[1] Hauff Volker, Deutsche Risikostudie Kernkraftwerke: Eine Untersuchung zu dem durch Störfälle in Kernkraftwerken verursachten Risiko, Bonn, Germany (1980).
[2] B. Chatterjee, D. Mukhopadhyay, H.G. Lele, A.K. Ghosh, H.S. Kushwaha, P. Groudev, B. Atanasova, Analyses for VVER-1000/320 reactor for spectrum of break sizes along with SBO, Ann. Nucl. Energy 37 (2010) 359-370.
[3] S.K. Mousavian, F. D’Auria, M.A. Salehi, Analysis of natural circulation phenomena in VVER-1000, Nucl. Eng. Des 229 (2004) 25-46.
[4] G. Heo, S.K. Lee, Design evaluation of emergency core cooling systems using Axiomatic Design, Nucl. Eng. Des 237 (2007) 38-46.
[5] RELAP5 Code Development Team, RELAP/MOD3 Code manual, Idaho national engineering and environmental laboratory, vol. 1-6. Idaho 83415 (1995).
[6] Atomic Energy Organization of Iran (AEOI), Final safety analysis report (FSAR) for BUSHEHR VVER-1000 reactor. Tehran, Iran (2007).
[7] S.M. Altaha, M. Mansouri, G. Jahanfarnia, Analysis of the small break loss of coolant accident in the VVER-1000/V446 reactor, Kerntechnik 80 (6) (2015) 545-556.
[8] Glaeser Horst, GRS method for uncertainty and sensitivity evaluation of code results and applications, Sci. Technol. Nucl. Ins. 2008 (2008) 1-7.
[9] USNRC, 10 CFR 50.46, Acceptance criteria for emergency core cooling systems for light water nuclear power reactors, and Appendix K, ECCS evaluation models, to 10 CFR Part 50, code of federal regulations (1989).
[10] Glaeser Horst, Summary of existing uncertainty methods, Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH NEA/CSNI/R (2013)8/PART2.
[11] M.G. Cox, M.P. Dainton, P.M. Harris, Software Specifications for Uncertainty Calculation and Associated Statistical Analysis, NPL Report CMSC 10/01(2001).
[12]
Lehman Ann, Jump For Basic Univariate and Multivariate Statistics: A Step-by-step Guide, Cary, NC: SAS Press. 123. ISBN 1-59047-576-3(2005).
[13] E. Burchill William, Physical phenomena of a Small-Break loss-of-coolant accident in a PWR, Nucl. Saf. 23 (5) (1982) 525-536.
)