Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor Model
The aim of this work is to simulate the thermohydraulic consequences of a main steam line break 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 experiments and computational fluid dyn...
| Main Authors: | , , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2016-08-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573316000802 |
| _version_ | 1818380327144390656 |
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| author | Istvan Farkas Ezddin Hutli Tatiana Farkas Antal Takács Attila Guba Iván Tóth |
| author_facet | Istvan Farkas Ezddin Hutli Tatiana Farkas Antal Takács Attila Guba Iván Tóth |
| author_sort | Istvan Farkas |
| collection | DOAJ |
| description | The aim of this work is to simulate the thermohydraulic consequences of a main steam line break 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 experiments and computational fluid dynamics (CFD) calculations to determine the flow distribution and the effect of thermal mixing phenomena in the primary loops for the improvement of normal operation conditions and structural integrity assessment of pressurized water reactors. The numerical model of ROCOM was developed using the FLUENT code. The positions of the inlet and outlet boundary conditions and the distribution of detailed velocity/turbulence parameters were determined by preliminary calculations. The temperature fields of transient calculation were averaged in time and compared with time-averaged experimental data. The perforated barrel under the core inlet homogenizes the flow, and therefore, a uniform temperature distribution is formed in the pressure vessel bottom. The calculated and measured values of lowest temperature were equal. The inlet temperature is an essential parameter for safety assessment. The calculation predicts precisely the experimental results at the core inlet central region. CFD results showed a good agreement (both qualitatively and quantitatively) with experimental results. |
| first_indexed | 2024-12-14T02:16:55Z |
| format | Article |
| id | doaj.art-38a13fe447984915aac44180b22b21f4 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-14T02:16:55Z |
| publishDate | 2016-08-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-38a13fe447984915aac44180b22b21f42022-12-21T23:20:36ZengElsevierNuclear Engineering and Technology1738-57332016-08-0148494195110.1016/j.net.2016.02.017Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor ModelIstvan Farkas0Ezddin Hutli1Tatiana Farkas2Antal Takács3Attila Guba4Iván Tóth5Department of Thermohydraulics, Centre for Energy Research, Hungarian Academy of Sciences, Konkoly-Thege Miklós út 29-33, 1121 Budapest, HungaryDepartment of Thermohydraulics, Centre for Energy Research, Hungarian Academy of Sciences, Konkoly-Thege Miklós út 29-33, 1121 Budapest, HungaryDepartment of Thermohydraulics, Centre for Energy Research, Hungarian Academy of Sciences, Konkoly-Thege Miklós út 29-33, 1121 Budapest, HungaryDepartment of Thermohydraulics, Centre for Energy Research, Hungarian Academy of Sciences, Konkoly-Thege Miklós út 29-33, 1121 Budapest, HungaryDepartment of Thermohydraulics, Centre for Energy Research, Hungarian Academy of Sciences, Konkoly-Thege Miklós út 29-33, 1121 Budapest, HungaryDepartment of Thermohydraulics, Centre for Energy Research, Hungarian Academy of Sciences, Konkoly-Thege Miklós út 29-33, 1121 Budapest, HungaryThe aim of this work is to simulate the thermohydraulic consequences of a main steam line break 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 experiments and computational fluid dynamics (CFD) calculations to determine the flow distribution and the effect of thermal mixing phenomena in the primary loops for the improvement of normal operation conditions and structural integrity assessment of pressurized water reactors. The numerical model of ROCOM was developed using the FLUENT code. The positions of the inlet and outlet boundary conditions and the distribution of detailed velocity/turbulence parameters were determined by preliminary calculations. The temperature fields of transient calculation were averaged in time and compared with time-averaged experimental data. The perforated barrel under the core inlet homogenizes the flow, and therefore, a uniform temperature distribution is formed in the pressure vessel bottom. The calculated and measured values of lowest temperature were equal. The inlet temperature is an essential parameter for safety assessment. The calculation predicts precisely the experimental results at the core inlet central region. CFD results showed a good agreement (both qualitatively and quantitatively) with experimental results.http://www.sciencedirect.com/science/article/pii/S1738573316000802Cold LegDowncomerMixingThermal ShocksThermal FatigueTemperatureVelocity |
| spellingShingle | Istvan Farkas Ezddin Hutli Tatiana Farkas Antal Takács Attila Guba Iván Tóth Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor Model Nuclear Engineering and Technology Cold Leg Downcomer Mixing Thermal Shocks Thermal Fatigue Temperature Velocity |
| title | Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor Model |
| title_full | Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor Model |
| title_fullStr | Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor Model |
| title_full_unstemmed | Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor Model |
| title_short | Validation of Computational Fluid Dynamics Calculation Using Rossendorf Coolant Mixing Model Flow Measurements in Primary Loop of Coolant in a Pressurized Water Reactor Model |
| title_sort | validation of computational fluid dynamics calculation using rossendorf coolant mixing model flow measurements in primary loop of coolant in a pressurized water reactor model |
| topic | Cold Leg Downcomer Mixing Thermal Shocks Thermal Fatigue Temperature Velocity |
| url | http://www.sciencedirect.com/science/article/pii/S1738573316000802 |
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