diff --git a/src/ace.F90 b/src/ace.F90 index c12915c4b1..b3dbd5adda 100644 --- a/src/ace.F90 +++ b/src/ace.F90 @@ -577,7 +577,7 @@ contains rxn % MT = 2 rxn % Q_value = ZERO rxn % multiplicity = 1 - rxn % IE = 1 + rxn % threshold = 1 rxn % scatter_in_cm = .true. rxn % has_angle_dist = .false. rxn % has_energy_dist = .false. @@ -608,7 +608,7 @@ contains ! read starting energy index LOCA = int(XSS(LXS + i - 1)) IE = int(XSS(JXS7 + LOCA - 1)) - rxn % IE = IE + rxn % threshold = IE ! read number of energies cross section values NE = int(XSS(JXS7 + LOCA)) diff --git a/src/ace_header.F90 b/src/ace_header.F90 index ccc438fca0..a1769733b3 100644 --- a/src/ace_header.F90 +++ b/src/ace_header.F90 @@ -42,7 +42,7 @@ module ace_header integer :: MT ! ENDF MT value real(8) :: Q_value ! Reaction Q value integer :: multiplicity ! Number of secondary particles released - integer :: IE ! Starting energy grid index + integer :: threshold ! Energy grid index of threshold logical :: scatter_in_cm ! scattering system in center-of-mass? real(8), allocatable :: sigma(:) ! Cross section values logical :: has_angle_dist ! Angle distribution present? diff --git a/src/cross_section.F90 b/src/cross_section.F90 index ae7e4ce8a6..0fbe2c3843 100644 --- a/src/cross_section.F90 +++ b/src/cross_section.F90 @@ -379,9 +379,9 @@ contains f = micro_xs(index_nuclide) % interp_factor ! Determine inelastic scattering cross section - if (i_energy >= rxn % IE) then - inelastic = (ONE - f) * rxn % sigma(i_energy - rxn%IE + 1) + & - f * rxn % sigma(i_energy - rxn%IE + 2) + if (i_energy >= rxn % threshold) then + inelastic = (ONE - f) * rxn % sigma(i_energy - rxn%threshold + 1) + & + f * rxn % sigma(i_energy - rxn%threshold + 2) end if end if diff --git a/src/output.F90 b/src/output.F90 index 60ef42a258..9372845243 100644 --- a/src/output.F90 +++ b/src/output.F90 @@ -288,7 +288,7 @@ contains write(ou,*) ' MT = ' // to_str(rxn % MT) write(ou,*) ' Q-value = ' // to_str(rxn % Q_value) write(ou,*) ' Multiplicity = ' // to_str(rxn % multiplicity) - write(ou,*) ' Starting index = ' // to_str(rxn % IE) + write(ou,*) ' Threshold = ' // to_str(rxn % threshold) if (rxn % has_energy_dist) then write(ou,*) ' Energy: Law ' // to_str(rxn % edist % law) end if @@ -840,10 +840,10 @@ contains write(unit_,'(3X,A11,1X,F8.3,3X,L1,3X,A4,1X,I6,1X,I11,1X,I11)') & reaction_name(rxn % MT), rxn % Q_value, rxn % scatter_in_cm, & - law, rxn % IE, size_angle, size_energy + law, rxn % threshold, size_angle, size_energy ! Accumulate data size - size_xs = size_xs + (nuc % n_grid - rxn%IE + 1) * 8 + size_xs = size_xs + (nuc % n_grid - rxn%threshold + 1) * 8 size_angle_total = size_angle_total + size_angle size_energy_total = size_energy_total + size_energy end do diff --git a/src/physics.F90 b/src/physics.F90 index 4bf582e866..501078d63b 100644 --- a/src/physics.F90 +++ b/src/physics.F90 @@ -365,12 +365,12 @@ contains rxn => nuc % reactions(nuc % index_fission(i)) ! if energy is below threshold for this reaction, skip it - if (IE < rxn%IE) cycle + if (IE < rxn % threshold) cycle ! add to cumulative probability if (nuc % has_partial_fission) then - prob = prob + ((ONE-f)*rxn%sigma(IE-rxn%IE+1) & - + f*(rxn%sigma(IE-rxn%IE+2))) + prob = prob + ((ONE - f)*rxn%sigma(IE - rxn%threshold + 1) & + + f*(rxn%sigma(IE - rxn%threshold + 2))) else prob = prob + micro_xs(index_nuclide) % fission end if @@ -469,11 +469,11 @@ contains if (rxn%MT >= 200 .or. rxn%MT == N_LEVEL) cycle ! if energy is below threshold for this reaction, skip it - if (IE < rxn%IE) cycle + if (IE < rxn % threshold) cycle ! add to cumulative probability - prob = prob + ((ONE-f)*rxn%sigma(IE-rxn%IE+1) & - + f*(rxn%sigma(IE-rxn%IE+2))) + prob = prob + ((ONE - f)*rxn%sigma(IE - rxn%threshold + 1) & + + f*(rxn%sigma(IE - rxn%threshold + 2))) end do ! Perform collision physics for inelastics scattering