Perturbation-Theory-Based Sensitivity and Uncertainty Analysis with CASMO-4
Creators
- 1. VTT Technical Research Centre of Finland, P.O. Box 1000, VTT 02044, Finland
Description
The topic of this paper is the development of sensitivity and uncertainty analysis capability to the reactor physics code CASMO-4 in the context of the UAM (Uncertainty Analysis in Best-Estimate Modelling for Design, Operation, and Safety Analysis of LWRs) benchmark. The sensitivity analysis implementation is based on generalized perturbation theory, which enables computing the sensitivity profiles of reaction rate ratios efficiently by solving one generalized adjoint system for each response. Both the theoretical background and the practical guidelines for modifying a deterministic transport code to compute the generalized adjoint solutions and sensitivity coefficients are reviewed. The implementation to CASMO-4 is described in detail. The developed uncertainty analysis methodology is deterministic, meaning that the uncertainties are computed based on the sensitivity profiles and covariance matrices for the uncertain nuclear data parameters. The main conclusions related to the approach used for creating a covariance library compatible with the cross-section libraries of CASMO-4 are presented. Numerical results are given for a lattice physics test problem representing a BWR, and the results are compared to the TSUNAMI-2D sequence in SCALE 6.1.
Files
10.1155_2012_157029.pdf
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Additional details
Identifiers
- DOI
- 10.1155/2012/157029;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2012
- Journal Page Range
- 1-11
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ADJOINT FLUX; BENCHMARKS; BWR TYPE REACTORS; CROSS SECTIONS; DATA COVARIANCES; DETERMINISTIC ESTIMATION; IMPLEMENTATION; LIBRARIES; NEUTRON PHYSICS; NUCLEAR DATA COLLECTIONS; PERTURBATION THEORY; REACTION KINETICS; REACTOR KINETICS; SAFETY ANALYSIS; SENSITIVITY; SENSITIVITY ANALYSIS
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; KINETICS; NEUTRON FLUX; PHYSICS; POWER REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- © Author(s)
- Notes
- Record automatically processed