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Changed attribute IE in reaction to threshold.
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5 changed files with 15 additions and 15 deletions
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@ -577,7 +577,7 @@ contains
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rxn % MT = 2
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rxn % Q_value = ZERO
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rxn % multiplicity = 1
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rxn % IE = 1
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rxn % threshold = 1
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rxn % scatter_in_cm = .true.
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rxn % has_angle_dist = .false.
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rxn % has_energy_dist = .false.
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@ -608,7 +608,7 @@ contains
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! read starting energy index
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LOCA = int(XSS(LXS + i - 1))
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IE = int(XSS(JXS7 + LOCA - 1))
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rxn % IE = IE
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rxn % threshold = IE
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! read number of energies cross section values
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NE = int(XSS(JXS7 + LOCA))
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@ -42,7 +42,7 @@ module ace_header
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integer :: MT ! ENDF MT value
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real(8) :: Q_value ! Reaction Q value
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integer :: multiplicity ! Number of secondary particles released
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integer :: IE ! Starting energy grid index
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integer :: threshold ! Energy grid index of threshold
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logical :: scatter_in_cm ! scattering system in center-of-mass?
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real(8), allocatable :: sigma(:) ! Cross section values
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logical :: has_angle_dist ! Angle distribution present?
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@ -379,9 +379,9 @@ contains
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f = micro_xs(index_nuclide) % interp_factor
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! Determine inelastic scattering cross section
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if (i_energy >= rxn % IE) then
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inelastic = (ONE - f) * rxn % sigma(i_energy - rxn%IE + 1) + &
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f * rxn % sigma(i_energy - rxn%IE + 2)
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if (i_energy >= rxn % threshold) then
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inelastic = (ONE - f) * rxn % sigma(i_energy - rxn%threshold + 1) + &
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f * rxn % sigma(i_energy - rxn%threshold + 2)
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end if
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end if
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@ -288,7 +288,7 @@ contains
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write(ou,*) ' MT = ' // to_str(rxn % MT)
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write(ou,*) ' Q-value = ' // to_str(rxn % Q_value)
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write(ou,*) ' Multiplicity = ' // to_str(rxn % multiplicity)
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write(ou,*) ' Starting index = ' // to_str(rxn % IE)
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write(ou,*) ' Threshold = ' // to_str(rxn % threshold)
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if (rxn % has_energy_dist) then
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write(ou,*) ' Energy: Law ' // to_str(rxn % edist % law)
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end if
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@ -840,10 +840,10 @@ contains
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write(unit_,'(3X,A11,1X,F8.3,3X,L1,3X,A4,1X,I6,1X,I11,1X,I11)') &
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reaction_name(rxn % MT), rxn % Q_value, rxn % scatter_in_cm, &
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law, rxn % IE, size_angle, size_energy
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law, rxn % threshold, size_angle, size_energy
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! Accumulate data size
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size_xs = size_xs + (nuc % n_grid - rxn%IE + 1) * 8
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size_xs = size_xs + (nuc % n_grid - rxn%threshold + 1) * 8
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size_angle_total = size_angle_total + size_angle
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size_energy_total = size_energy_total + size_energy
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end do
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@ -365,12 +365,12 @@ contains
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rxn => nuc % reactions(nuc % index_fission(i))
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! if energy is below threshold for this reaction, skip it
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if (IE < rxn%IE) cycle
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if (IE < rxn % threshold) cycle
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! add to cumulative probability
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if (nuc % has_partial_fission) then
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prob = prob + ((ONE-f)*rxn%sigma(IE-rxn%IE+1) &
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+ f*(rxn%sigma(IE-rxn%IE+2)))
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prob = prob + ((ONE - f)*rxn%sigma(IE - rxn%threshold + 1) &
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+ f*(rxn%sigma(IE - rxn%threshold + 2)))
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else
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prob = prob + micro_xs(index_nuclide) % fission
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end if
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@ -469,11 +469,11 @@ contains
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if (rxn%MT >= 200 .or. rxn%MT == N_LEVEL) cycle
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! if energy is below threshold for this reaction, skip it
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if (IE < rxn%IE) cycle
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if (IE < rxn % threshold) cycle
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! add to cumulative probability
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prob = prob + ((ONE-f)*rxn%sigma(IE-rxn%IE+1) &
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+ f*(rxn%sigma(IE-rxn%IE+2)))
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prob = prob + ((ONE - f)*rxn%sigma(IE - rxn%threshold + 1) &
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+ f*(rxn%sigma(IE - rxn%threshold + 2)))
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end do
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! Perform collision physics for inelastics scattering
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