1 Pusa M. Incorporating sensitivity and uncertainty analysis to a lattice physics code with application to CASMO-4[J]. Annals of Nuclear Energy, 2012, 40(1):153-162. DOI:10.1016/j.anucene.2011.10.013. 2 Mercatali L, Ivanov K, Sanchez V H. SCALE modeling of selected neutronics test problems within the OECD UAM LWR's benchmark[J]. Science & Technology of Nuclear Installations, 2013, (2):573697. DOI:10.1155/2013/573697. 3 Wan C, Cao L, Wu H, et al. Code development for eigenvalue total sensitivity analysis and total uncertainty analysis[J]. Annals of Nuclear Energy, 2015, 85:788-797. DOI:10.1016/j.anucene.2015.06.036. 4 Foad B, Takeda T. Sensitivity and uncertainty analysis for UO2, and MOX, fueled PWR, cells[J]. Annals of Nuclear Energy, 2015, 75(1):595-604. DOI:10.1016/j.anucene. 2014.08.068. 5 Xu J Y, Ma X B, Lu F, et al. Nuclear data and fuel/assembly manufacturing uncertainties analysis and preliminary validation of SUACL[EB/OL]. 2017. https://arxiv.org/abs/1704.06601. 6 Helton J C, Davis F J, Johnson J D. A comparison of uncertainty and sensitivity analysis results obtained with random and Latin hypercube sampling[J]. Reliability Engineering & System Safety, 2005, 89(3):305-330. DOI:10.1016/j.ress.2004.09.006. 7 Helton J C, Davis F J. Latin hypercube sampling and the propagation of uncertainty in analyses of complex systems[J]. Reliability Engineering & System Safety, 2003, 81(1):23-69. DOI:10.1016/S0951-8320(03)00058-9. 8 Chiba G, Kawamoto Y, Tsuji M, et al. Estimation of neutronics parameter sensitivity to nuclear data in random sampling-based uncertainty quantification calculations[J]. Annals of Nuclear Energy, 2015, 75:395-403. DOI:10.1016/j.anucene.2014.08.049. 9 Helton J C, Johnson J D, Sallaberry C J, et al. Survey of sampling-based methods for uncertainty and sensitivity analysis[J]. Reliability Engineering & System Safety, 2006, 91(10-11):1175-1209. DOI:10.1016/j.ress.2005. 11.017. 10 Wilks S S. Determination of sample sizes for setting tolerance limits[J]. Annals of Mathematical Statistics, 1941, 12(1):91-96. 11 潘昕怿, 兰兵, 张春明, 等. 多群核数据不确定性对堆芯物理计算的影响[J]. 核技术, 2016, 39(1):010602. DOI:10.11889/j.0253-3219.2016.hjs.39.010602. PAN Xinyi, LAN Bing, ZHANG Chunming, et al. Effect of uncertainty of multi-group nuclear data on core physics calculation[J]. Nuclear Techniques, 2016, 39(1):010602. DOI:10.11889/j.0253-3219.2016.hjs.39.010602. 12 Herman M, Trkov A. ENDF-6 formats manual[M]. 2009. 13 Chadwick M B, Herman M, Obložinský P, et al. ENDF/B-VⅡ.1 Nuclear data for science and technology:cross sections, covariances, fission product yields and decay data[J]. Nuclear Data Sheets, 2011, 112(12):2887-2996. DOI:10.1016/j.nds.2011.11.002. 14 Ivanov K, Avramova M, Kamerow S, et al. Benchmark for uncertainty analysis in modeling (UAM) for design, operation and safety analysis of LWRs (NEA-NSC-DOC-2013-7)[R]. Vienna, Austria:Nuclear Energy Agency of the OECD, 2013. 15 万承辉, 曹良志, 吴宏春, 等. 基于抽样方法的特征值不确定度分析[J]. 原子能科学技术, 2015, 49(11):1954-1960. DOI:10.7538/yzk.2015.49.11.1954. WAN Chenghui, CAO Liangzhi, WU Hongchun, et al. Uncertainty analysis of the eigenvalue based on sampling method[J]. Atomic Energy Science and Technology, 2015, 49(11):1954-1960. DOI:10.7538/yzk.2015.49.11.1954. |