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I am using detectors to keep track of the number of neutrons that are lost due to capture in each material (ie. clad, water, etc..) Within the detectors the material reaction -2 gives the total capture. What capture reactions are contained within this total capture? How is it different than the ENDF...
- Thu Jan 17, 2013 11:26 pm
- Forum: Validation
- Topic: Lattice calculations, Serpent vs. MCNP
- Replies: 13
- Views: 22064
I was working on a benchmark between mcnp and serpent. In serpent I have a problem very similar to your pwr single pin but without the depletion. When I used a finite square cylinder with periodic boundary conditions I get a smaller and less accurate multiplication value than when I use an infinite ...