From a7fb70d08b022ccaa04f16f1ebb2cd04a1dba890 Mon Sep 17 00:00:00 2001
From: Paul Romano <romano7@gmail.com>
Date: Mon, 19 Sep 2011 08:43:19 -0400
Subject: [PATCH] Removed material_total_xs subroutine in cross_section module.

---
 src/cross_section.f90 | 70 -------------------------------------------
 src/initialize.f90    |  5 +---
 2 files changed, 1 insertion(+), 74 deletions(-)

diff --git a/src/cross_section.f90 b/src/cross_section.f90
index f336234f7a..70733d5a06 100644
--- a/src/cross_section.f90
+++ b/src/cross_section.f90
@@ -1377,74 +1377,4 @@ contains
 
   end subroutine read_xsdata
 
-!===============================================================================
-! MATERIAL_TOTAL_XS calculates the total macroscopic cross section of each
-! material for use in sampling path lengths
-!===============================================================================
-
-  subroutine material_total_xs()
-
-    type(Material),      pointer :: mat => null()
-    type(Nuclide), pointer :: nuc => null()
-    integer :: i, j, k
-    integer :: index
-    integer :: IE
-    real(8) :: density_i
-    real(8) :: val
-    real(8) :: r
-    real(8) :: E_i
-    real(8) :: E_i1
-    real(8) :: sigma_i
-    real(8) :: sigma_i1
-    character(MAX_LINE_LEN) :: msg
-
-    msg = "Creating material total cross-sections..."
-    call message(msg, 4)
-
-    ! loop over all materials
-    do i = 1, n_materials
-
-       ! allocate storage for total xs
-       mat => materials(i)
-       allocate(mat%total_xs(n_grid))
-
-       ! initialize total cross-section
-       mat % total_xs = ZERO
-
-       ! loop over each isotope
-       do j = 1, mat % n_nuclides
-          index = mat % nuclide(j)
-          nuc => nuclides(index)
-
-          ! find atom density of isotope
-          density_i = mat % atom_density(j)
-
-          ! loop over points in union energy grid
-          do k = 1, n_grid
-             ! find nuclide grid index
-             IE      = nuc % grid_index(k)
-
-             ! get nuclide grid energy and cross-section value
-             E_i     = nuc % energy(IE)
-             sigma_i = nuc % total(IE)
-
-             ! interpolate as necessary
-             if (E_i < e_grid(k)) then
-                E_i1     = nuc % energy(IE + 1)
-                sigma_i1 = nuc % total(IE + 1)
-
-                r = (e_grid(k) - E_i)/(E_i1 - E_i)
-                val = (ONE - r)*sigma_i + r*sigma_i1
-             else
-                val = sigma_i
-             end if
-
-             ! add contribution to total cross-section
-             mat%total_xs(k) = mat%total_xs(k) + density_i * val
-          end do
-       end do
-    end do
-
-  end subroutine material_total_xs
-
 end module cross_section
diff --git a/src/initialize.f90 b/src/initialize.f90
index 6ac69f69bc..fc4f55573d 100644
--- a/src/initialize.f90
+++ b/src/initialize.f90
@@ -1,7 +1,7 @@
 module initialize
 
   use constants
-  use cross_section,    only: read_xs, read_xsdata, material_total_xs
+  use cross_section,    only: read_xs, read_xsdata
   use datatypes,        only: dict_create, dict_add_key, dict_get_key,         &
                               dict_has_key, DICT_NULL, dict_keys
   use datatypes_header, only: ListKeyValueII, DictionaryII
@@ -92,9 +92,6 @@ contains
     call unionized_grid()
     call original_indices()
 
-    ! calculate total material cross-sections for sampling path lenghts
-    call material_total_xs()
-
     ! create source particles
     call initialize_source()