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Ability to read multiple secondary energy distributions on a single reaction.
This commit is contained in:
Paul Romano
parent
ad2983918b
commit
6f73c0aaa0
3 changed files with 106 additions and 70 deletions
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@ -1,7 +1,8 @@
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module cross_section
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use constants
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use cross_section_header, only: Nuclide, Reaction, SAB_Table, XsListing
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use cross_section_header, only: Nuclide, Reaction, SAB_Table, XsListing, &
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DistEnergy
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use datatypes, only: dict_create, dict_add_key, dict_get_key, &
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dict_has_key, dict_delete, dict_keys
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use datatypes_header, only: DictionaryCI, ListKeyValueCI
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@ -841,21 +842,11 @@ contains
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type(Nuclide), pointer :: nuc
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integer :: LED ! location of energy distribution locators
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integer :: LDIS ! location of all energy distributions
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integer :: LOCC ! location of energy distributions for given MT
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integer :: LNW ! location of next energy distribution if multiple
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integer :: LAW ! secondary energy distribution law
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integer :: NR ! number of interpolation regions
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integer :: NE ! number of incoming energies
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integer :: IDAT ! location of first energy distribution for given MT
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integer :: loc ! locator
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integer :: length ! length of data to allocate
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integer :: length_interp_data ! length of interpolation data
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integer :: i ! loop index
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type(Reaction), pointer :: rxn => null()
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integer :: i ! loop index
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type(Reaction), pointer :: rxn => null()
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LED = JXS(10)
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LDIS = JXS(11)
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! Loop over all reactions
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do i = 1, NXS(5)
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@ -864,55 +855,94 @@ contains
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! find location of energy distribution data
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LOCC = XSS(LED + i - 1)
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LNW = XSS(LDIS + LOCC - 1)
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LAW = XSS(LDIS + LOCC)
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IDAT = XSS(LDIS + LOCC + 1)
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NR = XSS(LDIS + LOCC + 2)
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rxn % edist % law = LAW
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rxn % edist % n_interp = NR
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! allocate space for ENDF interpolation parameters
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if (NR > 0) then
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allocate(rxn % edist % nbt(NR))
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allocate(rxn % edist % int(NR))
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end if
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! read ENDF interpolation parameters
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XSS_index = LDIS + LOCC + 3
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if (NR > 0) then
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rxn % edist % nbt = get_real(NR)
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rxn % edist % int = get_real(NR)
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end if
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! allocate energy distribution
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allocate(rxn % edist)
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! allocate space for law validity data
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NE = XSS(LDIS + LOCC + 3 + 2*NR)
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allocate(rxn % edist % energy(NE))
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allocate(rxn % edist % pvalid(NE))
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length_interp_data = 5 + 2*(NR + NE)
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! read law validity data
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XSS_index = LDIS + LOCC + 4 + 2*NR
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rxn % edist % energy = get_real(NE)
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rxn % edist % pvalid = get_real(NE)
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! Set index to beginning of IDAT array
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loc = LDIS + IDAT - 2
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! determine length of energy distribution
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length = length_energy_dist(loc, LAW, LOCC, length_interp_data)
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! allocate secondary energy distribution array
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allocate(rxn % edist % data(length))
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! read secondary energy distribution
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XSS_index = loc + 1
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rxn % edist % data = get_real(length)
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! read data for energy distribution
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call get_energy_dist(rxn % edist, LOCC)
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end do
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end subroutine read_energy_dist
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!===============================================================================
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! GET_ENERGY_DIST reads in data for a single law for an energy distribution and
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! calls itself recursively if there are multiple energy distributions for a
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! single reaction
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!===============================================================================
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recursive subroutine get_energy_dist(edist, loc_law)
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type(DistEnergy), pointer :: edist ! energy distribution
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integer, intent(in) :: loc_law ! locator for data
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integer :: LDIS ! location of all energy distributions
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integer :: LNW ! location of next energy distribution if multiple
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integer :: LAW ! secondary energy distribution law
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integer :: NR ! number of interpolation regions
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integer :: NE ! number of incoming energies
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integer :: IDAT ! location of first energy distribution for given MT
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integer :: loc ! locator
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integer :: length ! length of data to allocate
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integer :: length_interp_data ! length of interpolation data
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LDIS = JXS(11)
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! locator for next law and information on this law
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LNW = XSS(LDIS + loc_law - 1)
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LAW = XSS(LDIS + loc_law)
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IDAT = XSS(LDIS + loc_law + 1)
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NR = XSS(LDIS + loc_law + 2)
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edist % law = LAW
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edist % n_interp = NR
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! allocate space for ENDF interpolation parameters
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if (NR > 0) then
