• Title/Summary/Keyword: Thermal prediction program

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THERMAL-HYDRAULIC TESTS AND ANALYSES FOR THE APR1400'S DEVELOPMENT AND LICENSING

  • Song, Chul-Hwa;Baek, Won-Pil;Park, Jong-Kyun
    • Nuclear Engineering and Technology
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    • v.39 no.4
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    • pp.299-312
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    • 2007
  • The program on thermal-hydraulic evaluation by testing and analysis (THETA) for the development and licensing of the new design features in the APR1400 (Advanced Power Reactor-1400) is briefly introduced with a presentation on the research motivation and typical results of the separate effect tests and analyses of the major design features. The first part deals with multi-dimensional phenomena related to the safety analysis of the APR1400. One research area is related to the multidimensional behavior of the safety injection (SI) water in a reactor pressure vessel downcomer that uses a direct vessel injection type of SI system. The other area is associated with the condensation of steam jets and the resultant thermal mixing in a water pool; these phenomena are relevant to the depressurization of a reactor coolant system (RCS). The second part describes our efforts to develop new components for safety enhancements, such as a fluidic device as a passive SI flow controller and a sparger to depressurize the RCS. This work contributes to an understanding of the new thermal-hydraulic phenomena that are relevant to advanced reactor system designs; it also improves the prediction capabilities of analysis tools for multi-dimensional flow behavior, especially in complicated geometries.

TAPINS: A THERMAL-HYDRAULIC SYSTEM CODE FOR TRANSIENT ANALYSIS OF A FULLY-PASSIVE INTEGRAL PWR

  • Lee, Yeon-Gun;Park, Goon-Cherl
    • Nuclear Engineering and Technology
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    • v.45 no.4
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    • pp.439-458
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    • 2013
  • REX-10 is a fully-passive small modular reactor in which the coolant flow is driven by natural circulation, the RCS is pressurized by a steam-gas pressurizer, and the decay heat is removed by the PRHRS. To confirm design decisions and analyze the transient responses of an integral PWR such as REX-10, a thermal-hydraulic system code named TAPINS (Thermal-hydraulic Analysis Program for INtegral reactor System) is developed in this study. Based on a one-dimensional four-equation drift-flux model, TAPINS incorporates mathematical models for the core, the helical-coil steam generator, and the steam-gas pressurizer. The system of difference equations derived from the semi-implicit finite-difference scheme is numerically solved by the Newton Block Gauss Seidel (NBGS) method. TAPINS is characterized by applicability to transients with non-equilibrium effects, better prediction of the transient behavior of a pressurizer containing non-condensable gas, and code assessment by using the experimental data from the autonomous integral effect tests in the RTF (REX-10 Test Facility). Details on the hydrodynamic models as well as a part of validation results that reveal the features of TAPINS are presented in this paper.

Two Dimensional Analysis for the External Vessel Cooling Experiment

  • Yoon, Ho-Jun;Kune Y. Suh
    • Nuclear Engineering and Technology
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    • v.32 no.4
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    • pp.410-423
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    • 2000
  • A two-dimensional numerical model is developed and applied to the LAVA-EXV tests performed at the Korea Atomic Energy Research Institute (KAERI) to investigate the external cooling effect on the thermal margin to failure of a reactor pressure vessel (RPV) during a severe accident. The computational program was written to predict the temperature profile of a two-dimensional spherical vessel segment accounting for the conjugate heat transfer mechanisms of conduction through the debris and the vessel, natural convection within the molten debris pool, and the possible ablation of the vessel wall in contact with the high temperature melt. Results of the sensitivity analysis and comparison with the LAVA-EXV test data indicated that the developed computational tool carries a high potential for simulating the thermal behavior of the RPV during a core melt relocation accident. It is concluded that the main factors affecting the RPV failure are the natural convection within the debris pool and the ablation of the metal vessel, The simplistic natural convection model adopted in the computational program partly made up for the absence of the mechanistic momentum consideration in this study. Uncertainties in the prediction will be reduced when the natural convection and ablation phenomena are more rigorously dealt with in the code, and if more accurate initial and time-dependent conditions are supplied from the test in terms of material composition and its associated thermophysical properties.

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Development of Program for the Temperature Rise Prediction of electrical equipment Using Thermal Network Method (열회로망법을 이용한 전력기기 온도예측 프로그램 개발)

  • Lee, Jong-C.;Ahn, Heui-Sub;Choi, Jong-Ung;Oh, Il-Sung
    • Proceedings of the KIEE Conference
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    • 2002.07b
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    • pp.946-948
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    • 2002
  • 최근 컴퓨팅 기술의 발전으로 3차원 복합열전달(conjugate heat transfer) 문제를 계산하는 수 치해석 기술이 어느 정도 가능해 졌지만, 실제적인 전력기기 내부의 온도분포를 수치적으로 계산하는 것은 탑재된 구성요소의 다양한 크기와 형상으로 인한 매우 복잡한 경계조건을 수반하고 조밀한 격자를 요구하기 때문에 공학적이지 않다. 이를 위하여 해석적 모델을 수립하여 전력기기 열설계를 위한 수치적 해석에 적용하는 방법이 널리 사용되고 있다. 본 연구에서는 열회로망법(Thermal Network Analysis, TNA)을 이용하여 전력기기 내부의 온도분포를 예측할 수 있는 프로그램을 개발하였다. 전류가 흘러 열이 발생하고 소산되는 주회로 성분들을 각각의 노드로 분할하는 절차를 확립하였고 열접촉저항과 주울열을 적절히 선정함으로써 실제 전류가 흐르는 회로망 내 온도분포를 계산하였다.

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Computer Simulation of Quench-Hardening of Alloy Steel for Structural Purposes by the Modified Finite Difference Method (개량차분법에 의한 임의의 형상의 열처리제품의 급냉경화 해석)

  • Kim, K.S.;Song, Y.B.;Hong, C.P.
    • Journal of the Korean Society for Heat Treatment
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    • v.2 no.2
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    • pp.11-16
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    • 1989
  • Understanding and control of thermal history of heat-treated components are very important in heat treating process. A computer program was developed for prediction of thermal history in quenching process with various cooling media and agitation conditions. Computer simulation of heat flow in quenching treatment of spur gear of SCM 22 H was carried out by two and three dimensional finite difference method. Distributions of microstructure and hardness in heat-treated spur gear were predicted by computer simulation, and the results showed a good agreement with the experiments. It was concluded that the

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Prediction of Nuggest Shape by Finite Element Modeling in Arc-spot Welding (유한요소 모델링을 이용한 아크 스폿 용접의 너깃 형상 예측)

  • 황종근;장경복;김기순;강성수
    • Journal of Welding and Joining
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    • v.17 no.2
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    • pp.84-90
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    • 1999
  • The shape of weld nuggest in arc spot welding of 304 stainless steel was found by searching thermal history of a weld joint through a three-dimensional finite element model. The problem consists of one in which the finite element mesh is growing continuously in time in order to accomodate metal transfer in arc spot welding using element rebirth technique. The analysis was performed on the basis of experimental results. The finite element program MARC, along with a few user subroutines, was employed to obtain the numerical results. Temperature-dependent thermal properties, stir effect in weld pool, effect of phase transformation, and the convective and radiative boundary conditions are included in the model. Numerically predicted shape of weld nuggest is compared with the experimentally observed shape.

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Noise Map Modeling and Analysis of Thermal Power Plant (화력발전소의 소음지도 모델링 및 해석)

  • Kim, Won-Jin;Yun, Jun-Ho
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2013.10a
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    • pp.605-610
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    • 2013
  • This study proposes an analysis model to simulate a noise map and estimate noise distribution for a location and its surroundings of a power plant. The noise map analysis was executed by using ENPro that is a commercial program for environmental noise prediction. Experimental evaluation for the proposed analysis model was carried out by comparing the results from noise analysis and measurement at several major points of the power plant and residential areas.

