SAPIUM: A Generic Framework for a Practical and Transparent Quantification of Thermal-Hydraulic Code Model Input Uncertainty
Creators
- 1. Inst Radioprotect and Surete Nucl IRSN, Ctr Cadarache, PSN RES SEMIA, F-13115 St Paul les Durance (France)
- 2. Tractebel ENGIE, Blvd Simon Bolivar 34-36, B-1000 Brussels (Belgium)
- 3. Univ Paris Saclay, CEA, DEN STMF LMES DM2S, F-91191 Gif sur Yvette (France)
- 4. NINE Nucl and Ind Engn Srl, Via Chiesa XXXII, I-75955100 Lucca (Italy)
- 5. Consejo Seguridad Nucl CSN, Madrid 28040 (Spain)
- 6. Univ Politecn Catalunya UPC, Avda Diagonal 647, Barcelona 08028 (Spain)
- 7. Gesell Anlagen and Reaktorsicherheit GRS GmbH, Forschungszentrum, D-85748 Garching (Germany)
- 8. EDF R and D, Dept PRISME, 6 Quai Watier, F-78401 Chatou (France)
- 9. Korea Inst Nucl Safety, 62 Gwahak Ro, Daejeon 34142 (Korea, Republic of)
- 10. Nucl Regulat Author, Minato Ku, 1-9-9 Roppongi, Tokyo 1068450 (Japan)
Description
Uncertainty analysis is a key element in nuclear power plant deterministic safety analysis using best-estimate thermal-hydraulic codes and best-estimate-plus-uncertainty methodologies. If forward uncertainty propagation methods have now become mature for industrial applications, the input uncertainty quantification (IUQ) on the physical models still requires further investigations. The Organisation for Economic Co-operation and Development/Nuclear Energy Agency PREMIUM project attempted to benchmark the available IUQ methods, but observed a strong user effect due to the lack of best practices guidance. The SAPIUM project has been proposed toward the construction of a clear and shared systematic approach for IUQ. The main outcome of the project is a first 'good-practices' document that can be exploited for safety study in order to reach consensus among experts on recommended practices as well as to identify remaining open issues for further developments. This paper describes the systematic approach that consists of five elements in a step-by-step approach to perform a meaningful model IUQ and validation as well as some good-practice guideline recommendations for each step. (author)
Availability note (English)
Available from doi: http://dx.doi.org/10.1080/00295639.2020.1759310Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Science and Engineering
- Journal Volume
- 194
- Journal Issue
- no.8-9
- Journal Page Range
- p. 721-736
- ISSN
- 0029-5639
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54065882
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- BENCHMARKS; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; SAFETY ANALYSIS; THERMAL HYDRAULICS
- Descriptors DEC
- ENERGY; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS