[3] International Atomic Energy Agency. Best estimate safety analysis f nuclear power plants: uncertainty evaluation[R]. Vienna: International Atomic Energy Agency, 2008.

[4] Briggs L L. Uncertainty quantification approaches f advanced react analyses[R]. Chicago: Argonne National Labaty, 2008.

[5] Prošek A, Mavko B. The state-of-the-art theory and applications of best-estimate plus uncertainty methods[J]. Nuclear Technology, 158, 69-79(2007).

[7] Wensauer A, Distler I, Heins L. Probabilistic uncertainty analysis applied to fuel rod design[M]Spitzer C, Schmocker U, Dang V N. Probabilistic Safety Assessment Management. London: Springer, 2004: 27912796.

[8] Boule A. Imptance of uncertainty quantification in unclear fuel behavi modeling simulation[C]Best Estimate Plus Uncertainty International Conference. Lucca, 2018.

[9] Bratton R N, Jessee M A, Wieselquist W A, et al. Rod internal pressure distribution and uncertainty analysis using FRAPCON[J]. Nuclear Technology, 197, 47-63(2017).

[10] HernezSolis A, Ekberg C, Jensen A O, et al. Statistical uncertainty analyses of void fraction predictions using two different sampling strategies: Latin hypercube simple rom sampling[C]Proceedings of the 18th International Conference on Nuclear Engineering. Xi’an, China: ASNE, 2010: 10591068.

[11] Ikonen T, Tulkki V. The importance of input interactions in the uncertainty and sensitivity analysis of nuclear fuel behavior[J]. Nuclear Engineering and Design, 275, 229-241(2014).

[13] Wang J R, Tsai C W, Lin H T, et al. Perfming uncertainty analysis of IIST facility SBLOCA by TRACE DAKOTA[R]. Washington DC: Nuclear Regulaty Commission, 2013.

[16] Sun Shanze. Nonparametric statistics hout[M]. Beijing: Peking University Press, 2020: 147150)