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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2014.1
- 수록면
- 313 - 342 (30page)
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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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참고문헌 (18)
참고문헌 신청
/ 1976 / Core Design and Operating Data for Cycles 1 and 2of Quad Cities 1
/ 2005 / Benchmark on the KRITZ-2 LEU and MOX Critical Experiments ? Final Report
/ 2007 / International Handbook of Evaluated Reactor Physics Benchmark Experiments / Nuclear Energy Agency
/ 2009 / International Reactor Physics Experiments Database Project (IRPhE) / Nuclear Energy Agency
A. J. Koning / 2005 / TENDL-2008: Consistent TALYS-base Evaluated Nuclear Data Library including covariance data
/ 2005 / Benchmark on the KRITZ-2 LEU and MOX Critical Experiments ? Final Report
/ 2007 / International Handbook of Evaluated Reactor Physics Benchmark Experiments / Nuclear Energy Agency
/ 2009 / International Reactor Physics Experiments Database Project (IRPhE) / Nuclear Energy Agency
A. J. Koning / 2005 / TENDL-2008: Consistent TALYS-base Evaluated Nuclear Data Library including covariance data
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