Atomic Energy · 2011 · 11 citations · 1 references
EngineeringNuclear EngineeringNuclear MaterialsNuclear PhysicsReactor PhysicsFuel IntegrityNeutron AbsorptionNuclear FissionNuclear Fuel MaterialsReactor Core DesignShielding For Nuclear ReactorsBurnup BehaviorBurnup PhysicsFuel Burnup AnalysisFuel Burnup EffectsReactor Fuel Burnup
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MCNP-A General Monte Carlo N-Particle Transport Code
Judith F. Briesmeister · 1993 · 5.1K citations