1. “Reactivity Accident Tests Results and Analyses for the SPERT III E-Core a Small Oxide-Fueled, Pressurized Water Reactor,” Ido-17281;Cardell,1969
2. Qualification of CASMO5/SIMULATE-3K against the SPERT III E-core cold start-up experiments;Grandi,2012
3. Validation of CASMO/SIMLATE-3K using the PSERT III E-core: cold start-up, hot start-up, hot standby and full power conditions;Grandi,2014
4. PSI methodologies for nuclear data uncertainty propagartion with CASMO-5M and MCNPX: results for OECD/NEA UAM benchmark pahse I;Wieselquist;Sci. Technol. Nucl. Inst,2013
5. Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles;Leray;Ann. Nucl. Energy,2017