Bhasin, V.Srivastava, A.Rastogi, R.Lele, H. G.Vaze, K. K.Ghosh, A. K.Kushwaha, H. S.2010-03-152010-03-152008http://hdl.handle.net/123456789/21025304 bytestext/htmlenadvanced natural circulation nuclear reactorlow-pressure emergency core cooling systemthermal-hydraulic analysisMonte Carlo and first-order reliability methodsBest-estimate evaluation of large-break loss-of-coolant accident for advanced natural circulation nuclear reactorArticle