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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.9
- 수록면
- 2,830 - 2,838 (9page)
- DOI
- https://doi.org/10.1016/j.net.2021.03.014
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초록· 키워드
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This work deals with the assessment of the burnup capabilities of the Serpent Monte Carlo code topredict spent nuclear fuel (SNF) isotopic concentrations for low-enriched uranium (LEU) fuel at differentburnup levels up to 47 MWd/kgU. The irradiation of six UO2 experimental samples in three differentVVER-1000 reactor units has been simulated and the predicted concentrations of actinides up to 244Cmhave been compared with the corresponding measured values. The results show a global good agreementbetween calculated and experimental concentrations, in several cases within the margins of the nucleardata uncertainties and in a few cases even within the reported experimental uncertainties. The differences in the performances of the JEFF3.1.1, ENDF/B-VII.1 and ENDF/B-VIII.0 nuclear data libraries (NDLs)have also been assessed and the use of the newly released ENDF/B-VIII.0 library has shown an increasedaccuracy in the prediction of the C/E's for some of the actinides considered, particularly for the plutonium isotopes. This work represents a step forward towards the validation of advanced simulation toolsagainst post irradiation experimental data and the obtained results provide an evidence of the capabilities of the Serpent Monte-Carlo code with the associated modern NDLs to accurately compute SNFnuclide inventory concentrations for VVER-1000 type reactors
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참고문헌 (5)
참고문헌 신청
M. B Chadwick / 2011 / ENDF/B-VII.1 nuclear data for science and Technology:cross sections, covariances, fission product yields and decay data / Nucl. Data Sheets 112(12):2887~2996
김정석 / 2015 / ANALYSIS OF HIGH BURNUP PRESSURIZED WATER REACTOR FUEL USING URANIUM, PLUTONIUM, NEODYMIUM, AND CESIUM ISOTOPE CORRELATIONS WITH BURNUP / Nuclear Engineering and Technology 47(7):924~933
T. Takeda / 1999 / Estimation of error propagation in monte-CarloBurnup calculations / J. Nucl. Sci. Technol 36(2):738~745
Zheng Lei / 2020 / Criticality benchmarking of ENDF/B-Ⅷ.0 and JEFF-3.3 neutron data libraries with RMC code / Nuclear Engineering and Technology 52(9):1917~1925
Bamidele Ebiwonjumi / 2021 / Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters / Nuclear Engineering and Technology 53(3):715~731
김정석 / 2015 / ANALYSIS OF HIGH BURNUP PRESSURIZED WATER REACTOR FUEL USING URANIUM, PLUTONIUM, NEODYMIUM, AND CESIUM ISOTOPE CORRELATIONS WITH BURNUP / Nuclear Engineering and Technology 47(7):924~933
T. Takeda / 1999 / Estimation of error propagation in monte-CarloBurnup calculations / J. Nucl. Sci. Technol 36(2):738~745
Zheng Lei / 2020 / Criticality benchmarking of ENDF/B-Ⅷ.0 and JEFF-3.3 neutron data libraries with RMC code / Nuclear Engineering and Technology 52(9):1917~1925
Bamidele Ebiwonjumi / 2021 / Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters / Nuclear Engineering and Technology 53(3):715~731
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