With revising the ECCS licensing rules in 1989, USNRC has allowed the use of “best estimate” thermal-hydraulics computer codes (such as RELAP5 and TRAC) with the requirement that uncertainty analysis accompany the results. Several methodologies have been developed for quantification of uncertainties of such codes. These methodologies are either input-driven or output-driven. They differ definition for the uncertainty range, qualification and quantification steps, types of uncertainty sources considered, methods of assignment of uncertainty distribution or range to various parameters, approach to propagation of uncertainty, and the way the dynamic characteristics of TH codes are handled. The IMTHUA methodology, developed by the authors, is a hybrid approach where an input-driven “white box” approach is augmented with output correction based on experimental results relevant to code output. This paper offers a comparative assessment of IMTHUA and other uncertainty analysis methodologies for thermal-hydraulics transient calculations. The methods will be compared based on their approaches for treatment of input, propagation, code models and correlations, as well as output. Comprehensiveness, approach to data treatment, and interpretation of results are among the criteria for comparison. Several examples are provided to clarify the differences.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4353-6
PROCEEDINGS PAPER
Survey on Methodologies for Thermal-Hydraulics System Codes Uncertainty Assessment Available to Purchase
Mohammad Pourgol-Mohammad,
Mohammad Pourgol-Mohammad
Goodman Global Inc., Houston, TX
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Kamran Sepanloo
Kamran Sepanloo
Atomic Energy Organization of Iran, Tehran, Iran
Search for other works by this author on:
Mohammad Pourgol-Mohammad
Goodman Global Inc., Houston, TX
Kamran Sepanloo
Atomic Energy Organization of Iran, Tehran, Iran
Paper No:
ICONE17-75463, pp. 405-413; 9 pages
Published Online:
February 25, 2010
Citation
Pourgol-Mohammad, M, & Sepanloo, K. "Survey on Methodologies for Thermal-Hydraulics System Codes Uncertainty Assessment." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 405-413. ASME. https://doi.org/10.1115/ICONE17-75463
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