A Review of the CFD Modeling Progress Triggered by ISP-47 on Containment Thermal Hydraulics

References

• H. KARWAT et al., “SOAR on Containment Thermalhydraulics and Hydrogen Distribution,” NEA/CSNI/R(1999)16, Organisation for Economic Co-operation and Development/Nuclear Energy Agency Committee on the Safety of Nuclear Installations (1999).
   Google Scholar
• H.-J. ALLELEIN et al., “International Standard Problem ISP-47 on Containment Thermal Hydraulics,” NEA/CSNI/R(2007)10, Organisation for Economic Co-operation and Development/Nuclear Energy Agency Committee on the Safety of Nuclear Installations (2007).
   Google Scholar
• “OECD/NEA THAI Project Final Report—Hydrogen and Fission Product Issues Relevant for Containment Safety Assessment Under Severe Accident Conditions,” NEA/CSNI/R(2010)3, Organisation for Economic Co-operation and Development/Nuclear Energy Agency Committee on the Safety of Nuclear Installations (June 2010).
   Google Scholar
• “OECD/SETH-2 Project PANDA and MISTRA Experiments Final Summary Report—Investigation of Key Issues for the Simulation of Thermal-Hydraulic Conditions in Water Reactor Containments,” NEA/CSNI/R(2012)5, Organisation for Economic Co-operation and Development/Nuclear Energy Agency Committee on the Safety of Nuclear Installations (2012).
   Google Scholar
• D. PALADINO et al., “For the Analysis and Mitigation of a Severe Accident Leading to Hydrogen Release into a Nuclear Plant Containment,” Proc. Int. Congress Advances in Nuclear Power Plants (ICAPP), Charlotte, North Carolina, April 6–9, 2014, American Nuclear Society (2014).
   Google Scholar
• S. SCHWARZ et al., “Benchmark on Hydrogen Distribution in a Containment Based on the OECD-NEA THAI HM-2 Experiment,” Nucl. Technol., 175, 594 (2011); https://doi.org/10.13182/NT11-A12508.
   Web of Science ®Google Scholar
• S. GUPTA et al., “THAI Test Facility for Experimental Research on Hydrogen and Fission Product Behaviour in Light Water Reactor Containments,” Nucl. Eng. Des., 294, 183 (2015); https://doi.org/10.1016/j.nucengdes.2015.09.013.
   Web of Science ®Google Scholar
• R. KAPULLA et al., “Break-Up of Gas Stratification in LWR Containment Induced by Negatively Buoyant Jets and Plumes,” Proc. ICONE-17, Brussels, Belgium, July 12–16, 2009.
   Google Scholar
• E. STUDER et al., “Interaction of a Light Gas Stratified Layer with an Air Jet Coming from Below: Large Scale Experiments and Scaling Issues,” Nucl. Eng. Des., 253, 406 (2012); https://doi.org/10.1016/j.nucengdes.2012.10.009.
   Web of Science ®Google Scholar
• R. ZBORAY et al., “Erosion and Break-Up of Light-Gas Layers by a Horizontal Jet in a Multi-Vessel, Large-Scale Containment Test System,” Nucl. Eng. Des., 291, 10, 10 (2015); https://doi.org/10.1016/j.nucengdes.2015.05.006.
   Google Scholar
• S. PARANJAPE et al., “Parametric Study on Density Stratification Erosion Caused by a Horizontal Steam Jet Interacting with a Vertical Plate Obstruction,” Nucl. Eng. Des., 312, 351 (2017); https://doi.org/10.1016/j.nucengdes.2016.12.012.
   Web of Science ®Google Scholar
• M. ANDREANI et al., “Synthesis of a Blind CFD Benchmark Exercise Based on a Test in the PANDA Facility Addressing the Stratification Erosion by a Vertical Jet in Presence of a Flow Obstruction,” Proc. OECD/NEA and IAEA Workshop Experiments and CFD Codes Application to Nuclear Reactor Safety (CFD4NRS), Cambridge, Massachusetts, September 9–13, 2016, Organisation for Economic Co-operation and Development/Nuclear Energy Agency/International Atomic Energy Agency.
   Google Scholar
• M. FREITAG and E. SCHMIDT, “Comparison Report for Blind and Open Simulations of THAI Test TH26—Dissolution of a Light Gas Stratification by Air Jet Injection,” Report No. 1501455-TH26-VB, Becker Technologies (June 2014).
   Google Scholar
• M. FREITAG et al., “Simulation Benchmark Based on THAI-Experiment on Dissolution of a Steam Stratification by Natural Convection,” Nucl. Eng. Des., 299, 37 (2016); https://doi.org/10.1016/j.nucengdes.2015.07.001.
   Web of Science ®Google Scholar
• D. PALADINO et al., “Outcomes from the EURATOM-ROSATOM ERCOSAM SAMARA Projects on Containment Thermal-Hydraulics for Severe Accident Management,” Nucl. Eng. Des., 308, 103 (2016); https://doi.org/10.1016/j.nucengdes.2016.08.011.
   Web of Science ®Google Scholar
• VEREIN DEUTSCHE INGENIEURE (ASSOCIATION OF GERMAN ENGINEERS), VDI Waermeatlas (VDI Heat Atlas), 10th ed., Springer (2006).
