Nuclear Engineering and Design · 2017 · 18 citations · 10 references
EngineeringNuclear EngineeringPhysicsNuclear PhysicsRadiation TransportReactor PhysicsNeutron Transport TheoryNuclear FissionRadiation Transport In MatterRadioactive DecayFission Product Accumulation
10
MCNP-A General Monte Carlo N-Particle Transport Code
Judith F. Briesmeister · 1993 · 5.1K citations
The DOE advanced gas reactor fuel development and qualification program
David A. Petti, John T. Maki, John Hunn et al. · JOM · 2010 · 106 citations