Summary and status of OECD/NEA UAM-LWR Benchmark
- 1. Department of Mechanical and Nuclear Engineering, Pennsylvania State University, University Park, PA (United States)
- 2. INSTN - CEA Saclay, Gif sur Yvette, (France)
- 3. OECD/NEA Data Bank, Issy-les-Moulineaux (France)
Description
In recent years there has been an increasing demand from nuclear research, industry, safety and regulation for best estimate predictions to be provided with their confidence bounds. Consequently OECD/NEA has initiated an international Uncertainty Analysis in Modeling (UAM) benchmark focused on uncertainty analysis in best-estimate coupled code calculations for design, operation, and safety analysis of LWRs. The title of this benchmark is: "Benchmarks for uncertainty analysis in modelling (UAM) for the design, operation and safety analysis of LWRs", or often referred to as "OECD/NEA UAM-LWR Benchmark". Reference systems and scenarios for coupled code analysis are defined to study the uncertainty effects for all stages of the system calculations. Measured data from plant operation are available for the chosen scenarios. The general frame of the OECD/NEA UAM LWR benchmark consists of three phases with different exercises for each phase. This paper summarizes the benchmark activity and discusses the status of each phase and exercise. Selected results are shown to illustrate the technical approach in defining different exercises and findings from benchmark analysis. For the first time this benchmarks aims to determine the uncertainty in LWR system calculations at all stages of a coupled reactor physics/thermal-hydraulics/fuel performance calculation. The full chain of uncertainty propagation from basic data, engineering uncertainties, across different scales (multi-scale), and physics phenomena (multi-physics) are tested on a number of benchmark exercises for which experimental data are available and for which the power plant details have been released. As part of this effort, the development and assessment of different methods or techniques to account for the uncertainties in the calculations are investigated and reported, which contributes to the state-of-the-art in this area. (author)
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Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the international conference on physics of reactors (PHYSOR2014)
- Imprint Pagination
- 5489 p.
- Journal Page Range
- 18 p.
- Report number
- JAEA-Conf--2014-003
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR2014
- Dates
- 28 Sep - 3 Oct 2014
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47042703
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BWR TYPE REACTORS; COMPUTER CALCULATIONS; FUEL MANAGEMENT; REACTOR KINETICS; REACTOR OPERATION; REACTOR PHYSICS; REACTOR SAFETY; SAFETY ANALYSIS; THERMAL HYDRAULICS; WWER TYPE REACTORS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; KINETICS; MANAGEMENT; MECHANICS; NUCLEAR MATERIALS MANAGEMENT; OPERATION; PHYSICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: PAPERS, Paper ID: a11_1104813.pdf; 4 refs., 4 figs., 6 tabs.