Hi forum,

I’m relatively new to OpenMC and working on a research about reactor’s power peaking factor. Could I calculate power peaking factor (both radially and axially) from fission-q-prompt tally score?

Best regards,

Fadil

Hi forum,

I’m relatively new to OpenMC and working on a research about reactor’s power peaking factor. Could I calculate power peaking factor (both radially and axially) from fission-q-prompt tally score?

Best regards,

Fadil

Hi @fadilnaufalwahas and welcome to the forum. I would recommend using the `fission-q-recoverable`

score because it includes energy from delayed neutrons, photons, and electrons whereas `fission-q-prompt`

does not. Be aware that these scores don’t account for non-fission energy deposition (such as production of photons from (n,γ) reactions and their subsequent deposition), so if you really want to do this rigorously, you need to run a coupled neutron–photon simulation and tally the `heating`

score.

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Thank you @paulromano

Referring to the posts you made [1] [2], I would like to know if I understood the calculation. The power of fuel (in watt) could be calculated by:

P (watt) = ( F * Pr * (vf / f) * c ) / ( Q * keff )

with

F = tally `fission-q-recoverable`

(eV/source)

vf = tally `nu-fission`

(neutron/source)

f = tally `fission`

(fission/source)

Pr = known reactor power (J/s)

Q = 3.2E-11 J/fission (for U-235)

keff = neutron multiplication factor (neutron/source)

c = 1.6E-19 watt.s/eV

Is my interpretation correct?

Best regards,

Fadil

@fadilnaufalwahas The method I had outlined in those earlier posts is probably not the best, or most straightforward, way to perform a power normalization. There is now a section in our user’s guide about normalizing tally results that gives good advice about how to do this.

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