참고문헌
- G. Radulescu, D.E. Mueller, J.C. Wagner, Sensitivity and uncertainty analysis of commercial reactor criticals for burnup credit, Nucl. Technol. 167 (2) (2009) 268-287. https://doi.org/10.13182/NT09-A8963
-
D. Rochman, A. Koning, D. Da Cruz, Propagation of
$^{235,236,238}U$ and$^{239}Pu$ nuclear data uncertainties for a typical PWR fuel element, Nucl. Technol. 179 (3) (2012) 323-338. https://doi.org/10.13182/NT11-61 - M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz, Criticality safety evaluation of a swiss wet storage pool using a global uncertainty analysis methodology, Ann. Nucl. Energy 83 (2015) 226-235. https://doi.org/10.1016/j.anucene.2015.03.052
- H.J. Park, D.H. Lee, B.K. Jeon, H.J. Shim, Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD, Nucl. Eng. Technol. 50 (7) (2018) 1043-1050. https://doi.org/10.1016/j.net.2018.06.003
- W.A. Metwally, A.S. Alawad, B.A. Khuwaileh, On the over-conservatism of the 5% depletion uncertainty rule in spent fuel criticality analyses, Ann. Nucl. Energy 125 (2019) 1-11. https://doi.org/10.1016/j.anucene.2018.10.048
- M.I. Radaideh, D. Price, T. Kozlowski, Criticality and uncertainty assessment of assembly misloading in BWR transportation cask, Ann. Nucl. Energy 113 (2018) 1-14. https://doi.org/10.1016/j.anucene.2017.11.006
- A. Papoulis, S.U. Pillai, Probability, Random Variables, and Stochastic Processes, Tata McGraw-Hill Education, 2002.
- I. Gauld, Strategies for application of isotopic uncertainties in burnup credit, in: Tech. rep., NUREG/CR-6811, ORNL/TM-2001/257, US Nuclear Regulatory Commission, Oak Ridge National Laboratory, United States, 2003.
- H. Yun, K. Park, W. Choi, S.G. Hong, An efficient evaluation of depletion uncertainty for a GBC-32 dry storage cask with PLUS7 fuel assemblies using the Monte Carlo uncertainty sampling method, Ann. Nucl. Energy 110 (2017) 679-691. https://doi.org/10.1016/j.anucene.2017.07.020
- D. Price, M.I. Radaideh, D. O'Grady, T. Kozlowski, Advanced bwr criticality safety part ii: cask criticality, burnup credit, sensitivity, and uncertainty analyses, Prog. Nucl. Energy 115 (2019) 126-139. https://doi.org/10.1016/j.pnucene.2019.03.039
- M.I. Radaideh, D. Price, D. O'Grady, T. Kozlowski, Advanced BWR criticality safety part I: model development, model validation, and depletion with uncertainty analysis, Prog. Nucl. Energy 113 (2019) 230-246. https://doi.org/10.1016/j.pnucene.2019.01.010
- M.L. Fensin, Optimum Boiling Water Reactor Fuel Design Strategies to Enhance Reactor Shutdown by the Standby Liquid Control System, Master's thesis, University of Florida, 2004.
- D. Mueller, J. Scaglione, J. Wagner, S. Bowman, Computational benchmark for estimated reactivity margin from fission products and minor actinides in BWR burnup credit, in: Tech. rep., NUREG/CR-7157, ORNL/TM-2012/96, US Nuclear Regulatory Commission, Oak Ridge National Laboratory, United States, 2013.
- G. Ilas, H. Liljenfeldt, Decay heat uncertainty for BWR used fuel due to modeling and nuclear data uncertainties, Nucl. Eng. Des. 319 (2017) 176-184. https://doi.org/10.1016/j.nucengdes.2017.05.009
- G. M. Grandi, J. A. Borkowski, Benchmark of SIMULATE-3K against the frigg loop stability experiments, In: Proc. Advances in Nuclear Fuel Management III (ANFM 2003) Hilton Head Island, South Carolina, United States, October 5-8, 2003.
- M. Kruners, G. Grandi, M. Carlssonc, PWR transient xenon modeling and analysis using studsvik CMS, In: Proc. 2010 LWR Fuel Performance/TopFuel/WRFPM Orlando, Florida, United States, September 26-29, 2010.
- S.M. Bowman, Scale 6: comprehensive nuclear safety analysis code system, Nucl. Technol. 174 (2) (2011) 126-148. https://doi.org/10.13182/NT10-163
- A. Hoefer, T. Ivanova, B. Rearden, D. Mennerdahl, O. Buss, Proposal for benchmark phase IV role of integral experiment covariance data for criticality safety validation, in: Tech. rep., Working Party on Nuclear Criticality Safety, OECD Nuclear Energy Agency, France, 2015.
- J.B. Briggs, L. Scott, A. Nouri, The international criticality safety benchmark evaluation project, Nucl. Sci. Eng. 145 (1) (2003) 1-10. https://doi.org/10.13182/NSE03-14
- F. Michel-Sendis, I. Gauld, J. Martinez, C. Alejano, M. Bossant, D. Boulanger, O. Cabellos, V. Chrapciak, J. Conde, I. Fast, et al., SFCOMPO-2.0: an OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data, Ann. Nucl. Energy 110 (2017) 779-788. https://doi.org/10.1016/j.anucene.2017.07.022
- U. Mertyurek, M.W. Francis, I.C. Gauld, SCALE 5 analysis of BWR spent nuclear fuel isotopic compositions for safety studies, in: Tech. rep., ORNL/TM-2010/286, Oak Ridge National Laboratory, United States, 2010.
- M.I. Radaideh, K. Borowiec, T. Kozlowski, Integrated framework for model assessment and advanced uncertainty quantification of nuclear computer codes under bayesian statistics, Reliab. Eng. Syst. Saf. 189 (2019) 357-377. https://doi.org/10.1016/j.ress.2019.04.020
피인용 문헌
- Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations vol.2020, 2020, https://doi.org/10.1155/2020/2764634
- Criticality Analysis for BWR Spent Fuel Based on the Burnup Credit Evaluation from Full Core Simulations vol.11, pp.4, 2020, https://doi.org/10.3390/app11041498