   Google Scholar
• S. KELM et al., “Application of the MiniPanda Test Case ‘Erosion of a Stratified Layer by a Vertical Jet’ for CFD Validation,” Nucl. Eng. Des., 299, 124 (2016); https://doi.org/10.1016/j.nucengdes.2015.08.013.
   Web of Science ®Google Scholar
• S. KELM, R. KAPULLA, and H.-J. ALLELEIN, “Erosion of a Confined Stratified Layer by a Vertical Jet—Detailed Assessment of a CFD Approach Against the OECD/NEA PSI Benchmark,” Nucl. Eng. Des., 312, 228 (2017); https://doi.org/10.1016/j.nucengdes.2016.09.014.
   Web of Science ®Google Scholar
• S. KELM et al., “A Comparative Assessment of Different Experiments on Buoyancy Driven Mixing Processes by Means of CFD,” Ann. Nucl. Energy, 93, 50 (2016); https://doi.org/10.1016/j.anucene.2015.12.032.
   Web of Science ®Google Scholar
• “ANSYS CFX-Solver Theory Guide and Solver Modeling Guide,” Release 17.2, ANSYS, Inc. (2016).
   Google Scholar
• H. MÜLLER et al., “Development of a Wall Condensation Model for Coarse Mesh Containment Scale Applications,” Proc. OECD/NEA and IAEA Workshop Experiments and CFD Codes Application to Nuclear Reactor Safety (CFD4NRS), Cambridge, Massachusetts, September 9–13, 2016, Organisation for Economic Co-operation and Development/Nuclear Energy Agency/International Atomic Energy Agency.
   Google Scholar
• W. AMBROSINI et al., “Lesson Learned from the SARNET Wall Condensation Benchmarks,” Ann. Nucl. Energy, 74, 153 (2014); https://doi.org/10.1016/j.anucene.2014.07.014.
   Web of Science ®Google Scholar
• A. HUNDHAUSEN et al., “Towards CFD-Grade Measurements in a Condensing Boundary Layer—First Results of the New SETCOM Facility,” Proc. 8th Conf. Severe Accident Research (ERMSAR), Warsaw, Poland, May 16–18, 2017.
   Google Scholar
• J. LEHMKUHL et al., “Improvement of Wall Condensation Modeling with Suction Wall Functions for Containment Application,” Nucl. Eng. Des., 299, 105 (2016); https://doi.org/10.1016/j.nucengdes.2015.08.002.
   Web of Science ®Google Scholar
• W. CHUNG and C. B. DEVAUD, “Buoyancy-Corrected k-ε Models and Large Eddy Simulation Applied to a Large Axisymmetric Helium Plume,” Int. J. Numer. Methods Fluids, 58, 57 (2008); https://doi.org/10.1002/fld.v58:1.
   Web of Science ®Google Scholar
• S. ABE et al., “RANS Analyses on Erosion Behavior of Density Stratification Consisted of Helium-Air Mixture Gas by a Low Momentum Vertical Buoyant Jet in the PANDA Test Facility, the Third International Benchmark Exercise (IBE-3),” Nucl. Eng. Des., 289, 231 (2015); https://doi.org/10.1016/j.nucengdes.2015.04.002.
   Web of Science ®Google Scholar
• S. KELM, H. MÜLLER, and H.-J. ALLELEIN, “Importance of Thermal Radiation Heat Transfer Modeling in Containment Typical Flows,” Proc. OECD/NEA and IAEA Workshop on Experiments and CFD Codes Application to Nuclear Reactor Safety (CFD4NRS), Cambridge, Massachusetts, September 9–13, 2016, Organisation for Economic Co-operation and Development/Nuclear Energy Agency/International Atomic Energy Agency.
   Google Scholar
• A. DEHBI et al., “The Influence of Thermal Radiation on the Free Convection Inside Enclosures,” Proc. 8th Conf. Severe Accident Research (ERMSAR), Warsaw, Poland, May 16–18, 2017.
   Google Scholar
• J. MALET et al., “ISP-47—STEP 1: TOSQAN—Mistra, Phase A: TOSQAN Experimental Results of the Air-Steam Phase,” Report No. DPEAJSERAC/LPMAC/02-45, IRSN (Dec. 2016).
   Google Scholar
• K. FISCHER et al., “ISP-47—STEP 2: ThAI, Volume 1-4,” Report No. BF-R 70031-1/2/3/4, Becker Technologies (Dec. 2004).
   Google Scholar
• J. MAHAFFY et al., “Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications—Revision,” NEA/CSNI/R(2014)11, Organisation for Economic Co-operation and Development/Nuclear Energy Agency Committee on the Safety of Nuclear Installations.
   Google Scholar
• F. R. MENTER et al., “CFD Best Practice Guidelines for CFD Code Validation for Reactor Safety Applications,” EU-ECORA FIKS-CT-2001-00154, European Commission–ECORA (2001).
   Google Scholar
• P. ROYL et al., “Benchmarking of the 3D CFD Code GASFLOW with Containment Thermal Hydraulic Tests from HDR and THAI,” Proc. OECD/NEA and IAEA Workshop on Experiments and CFD Codes Application to Nuclear Reactor Safety (CFD4NRS), Munich, Germany, September 5–7, 2006.
   Google Scholar