The discussion centers around recommendations for nuclear reaction modeling software, specifically for simulating different fuel pellet shapes. MCNP (Monte Carlo N-Particle Transport Code) is highlighted as an industry-standard simulation package suitable for this purpose. Key considerations for modeling include fission density, self-shielding effects, and the geometry of the pellet shapes. The conversation also touches on the need to model neutron capture, scattering, and the reactions of fission products alongside the fuel materials such as Uranium, Plutonium, and Thorium.
PREREQUISITESNuclear engineers, researchers in nuclear physics, and anyone involved in modeling nuclear reactions and fuel pellet designs will benefit from this discussion.
What does one mean by 'model nuclear reactions' in the context of 'different pellet shapes'?Todobek said:model nuclear reactions