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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.3
- 수록면
- 715 - 731 (17page)
- DOI
- https://doi.org/10.1016/j.net.2020.07.012
이용수
초록· 키워드
오류제보하기
Uncertainties are calculated for pressurized water reactor (PWR) spent nuclear fuel (SNF) characteristics.
The deterministic code STREAM is currently being used as an SNF analysis tool to obtain isotopic inventory,radioactivity, decay heat, neutron and gamma source strengths. The SNF analysis capability ofSTREAM was recently validated. However, the uncertainty analysis is yet to be conducted. To estimate theuncertainty due to nuclear data, STREAM is used to perturb nuclear cross section (XS) and resonanceintegral (RI) libraries produced by NJOY99. The perturbation of XS and RI involves the stochastic samplingof ENDF/B-VII.1 covariance data. To estimate the uncertainty due to modeling parameters (fueldesign and irradiation history), surrogate models are built based on polynomial chaos expansion (PCE)and variance-based sensitivity indices (i.e., Sobol’ indices) are employed to perform global sensitivityanalysis (GSA). The calculation results indicate that uncertainty of SNF due to modeling parameters arealso very important and as a result can contribute significantly to the difference of uncertainties due tonuclear data and modeling parameters. In addition, the surrogate model offers a computationally efficientapproach with sig
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참고문헌 (29)
참고문헌 신청
최지원 / 2019 / Verification and Validation of STREAM/RAST-K for PWR Analysis / Nuclear Engineering and Technology 51(2):356~368
Nhan Nguyen Trong Mai / 2020 / Extension of Monte Carlo code MCS to spent fuel cask shielding analysis / International Journal of Energy Research 44(10):8089~8102
B. Ebiwonjumi / 2018 / Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory / Ann. Nucl. Energy 120:431~449
B. Ebiwonjumi / 2019 / Verification and validation of radiation source term capabilities in STREAM / Ann. Nucl. Energy 124:80~87
B. T. Rearden / 2009 / TSUNAMI Primer: A Primer for Sensitivity/Uncertainty Calculations with SCALE
Nhan Nguyen Trong Mai / 2020 / Extension of Monte Carlo code MCS to spent fuel cask shielding analysis / International Journal of Energy Research 44(10):8089~8102
B. Ebiwonjumi / 2018 / Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory / Ann. Nucl. Energy 120:431~449
B. Ebiwonjumi / 2019 / Verification and validation of radiation source term capabilities in STREAM / Ann. Nucl. Energy 124:80~87
B. T. Rearden / 2009 / TSUNAMI Primer: A Primer for Sensitivity/Uncertainty Calculations with SCALE
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