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RYAN N. BRATTON,M.AVRAMOVA,K. IVANOV 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.3
A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark forUncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of availableuncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safetycalculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phaseseach of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known asthe “Neutronics Phase”, which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughoutsteady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured dataare available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, andVVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments andthe SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutronnuclidereactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters ofneutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuityfactors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done toreduce uncertainties in key nuclide reaction uncertainties (i.e.: 238U radiative capture and inelastic scattering (n, n’) as well asthe average number of neutrons released per fission event of 239Pu).
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Bratton, Ryan N.,Avramova, M.,Ivanov, K. Korean Nuclear Society 2014 Nuclear Engineering and Technology Vol.46 No.3
A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).
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