During a severe nuclear power plant (NPP) accident, large amounts of hydrogen and steam can be produced in nuclear reactor containment. In the case of hydrogen combustion, there is a possibility of producing short term pressure or detonation force. Therefore, these gas species’ production could threaten containment integrity. For instance, in the past, two gas explosion accidents occurred: In 1979 Three Mile Island and in 2011 Fukushima. After these accidents, modeling the gas behavior became an important topic in nuclear safety analyses. In order to predict hydrogen behavior and other gas species transport, mixing and combustion, reliable turbulence models need to be applied. In this work, standard k–ε, k–ω, RNG k–ε, Realizable k–ε and SST k–ω turbulence models are addressed. The computations are performed with HYDRAGON code. HYDRAGON code is a three-dimensional thermal-hydraulic code, developed to solve low-speed gas flow of compressible Navier-Stokes equations in cartesian or cylindrical coordinates or a mixture of the two coordinates. The goal of this work is to test the performance of these models by comparing the results to the benchmark. The code aims to predict containment thermal-hydraulic conditions during NPP accident.
Skip Nav Destination
2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4594-3
PROCEEDINGS PAPER
Application of Some Turbulence Models to Simulate Buoyancy-Driven Flow
Aniseh A. A. Abdalla,
Aniseh A. A. Abdalla
Tsinghua University, Beijing, China
Search for other works by this author on:
Mohammad Alrwashdeh
Mohammad Alrwashdeh
Tsinghua University, Beijing, China
Search for other works by this author on:
Aniseh A. A. Abdalla
Tsinghua University, Beijing, China
Jiyang Yu
Tsinghua University, Beijing, China
Mohammad Alrwashdeh
Tsinghua University, Beijing, China
Paper No:
ICONE22-30060, V004T10A003; 8 pages
Published Online:
November 17, 2014
Citation
Abdalla, AAA, Yu, J, & Alrwashdeh, M. "Application of Some Turbulence Models to Simulate Buoyancy-Driven Flow." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory. Prague, Czech Republic. July 7–11, 2014. V004T10A003. ASME. https://doi.org/10.1115/ICONE22-30060
Download citation file:
21
Views
Related Proceedings Papers
Related Articles
From Water Hammer to Ignition
Mechanical Engineering (December,2014)
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
Safest Roadmap for Corium Experimental Research in Europe
ASME J. Risk Uncertainty Part B (September,2018)
Related Chapters
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards