1. C. ANDREADES and P. PETERSON, “Technical Description of the ‘Mark I’ Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant, UCBTH-14-002,” University of California, Berkeley, Department of Nuclear Engineering (2014).
2. L. A. MANN, “ART Accident Analysis Hazards Tests (U),” ORNL-55-22-100, Oak Ridge National Laboratory (1955).
3. C. ANDREADES, “Nuclear Air-Brayton Combined Cycle Power Conversion Design, Physical Performance Estimation and Economic Assessment,” Dissertation, University of California, Berkeley (2015).
4. N. ZWEIBAUM, “Experimental Validation of Passive Safety System Models: Application to Design and Optimization of Fluoride-Salt-Cooled, High-Temperature Reactors,” PhD Thesis, University of California, Berkeley (2015).
5. “Fluoride-Salt-Cooled High Temperature Reactor (FHR) Materials, Fuels and Components White Paper,” UCBTH-12-003, University of California, Berkeley, Thermal Hydraulics Laboratory (July 2013).