Generic CANDU 6 plant severe accident analysis employing SCAPSIM/RELAP5 code

CATHENA: A thermalhydraulic code for CANDU analysis

B. Hanna · Nuclear Engineering and Design · 1998 · 86 citations

Engineering, Calibration, Thermal Analysis +4

Quantitative assessment of thermal–hydraulic codes used for heavy water reactor calculations

Andrej Prošek, Francesco Saverio D'Auria, D. J. Richards et al. · Nuclear Engineering and Design · 2005 · 24 citations

Thermodynamic Modelling, Core Thermal Hydraulics, Engineering +13

Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents

Hiroyasu Mochizuki, Mitsutaka H. Koike, Takaaki Sakai · Nuclear Engineering and Design · 1993 · 14 citations

Engineering, Civil Engineering, Core Coolability +4

SCDAP/RELAP5 application to CANDU6 fuel channel analysis under postulated LLOCA/LOECC conditions

Mirea Mladin, Daniel Dupleac, Ilie Prisecaru · Nuclear Engineering and Design · 2008 · 14 citations

Lloca/loecc Conditions, Engineering, Scdap/relap5 Application +1