In spite of being a significant source of uncertainty, “Model Uncertainty” is ignored in most of engineering applications. The influence of model uncertainty is most pronounced for areas with limited knowledge and complex simulations structures like severe accident calculations; however lack of a systematic methodology makes this assessment a challenge. The present study is devoted to the treatment of model uncertainty in severe accident analysis for nuclear power plants. After a review of available methodologies for model uncertainty treatment in different applications, the unique features are described for the severe accident problems with supportive examples from the real calculations. By reviewing available approaches in engineering and science as well as the structure of severe accident codes, challenges are discussed for model uncertainty assessment in this area. This paper initiates a systematic examination at the subject.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5004-6
PROCEEDINGS PAPER
Overview of Code Structures, Challenges and Available Methodologies for Treatment of Model Uncertainty in Severe Accident Calculations
Seyed Mohsen Hoseyni,
Seyed Mohsen Hoseyni
Quality Consulting, Attleboro, MA
Search for other works by this author on:
Mohammad Pourgol-Mohammad
Mohammad Pourgol-Mohammad
Quality Consulting, Attleboro, MA
Search for other works by this author on:
Seyed Mohsen Hoseyni
Quality Consulting, Attleboro, MA
Mohammad Pourgol-Mohammad
Quality Consulting, Attleboro, MA
Paper No:
ICONE24-61098, V004T14A023; 12 pages
Published Online:
October 25, 2016
Citation
Hoseyni, SM, & Pourgol-Mohammad, M. "Overview of Code Structures, Challenges and Available Methodologies for Treatment of Model Uncertainty in Severe Accident Calculations." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T14A023. ASME. https://doi.org/10.1115/ICONE24-61098
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