Towards an uncertainty quantification methodology with CASMO-5
Description
We present the development of an uncertainty quantification (UQ) methodology for the CASMO-5 lattice physics code, used extensively at the Paul Scherrer Institut for standalone neutronics calculations, as well as the generation of nuclear fuel segment libraries for the downstream core simulator, SIMULATE-3. We focus here on propagation of nuclear data uncertainties and describe the framework required for 'black box' UQ--in this case minor modifications of the code are necessary to allow perturbation of the CASMO-5 nuclear data library. We then implement a basic rst-order UQ method, direct perturbation, which directly produces sensitivity coefficients and when folded with the input nuclear data variance-covariance matrix (VCM) yields output uncertainties in the form of an output VCM. We discuss the implementation, including how to map the VCMs of a different group structure to the code library group structure (in our case the ENDF/B-VII-based 586-group library in CASMO-5), present some results for pin cell calculations, and conclude with future work. (author)
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Additional details
Publishing Information
- Imprint Pagination
- 14 p.
- Report number
- INIS-BR--16316
Conference
- Title
- international conference on mathematics and computational methods applied to nuclear science and engineering
- Acronym
- M and C 2011
- Dates
- 8-12 May 2011
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 47076438
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; CROSS SECTIONS; DATA COVARIANCES; EIGENVALUES; NEUTRONS; NUCLEAR FUELS; PERTURBATION THEORY; REACTOR CORES; REACTOR LATTICES; SENSITIVITY ANALYSIS
- Descriptors DEC
- BARYONS; COMPUTER CODES; ELEMENTARY PARTICLES; ENERGY SOURCES; FERMIONS; FUELS; HADRONS; MATERIALS; NUCLEONS; REACTOR COMPONENTS; REACTOR MATERIALS; SIMULATION