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Added comments for new subroutines in tally module.
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1 changed files with 15 additions and 3 deletions
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@ -428,6 +428,11 @@ contains
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cycle
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else
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! If there is no outgoing energy filter, than we only need to
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! score to one bin. For the score to be 'analog', we need to
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! score the number of particles that were banked in the fission
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! bank. Since this was weighted by 1/keff, we multiply by keff
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! to get the proper score.
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score = keff * p % n_bank
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@ -451,7 +456,10 @@ contains
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end subroutine score_analog_tally
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!===============================================================================
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! SCORE_FISSION_EOUT
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! SCORE_FISSION_EOUT handles a special case where we need to store neutron
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! production rate with an outgoing energy filter (think of a fission matrix). In
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! this case, we may need to score to multiple bins if there were multiple
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! neutrons produced with different energies.
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!===============================================================================
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subroutine score_fission_eout(p, t, bins, j)
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@ -499,7 +507,10 @@ contains
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end subroutine score_fission_eout
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!===============================================================================
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! SCORE_TRACKLENGTH_TALLY
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! SCORE_TRACKLENGTH_TALLY calculates fluxes and reaction rates based on the
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! track-length estimate of the flux. This is triggered at every event (surface
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! crossing, lattice crossing, or collision) and thus cannot be done for tallies
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! that require post-collision information.
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!===============================================================================
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subroutine score_tracklength_tally(p, distance)
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@ -585,7 +596,8 @@ contains
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end subroutine score_tracklength_tally
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!===============================================================================
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! GET_SCORING_BINS
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! GET_SCORING_BINS determines a combination of filter bins that should be scored
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! for a tally based on the particle's current attributes.
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!===============================================================================
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subroutine get_scoring_bins(p, index_tally, bins, found_bin)
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