Discussion of OECD LWR Uncertainty Analysis in Modelling Benchmark
Creators
- 1. The Pennsylvania State University, University Park (United States)
- 2. CEA, Saclay (France)
- 3. NEA/OECD, Paris (France)
Description
The demand for best estimate calculations in nuclear reactor design and safety evaluations has increased in recent years. Uncertainty quantification has been highlighted as part of the best estimate calculations. The modelling aspects of uncertainty and sensitivity analysis are to be further developed and validated on scientific grounds in support of their performance and application to multi-physics reactor simulations. The Organization for Economic Co-operation and Development (OECD) / Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC) has endorsed the creation of an Expert Group on Uncertainty Analysis in Modelling (EGUAM). Within the framework of activities of EGUAM/NSC the OECD/NEA initiated the Benchmark for Uncertainty Analysis in Modelling for Design, Operation, and Safety Analysis of Light Water Reactor (OECD LWR UAM benchmark). The general objective of the benchmark is to propagate the predictive uncertainties of code results through complex coupled multi-physics and multi-scale simulations. The benchmark is divided into three phases with Phase I highlighting the uncertainty propagation in stand-alone neutronics calculations, while Phase II and III are focused on uncertainty analysis of reactor core and system respectively. This paper discusses the progress made in Phase I calculations, the Specifications for Phase II and the incoming challenges in defining Phase 3 exercises. The challenges of applying uncertainty quantification to complex code systems, in particular the time-dependent coupled physics models are the large computational burden and the utilization of non-linear models (expected due to the physics coupling). (authors)
Files
45107571.pdf
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(2.2 MB)
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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. 138-150, 692-740
- 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
- 45107571
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTER CODES; COMPUTERIZED SIMULATION; COORDINATED RESEARCH PROGRAMS; CROSS SECTIONS; DATA COVARIANCES; DETERMINISTIC ESTIMATION; NUCLEAR DATA COLLECTIONS; PROBABILISTIC ESTIMATION; REACTOR CORES; REACTOR SAFETY; SAFETY ANALYSIS; SAFETY MARGINS; SENSITIVITY ANALYSIS; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; TIME DEPENDENCE; TRANSIENTS; WATER COOLED REACTORS
- Descriptors DEC
- CALCULATION METHODS; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR COMPONENTS; REACTORS; RESEARCH PROGRAMS; SAFETY; SIMULATION
Optional Information
- Notes
- 11 refs., 62 p.