Fixed allocation of fission/source bank. Deallocated several important arrays.

ChangeLog

@@ -1,3 +1,14 @@
+2011-04-22 Paul Romano <romano7@mit.edu>
+
+	* geometry.f90: Deallocated count lists in neighbor_lists.
+	* global.f90: Deallocate arrays that were not previously
+	deallocated (xs_continuous, xs_thermal, e_grid, lattices).
+	* mpi_routines.f90: Added variable p_sample to lessen calculation
+	inside of sampling loop.
+	* physics.f90: Commented warning about low particle energy.
+	* source.f90: Changed source and fission banks to be allocated
+	maxwork instead of n_particles.
+
 2011-04-21 Paul Romano <romano7@mit.edu>
 
 	* main.f90: Moved RN_init_particle at end of cycle to

src/geometry.f90

@@ -994,6 +994,9 @@ contains
        end do
     end do
 
+    deallocate(count_positive)
+    deallocate(count_negative)
+
   end subroutine neighbor_lists
 
 end module geometry

src/global.f90

@@ -285,9 +285,15 @@ contains
     if (allocated(cells)) deallocate(cells)
     if (allocated(surfaces)) deallocate(surfaces)
     if (allocated(materials)) deallocate(materials)
+    if (allocated(lattices)) deallocate(lattices)
 
-    ! Deallocate xsdata list
+    ! Deallocate cross section data
     if (allocated(xsdatas)) deallocate(xsdatas)
+    if (allocated(xs_continuous)) deallocate(xs_continuous)
+    if (allocated(xs_thermal)) deallocate(xs_thermal)
+
+    ! Deallocate energy grid
+    if (allocated(e_grid)) deallocate(e_grid)
 
     ! Deallocate fission and source bank
     if (allocated(fission_bank)) deallocate(fission_bank)

src/mpi_routines.f90

@@ -120,6 +120,7 @@ contains
     integer    :: send_to_right   ! # of bank sites to send/recv to or from right
     integer(8) :: sites_needed    ! # of sites to be sampled
     integer(8) :: sites_remaining ! # of sites left in fission bank
+    real(8)    :: p_sample        ! probability of sampling a site
     real(8)    :: t0, t1, t2, t3, t4
     type(Bank), allocatable :: &
          & temp_sites(:),      & ! local array of extra sites on each node
@@ -174,6 +175,7 @@ contains
     else
        sites_needed = n_particles
     end if
+    p_sample = real(sites_needed,8)/real(total,8)
 
     msg = "Sampling fission sites..."
     call message(msg, 8)
@@ -196,7 +198,7 @@ contains
        end if
 
        ! Randomly sample sites needed
-       if (rang() < real(sites_needed)/real(total)) then
+       if (rang() < p_sample) then
           count = count + 1
           temp_sites(count) = fission_bank(i)
        end if

src/physics.f90

@@ -251,8 +251,8 @@ contains
     ! check for very low energy
     if (p % E < 1.0e-100_8) then
        p % alive = .false.
-       msg = "Killing neutron with extremely low energy"
-       call warning(msg)
+       ! msg = "Killing neutron with extremely low energy"
+       ! call warning(msg)
     end if
 
     ! find energy index, interpolation factor

src/source.f90

@@ -33,14 +33,14 @@ contains
     msg = 'Initializing source particles...'
     call message(msg, 6)
 
-    ! Allocate fission and source banks
-    allocate(source_bank(n_particles))
-    allocate(fission_bank(3*n_particles))
-
     ! Determine maximum amount of particles to simulate on each
     ! processor
     maxwork = ceiling(real(n_particles)/n_procs)
 
+    ! Allocate fission and source banks
+    allocate(source_bank(maxwork))
+    allocate(fission_bank(3*maxwork))
+
     ! Check external source type
     if (external_source%type == SRC_BOX) then
        p_min = external_source%values(1:3)