Towards an Industrial Application of Statistical Uncertainty Analysis Methods to Multi-physical Modelling and Safety Analyses
- 1. Tractebel Engineering - GDF SUEZ, Avenue Ariane 7, B-1200 Brussels (Belgium)
Description
Since 1980's, Tractebel Engineering (TE) has being developed and applied a multi-physical modelling and safety analyses capability, based on a code package consisting of the best estimate 3D neutronic (PANTHER), system thermal hydraulic (RELAP5), core sub-channel thermal hydraulic (COBRA-3C), and fuel thermal mechanic (FRAPCON/FRAPTRAN) codes. A series of methodologies have been developed to perform and to license the reactor safety analysis and core reload design, based on the deterministic bounding approach. Following the recent trends in research and development as well as in industrial applications, TE has been working since 2010 towards the application of the statistical sensitivity and uncertainty analysis methods to the multi-physical modelling and licensing safety analyses. In this paper, the TE multi-physical modelling and safety analyses capability is first described, followed by the proposed TE best estimate plus statistical uncertainty analysis method (BESUAM). The chosen statistical sensitivity and uncertainty analysis methods (non-parametric order statistic method or bootstrap) and tool (DAKOTA) are then presented, followed by some preliminary results of their applications to FRAPCON/FRAPTRAN simulation of OECD RIA fuel rod codes benchmark and RELAP5/MOD3.3 simulation of THTF tests. (authors)
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45107577.pdf
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Additional details
Publishing Information
- Imprint Title
- OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations - Workshop Proceedings
- Imprint Pagination
- 1166 p.
- Journal Page Range
- p. 216-233, 854-877
- Report number
- NEA-CSNI-R--2013-8
Conference
- Title
- OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations
- Dates
- 16-18 Nov 2011
- Place
- Barcelona (Spain)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 45107577
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ACCURACY; BENCHMARKS; COMPARATIVE EVALUATIONS; COMPUTER CODES; COMPUTERIZED SIMULATION; DATA COVARIANCES; EXPERIMENTAL DATA; LICENSING PROCEDURES; PROBABILISTIC ESTIMATION; REACTOR SAFETY; SAFETY ANALYSIS; SENSITIVITY ANALYSIS; STATISTICS; TEST FACILITIES; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ADMINISTRATIVE PROCEDURES; CALCULATION METHODS; DATA; EVALUATION; FLUID MECHANICS; HYDRAULICS; INFORMATION; MATHEMATICS; MECHANICS; NUMERICAL DATA; SAFETY; SIMULATION
Optional Information
- Notes
- 27 refs., 42 p.