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Temperature Prediction of Underground Working Place Using Artificial Neural Networks (인공신경망을 이용한 심부 갱내온도 예측)

  • Kim, Yun-Kwang;Kim, Jin
    • Tunnel and Underground Space
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    • v.17 no.4
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    • pp.301-310
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    • 2007
  • The prediction of temperature in the workings for the propriety examination for the development of a deep coal bed and the ventilation design is fairly important. It is quite demanding to obtain precise thermal conductivity of rock due to the variety and the complexity of the rock types contiguous to the coal bed. Therefore, to estimate the thermal conductivity corresponding to this geological situation and complex gallery conditions, a computing program which is TemPredict, is developed in this study. It employs Artificial Neural Network and calculates the climatic conditions in galleries. This advanced neural network is based upon the Back-Propagation Algorithm and composed of the input layers that are acceptant of the physical and geological factors of the coal bed and the hidden layers each of which has the 5 and 3 neurons. To verify TemPredict, the calculated result is compared with the measured one at the entrance of -300 ML 9X of Jang-sung production department, Jang-sung Coal Mine. The difference between the results calculated by TemPredict ($25.65^{\circ}C$) and measured ($25.7^{\circ}C$) is only $0.05^{\circ}C$, which is less than the allowable error 5%. The result has more than 95% of very high reliability. The temperature prediction for the main carriage gallery 9X in -425 ML under construction when it is completed is made. Its result is $28.2^{\circ}C$. In the future, it would contribute to the ventilation design for the mine and the underground structures.

Fire Resistance Behaviour of High Strength Concrete Members with Vapor Pressure and Creep Models (증기압 및 크리프 모델을 사용한 고강도콘크리트 부재의 내화성능평가)

  • Lee, Tae-Gyu
    • Fire Science and Engineering
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    • v.24 no.4
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    • pp.33-40
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    • 2010
  • A numerical model considering the vapor pressure and the creep models, in the form of a analytical program, for tracing the behavior of high strength concrete (HSC) members exposed to fire is presented. The two stages, i.e., spalling procedure and fire resistance time, associated with the thermal, moisture flow, creep and structural analysis, for the prediction of fire resistance behavior are explained. The use of the analytical program for tracing the response of HSC member from the initial pre-loading stage to collapse, due to fire, is demonstrated. The validity of the numerical model used in this program is established by comparing the predictions from this program with results from others fire resistance tests. The analytical program can be used to predict the fire resistance of HSC members for any value of the significant parameters, such as load, sectional dimensions, member length, and concrete strength.

Prediction of Performance considering Ablated PTFE in High Voltage Self-blast Circuit Breaker (PTFE 용삭을 고려한 초고압 복합소호 차단기의 성능 예측)

  • Kim, Jin-Bum;Kweon, Ki-Yeoung;Lee, Hahk-Sung
    • 한국전산유체공학회:학술대회논문집
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    • 2008.03b
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    • pp.695-698
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    • 2008
  • Self-blast circuit breakers utilize the energy dissipated by the arc itself to create the required conditions for arc quenching during the current zero. During the arcing period, high pressure, temperature and radiation of the arc could burn in pure SF6 gas and PTFE nozzle. Ablated nozzle shape and $SF_6$-PTFE mixture vapor affect the performance of an self-blast circuit breaker. After a number of tests, nozzle in circuit breaker is disassembled, a section of ablated nozzle is investigated precisely. Using computational fluid dynamics, the conservation equation for the gas and temperature, velocity and electric fields within breaker is solved. Before applying a section model, developed program is verified with experimental data. Performance of ablated nozzle shape is compared with original model through analysis program.

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