• 제목/요약/키워드: Anisotropic Buoyancy

검색결과 4건 처리시간 0.016초

부력에 의한 난류 열대류의 혼성 난류모델 (A Hybrid Turbulence Model for Prediction of Buoyancy-Driven Turbulent Thermal Convection Flow)

  • 김태규;성형진
    • 대한기계학회논문집
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    • 제17권8호
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    • pp.2069-2078
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    • 1993
  • The buoyancy-driven turbulent thermal convection is predicted using an anisotropic hybrid turbulence model, which is incorporated with a low Reynolds k-.epsilon. turbulence model and an anisotropic buoyant part of algebraic stress model(ASM). The numerical predictions are compared with the Davidson's model,(1) the full ASM and the experimental results of Cheesewright et al.(2) All the models are shown to predict good agreements with the experiments for the averaged turbulence quantities. It is found that the effect of an anisotropic part on the Reynolds stress and the turbulent heat fluxes is substantial. In this study, the present hybrid model gives a fairly reasonable prediction in terms of the computational accuracy, convergence and stability. The contribution of an anisotropic buoyant part to turbulent heat fluxes are also scrutinized over the range of Rayleigh numbers $(4.79{\times}10^{10}{\le}Ra{\le}7.46{\times}10^{10}).$

Assessment of turbulent heat flux models for URANS simulations of turbulent buoyant flows in ROCOM tests

  • Zonglan Wei;Bojan Niceno ;Riccardo Puragliesi;Ezequiel Fogliatto
    • Nuclear Engineering and Technology
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    • 제54권11호
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    • pp.4359-4372
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    • 2022
  • Turbulent mixing in buoyant flows is an essential mechanism involved in many scenarios related to nuclear safety in nuclear power plants. Comprehensive understanding and accurate predictions of turbulent buoyant flows in the reactor are of crucial importance, due to the function of mitigating the potential detrimental consequences during postulated accidents. The present study uses URANS methodology to investigate the buoyancy-influenced flows in the reactor pressure vessel under the main steam line break accident scenarios. With a particular focus on the influence of turbulent heat flux closure models, various combinations of two turbulence models and three turbulent heat flux models are utilized for the numerical simulations of three ROCOM tests which have different characteristic features in terms of the flow rate and fluid density difference between loops. The simulation results are compared with experimental measurements of the so-called mixing scalar in the downcomer and at the core inlet. The study shows that the anisotropic turbulent heat flux models are able to improve the accuracy of the predictions under conditions of strong buoyancy whilst in the weak buoyancy case, a major role is played by the selected turbulence models with essentially a negligible influence of the turbulent heat flux closure models.

3-D CFD Analysis of the CANDU-6 Moderator Circulation Under Nnormal Operating Conditions

  • Yoon, Churl;Rhee, Bo-Wook;Min, Byung-Joo
    • Nuclear Engineering and Technology
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    • 제36권6호
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    • pp.559-570
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    • 2004
  • A computational fluid dynamics model for predicting moderator circulation inside the Canada deuterium uranium (CANDU) reactor vessel has been developed to estimate the local subcooling of the moderator in the vicinity of the calandria tubes. The buoyancy effect induced by the internal heating is accounted for by the Boussinesq approximation. The standard $k-{\varepsilon}$ turbulence model with logarithmic wall treatment is applied to predict the turbulent jet flows from the inlet nozzles. The matrix of the calandria tubes in the core region is simplified to a porous media in which the anisotropic hydraulic impedance is modeled using an empirical correlation of pressure loss. The governing equations are solved by DFX-4.4, a commercial CFD code developed by AEA technology. The resultant flow patterns of the constant-z slices containing the inlet nozzles and the outlet port are "mined-type", as observed in the former 2-dimensional experimental investigations. With 103% full power for conservatism, the maximum temperature of the moderator is $82.9^{\circ}C$ at the top of the core region. Considering the hydrostatic pressure change, the minimum subcooling is $24.8^{\circ}C$.

머시영역의 비등방성을 고려한 2성분혼합물의 응고과정 (Solidification Process of a Binary Mixture with Anisotropy of the Mushy Region)

  • 유호선
    • 대한기계학회논문집
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    • 제17권1호
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    • pp.162-171
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    • 1993
  • 본 연구에서는 2성분혼합물의 응고과정해석에 머시영역의 비등방성을 포함시 킬수 있는 모델을 정립하고 실제계산을 수행하여 비등방성이 천이현상 및 조대편석(m- acrosegregation)에 미치는 영향을 보이고자 한다. 이 과정에서 기본 방정식의 변형 을 통한 수치해석의 효율화에 관해서도 취급할 것이다. 해석대상은 비등방성의 효과 가 잘 나타날 수 있으면서 해석은 용이한 2차원 정사각형용기로 선택하였다. 대상혼 합물은 실용적으로 관심있는 금속 합금과 결정구조가 유사하며 물성치가 비교적 잘 확 립된 염화암모늄수용액(NH$_{4}$C1-H$_{2}$O)이다. 특히 아공정염화암모늄수용액은 부력비(buoyancy factor)가 -1.4정도로서 온도와 농도구배에 의한 부력이 크기는 비슷 하지만 작용방향이 반대이기 때문에 이중확산대류의 전형적인 형태를 고찰하기에 편리 한 물질이다.