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Engineering
Nuclear Engineering
MCNP FMESH for Plotting power distribution
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[QUOTE="Grelbr42, post: 6866700, member: 732225"] No. It's not possible. You need to normalize the tallies to reactor power. The tallies are all "per particle started." You need to determine how many particles per second are started. MCNP can't tell what power you are operating at. If it's a reactor, you start with reactor power. Then you divide this by the energy per fission. Typically that's around 200 MeV, but it depends on the details of your reactor design, the isotopes, and few other things. You *can* get MCNP to tell you that. Divide the power by the energy per fission to get the fissions per second. Then you need the average neutrons per fission. You multiply fissions per second by this number to get neutrons per second. An alternative way to normalize is the following. Total the heat deposition (using F6 tallies) in *every* component of the reactor, which will be energy per particle started. Then set this equal to the reactor power. That will let you convert the tally to a number of neutrons per second. [/QUOTE]
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MCNP FMESH for Plotting power distribution
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