I. Nuclear Power Systems 30% A. Nuclear Engineering Science 17.5% 1. Reactor core analysis (e.g., neutron balance, diffusion calculations, fuel depletion, transient analysis, neutron reflection) 2. Reactor safety analysis (e.g., LOCA, transient thermal-hydraulic behavior, fuel-clad mechanical interactions, chemical interactions) 3. Energy release from nuclear processes (e.g., fission, fission product decay, neutron capture, prompt gamma) 4. Thermal-hydraulic analysis (e.g., heat transfer, fluid dynamics, natural circulation, critical heat flux, departure from nucleate boiling [DNB], peak centerline temperature, peak clad temperature, hot channel factor, flow oscillations) 5. Probabilistic risk assessment (PRA) (e.g., fault-tree and event-tree analysis, minimum cut sets, probability distribution functions and cumulative distribution functions, level 1-core damage, level 2-containment response, level 3-environmental effects, Bayesian statistics, common-cause failures, initiating & failure data collection and analysis, human reliability analysis, shutdown/low power, external events [e.g., floods, seismic events], quantitative risk analysis [QRA])