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allocate(edist % nbt(NR))
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allocate(edist % int(NR))
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end if
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! read ENDF interpolation parameters
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XSS_index = LDIS + loc_law + 3
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if (NR > 0) then
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edist % nbt = get_real(NR)
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edist % int = get_real(NR)
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end if
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! allocate space for law validity data
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NE = XSS(LDIS + loc_law + 3 + 2*NR)
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edist % n_energy = NE
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allocate(edist % energy(NE))
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allocate(edist % pvalid(NE))
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length_interp_data = 5 + 2*(NR + NE)
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! read law validity data
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XSS_index = LDIS + loc_law + 4 + 2*NR
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edist % energy = get_real(NE)
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edist % pvalid = get_real(NE)
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! Set index to beginning of IDAT array
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loc = LDIS + IDAT - 2
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! determine length of energy distribution
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length = length_energy_dist(loc, LAW, loc_law, length_interp_data)
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! allocate secondary energy distribution array
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allocate(edist % data(length))
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! read secondary energy distribution
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XSS_index = loc + 1
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edist % data = get_real(length)
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! read next energy distribution if present
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if (LNW > 0) then
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allocate(edist % next)
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call get_energy_dist(edist % next, LNW)
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end if
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end subroutine get_energy_dist
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!===============================================================================
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! LENGTH_ENERGY_DIST determines how many values are contained in an LDAT energy
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! distribution array based on the secondary energy law and location in XSS
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@ -31,6 +31,10 @@ module cross_section_header
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real(8), allocatable :: energy(:) ! energy grid for law validity
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real(8), allocatable :: pvalid(:) ! probability of law validity
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real(8), allocatable :: data(:) ! energy distribution data
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! For reactions that may have multiple energy distributions such as (n.2n),
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! this pointer allows multiple laws to be stored
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type(DistEnergy), pointer :: next => null()
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end type DistEnergy
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!===============================================================================
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@ -39,15 +43,15 @@ module cross_section_header
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!===============================================================================
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type Reaction
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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 :: TY ! Number of neutrons released
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integer :: IE ! Starting energy grid index
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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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logical :: has_energy_dist ! Energy distribution present?
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type(DistAngle) :: adist ! Secondary angular distribution
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type(DistEnergy) :: edist ! Secondary energy distribution
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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 :: TY ! Number of neutrons released
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integer :: IE ! Starting energy grid index
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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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logical :: has_energy_dist ! Energy distribution present?
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type(DistAngle) :: adist ! Secondary angular distribution
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type(DistEnergy), pointer :: edist ! Secondary energy distribution
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end type Reaction
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!===============================================================================
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@ -103,7 +107,7 @@ module cross_section_header
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integer :: n_precursor
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real(8), allocatable :: nu_d_data(:)
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real(8), allocatable :: nu_d_precursor_data(:)
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type(DistEnergy), allocatable :: nu_d_edist(:)
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type(DistEnergy), pointer :: nu_d_edist(:) => null()
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! Unresolved resonance data
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logical :: urr_present
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@ -1025,7 +1025,8 @@ contains
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real(8) :: yield ! delayed neutron precursor yield
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real(8) :: prob ! cumulative probability
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logical :: actual_event ! did fission actually occur? (no survival biasing)
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type(Nuclide), pointer :: nuc
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type(Nuclide), pointer :: nuc
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type(DistEnergy), pointer :: edist => null()
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! Get pointer to nuclide
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nuc => nuclides(index_nuclide)
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@ -1130,11 +1131,12 @@ contains
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! sample from energy distribution for group j
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law = nuc % nu_d_edist(j) % law
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edist => nuc % nu_d_edist(j)
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do
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if (law == 44 .or. law == 61) then
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call sample_energy(nuc%nu_d_edist(j), E, E_out, mu)
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call sample_energy(edist, E, E_out, mu)
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else
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call sample_energy(nuc%nu_d_edist(j), E, E_out)
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call sample_energy(edist, E, E_out)
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end if
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! resample if energy is >= 20 MeV
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if (E_out < 20) exit
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@ -1425,7 +1427,7 @@ contains
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subroutine sample_energy(edist, E_in, E_out, mu_out, A, Q)
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type(DistEnergy), intent(inout) :: edist
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type(DistEnergy), pointer :: edist
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real(8), intent(in) :: E_in
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real(8), intent(out) :: E_out
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real(8), intent(inout), optional :: mu_out
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