Changed SAB_Table derived type to SAlphaBeta.

src/ace.F90

@@ -1,6 +1,6 @@
 module ace
 
-  use ace_header,       only: Nuclide, Reaction, SAB_Table, XsListing, &
+  use ace_header,       only: Nuclide, Reaction, SAlphaBeta, XsListing, &
                               DistEnergy
   use constants
   use datatypes,        only: dict_create, dict_add_key, dict_get_key, &
@@ -43,7 +43,7 @@ contains
     character(12)  :: alias     ! alias of nuclide, e.g. U-235.03c
     type(Material),  pointer :: mat => null()
     type(Nuclide),   pointer :: nuc => null()
-    type(SAB_Table), pointer :: sab => null()
+    type(SAlphaBeta), pointer :: sab => null()
     type(DictionaryCI), pointer :: already_read => null()
 
     ! allocate arrays for ACE table storage and cross section cache
@@ -163,7 +163,7 @@ contains
     character(70) :: comment       ! comment for ACE table
     character(MAX_FILE_LEN) :: filename ! path to ACE cross section library
     type(Nuclide),   pointer :: nuc => null()
-    type(SAB_Table), pointer :: sab => null()
+    type(SAlphaBeta), pointer :: sab => null()
     type(XsListing), pointer :: listing => null()
 
     ! determine path, record length, and location of table
@@ -1128,7 +1128,7 @@ contains
 
   subroutine read_thermal_data(table)
 
-    type(SAB_Table), pointer :: table
+    type(SAlphaBeta), pointer :: table
 
     integer :: i      ! index for incoming energies
     integer :: j      ! index for outgoing energies

src/ace_header.F90

@@ -125,11 +125,11 @@ module ace_header
   end type Nuclide
 
 !===============================================================================
-! SAB_TABLE contains S(a,b) data for thermal neutron scattering, typically off
+! SALPHABETA contains S(a,b) data for thermal neutron scattering, typically off
 ! of light isotopes such as water, graphite, Be, etc
 !===============================================================================
      
-  type SAB_Table
+  type SAlphaBeta
     character(10) :: name ! name of table, e.g. lwtr.10t
     integer       :: zaid ! Z and A identifier, e.g. 6012 for Carbon-12
     real(8)       :: awr  ! weight of nucleus in neutron masses
@@ -156,7 +156,7 @@ module ace_header
     real(8), allocatable :: elastic_e_in(:)
     real(8), allocatable :: elastic_P(:)
     real(8), allocatable :: elastic_mu(:,:)
-  end type SAB_Table
+  end type SAlphaBeta
 
 !===============================================================================
 ! XSLISTING contains data read from a cross_sections.xml file

src/cross_section.F90

@@ -1,6 +1,6 @@
 module cross_section
 
-  use ace_header,      only: Nuclide, SAB_Table, Reaction, UrrData
+  use ace_header,      only: Nuclide, SAlphaBeta, Reaction, UrrData
   use constants
   use error,           only: fatal_error
   use fission,         only: nu_total
@@ -215,7 +215,7 @@ contains
     real(8) :: f         ! interp factor on S(a,b) energy grid
     real(8) :: inelastic ! S(a,b) inelastic cross section
     real(8) :: elastic   ! S(a,b) elastic cross section
-    type(SAB_Table), pointer :: sab => null()
+    type(SAlphaBeta), pointer :: sab => null()
 
     ! Set flag that S(a,b) treatment should be used for scattering
     micro_xs(i_nuclide) % use_sab = .true.

src/global.F90

@@ -1,6 +1,6 @@
 module global
 
-  use ace_header,       only: Nuclide, SAB_Table, xsListing, NuclideMicroXS, &
+  use ace_header,       only: Nuclide, SAlphaBeta, xsListing, NuclideMicroXS, &
                               MaterialMacroXS
   use bank_header,      only: Bank
   use cmfd_header
@@ -66,9 +66,9 @@ module global
   ! CROSS SECTION RELATED VARIABLES
 
   ! Cross section arrays
-  type(Nuclide),   allocatable, target :: nuclides(:)    ! Nuclide cross-sections
-  type(SAB_Table), allocatable, target :: sab_tables(:)  ! S(a,b) tables
-  type(XsListing), allocatable, target :: xs_listings(:) ! cross_sections.xml listings 
+  type(Nuclide),    allocatable, target :: nuclides(:)    ! Nuclide cross-sections
+  type(SAlphaBeta), allocatable, target :: sab_tables(:)  ! S(a,b) tables
+  type(XsListing),  allocatable, target :: xs_listings(:) ! cross_sections.xml listings 
 
   ! Cross section caches
   type(NuclideMicroXS), allocatable :: micro_xs(:)  ! Cache for each nuclide

src/output.F90

@@ -960,8 +960,8 @@ contains
 
   subroutine print_sab_table(sab, unit)
 
-    type(SAB_Table), pointer :: sab
-    integer,        optional :: unit
+    type(SAlphaBeta), pointer :: sab
+    integer,         optional :: unit
 
     integer :: size_sab ! memory used by S(a,b) table
     integer :: unit_    ! unit to write to
@@ -1119,8 +1119,8 @@ contains
 
     integer                  :: i    ! loop index
     character(MAX_FILE_LEN)  :: path ! path of summary file
-    type(Nuclide),   pointer :: nuc => null()
-    type(SAB_Table), pointer :: sab => null()
+    type(Nuclide),    pointer :: nuc => null()
+    type(SAlphaBeta), pointer :: sab => null()
 
     ! Create filename for log file
     path = "cross_sections.out"

src/physics.F90

@@ -594,7 +594,7 @@ contains
     real(8) :: mu_i1jk      ! outgoing cosine k for E_in(i+1) and E_out(j)
     real(8) :: prob         ! probability for sampling Bragg edge
     real(8) :: u, v, w      ! directional cosines
-    type(SAB_Table), pointer :: sab => null()
+    type(SAlphaBeta), pointer :: sab => null()
 
     ! Get pointer to S(a,b) table
     sab => sab_tables(i_sab)