to the accident management strategy during the late-phase severe accidents.

Recent Developments Involving the Application of Infrared Thermal Imaging in Agriculture

  • Lee, Jun-Soo;Hong, Gwang-Wook;Shin, Kyeongho;Jung, Dongsoo;Kim, Joo-Hyung
    • 센서학회지
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    • 제27권5호
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    • pp.280-293
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    • 2018
  • The conversion of an invisible thermal radiation pattern of an object into a visible image using infrared (IR) thermal technology is very useful to understand phenomena what we are interested in. Although IR thermal images were originally developed for military and space applications, they are currently employed to determine thermal properties and heat features in various applications, such as the non-destructive evaluation of industrial equipment, power plants, electricity, military or drive-assisted night vision, and medical applications to monitor heat generation or loss. Recently, IR imaging-based monitoring systems have been considered for application in agricultural, including crop care, plant-disease detection, bruise detection of fruits, and the evaluation of fruit maturity. This paper reviews recent progress in the development of IR thermal imaging techniques and suggests possible applications of thermal imaging techniques in agriculture.

소듐냉각고속로 KALIMER-600 축소 물모의 열유동 가시화 실험장치 구축 및 거시 유동장 특성 측정 (Water-Simulant Facility Installation for the Sodium-Cooled Fast Reactor KALIMER-600 and Global Flow Measurement)

  • 차재은;김성오
    • 한국가시화정보학회지
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    • 제9권4호
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    • pp.54-62
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    • 2011
  • KAERI has developed a KALIMER-600 which is a pool-type sodium-cooled fast reactor with a 600MWe electric generation capacity. For a SFR development, one of the main topics is an enhancement of the reactor system safety. Therefore, we have a long-term plan to design the large sodium experimental facility to evaluate the reactor safety and component performance. In order to extrapolate a thermal hydraulic phenomena in a large sodium reactor, the thermal hydraulics phenomena is under investigation in a 1/$10^{th}$ water-simulant facility for the KALIMER-600. In this paper, we shortly described the experimental facility setup and the measurement of the isothermal global flow behavior. For the flow field measurement, the PIV method was used in a transparent Plexiglas reactor vessel model at around $20^{\circ}C$ water condition.