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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 941 - 951 (11page)
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초록· 키워드
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The aim of this work is to simulate the thermohydraulic consequences of a main steam linebreak and to compare the obtained results with Rossendorf Coolant Mixing Model (ROCOM)1.1 experimental results. The objective is to utilize data from steady-state mixing experimentsand computational fluid dynamics (CFD) calculations to determine the flow distributionand the effect of thermal mixing phenomena in the primary loops for theimprovement of normal operation conditions and structural integrity assessment of pressurizedwater reactors. The numerical model of ROCOM was developed using the FLUENTcode. The positions of the inlet and outlet boundary conditions and the distribution ofdetailed velocity/turbulence parameters were determined by preliminary calculations. Thetemperature fields of transient calculation were averaged in time and compared with timeaveragedexperimental data. The perforated barrel under the core inlet homogenizes theflow, and therefore, a uniform temperature distribution is formed in the pressure vesselbottom. The calculated and measured values of lowest temperature were equal. The inlettemperature is an essential parameter for safety assessment. The calculation predicts preciselythe experimental results at the core inlet central region. CFD results showed a goodagreement (both qualitatively and quantitatively) with experimental results.
목차
등록된 정보가 없습니다.
참고문헌 (36)
참고문헌 신청
U. Rohdea / 2007 / Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactordvalidation of CFD codes / Nucl. Eng. Des 237:1639~1655
H.D. Kweon / 2008 / Fatigue design of nuclear class piping considering thermal stratification / Nucl. Eng. Des 238:1265~1274
E.C. Eggertson / 2011 / Turbulent mixingand its effectsonthermal fatigue innuclear reactors / Int. J. Math. Comput. Phys. Electr. Comput. Eng 52:206~213
K.J. Metzner / Thermal Fatigue Evaluation of Piping System Tee-Connections
S.,M. Hosseini / 2007 / Classification of turbulent jets in a T-junction area with a 90-deg bend upstream / Int. J. Heat Mass Transf 51:2444~2454
H.D. Kweon / 2008 / Fatigue design of nuclear class piping considering thermal stratification / Nucl. Eng. Des 238:1265~1274
E.C. Eggertson / 2011 / Turbulent mixingand its effectsonthermal fatigue innuclear reactors / Int. J. Math. Comput. Phys. Electr. Comput. Eng 52:206~213
K.J. Metzner / Thermal Fatigue Evaluation of Piping System Tee-Connections
S.,M. Hosseini / 2007 / Classification of turbulent jets in a T-junction area with a 90-deg bend upstream / Int. J. Heat Mass Transf 51:2444~2454
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