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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 1,148 - 1,155 (8page)
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This work presents two different methods for quantifying and propagating the uncertainty associated with fuel composition at end of life for cask criticality calculations. The first approach, the computational approach uses parametric uncertainty including those associated with nuclear data, fuel geometry, material composition, and plant operation to perform forward depletion on Monte-Carlo sampled inputs. These uncertainties are based on experimental and prior experience in criticality safety. The second approach, the data-driven approach relies on using radiochemcial assay data to derive code bias information.The code bias data is used toperturb the isotopic inventory in the data-drivenapproach. Forboth approaches, the uncertainty in keff for the cask is propagated by performing forward criticality calculations on sampled inputs using the distributions obtained from each approach. It is found that the data driven approach yielded a higher uncertainty than the computational approach by about 500 pcm. An exploration is also done to see if considering correlation between isotopes at end of life affects keff uncertainty, and the results demonstrate an effect of about 100 pcm.
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참고문헌 (22)
참고문헌 신청
G. Radulescu / 2009 / Sensitivity and uncertainty analysis of commercial reactor criticals for burnup credit / Nucl. Technol 167(2):268~287
D. Rochman / 2012 / Propagation of 235,236,238U and 239Pu nuclear data uncertainties for a typical PWR fuel element / Nucl. Technol 179(3):323~338
M. Pecchia / 2015 / Criticality safety evaluation of a swiss wet storage pool using a global uncertainty analysis methodology / Ann. Nucl. Energy 83:226~235
박호진 / 2018 / Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD / Nuclear Engineering and Technology 50(7):1043~1050
W. A. Metwally / 2019 / On the over-conservatism of the 5% depletion uncertainty rule in spent fuel criticality analyses / Ann. Nucl. Energy 125:1~11
D. Rochman / 2012 / Propagation of 235,236,238U and 239Pu nuclear data uncertainties for a typical PWR fuel element / Nucl. Technol 179(3):323~338
M. Pecchia / 2015 / Criticality safety evaluation of a swiss wet storage pool using a global uncertainty analysis methodology / Ann. Nucl. Energy 83:226~235
박호진 / 2018 / Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD / Nuclear Engineering and Technology 50(7):1043~1050
W. A. Metwally / 2019 / On the over-conservatism of the 5% depletion uncertainty rule in spent fuel criticality analyses / Ann. Nucl. Energy 125:1~11
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