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https://github.com/openmc-dev/openmc.git
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Reset global variables on openmc_finalize
This commit is contained in:
Paul Romano
parent
7bc61c1f41
commit
09d1dd7f3c
5 changed files with 107 additions and 60 deletions
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@ -320,7 +320,6 @@ set(LIBOPENMC_FORTRAN_SRC
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src/endf_header.F90
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src/energy_distribution.F90
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src/error.F90
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src/finalize.F90
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src/geometry.F90
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src/geometry_header.F90
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src/global.F90
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104
src/api.F90
104
src/api.F90
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@ -2,19 +2,20 @@ module openmc_api
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use, intrinsic :: ISO_C_BINDING
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use hdf5, only: HID_T
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use hdf5, only: HID_T, h5tclose_f, h5close_f
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use constants, only: K_BOLTZMANN
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use eigenvalue, only: k_sum, openmc_get_keff
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use finalize, only: openmc_finalize
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use geometry, only: find_cell
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use geometry_header, only: root_universe
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use global
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use hdf5_interface
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use message_passing, only: master
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use message_passing
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use initialize, only: openmc_init
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use input_xml, only: assign_0K_elastic_scattering, check_data_version
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use particle_header, only: Particle
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use plot, only: openmc_plot_geometry
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use random_lcg, only: seed
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use simulation, only: openmc_run
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use volume_calc, only: openmc_calculate_volumes
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@ -70,6 +71,89 @@ contains
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end if
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end function openmc_cell_set_temperature
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!===============================================================================
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! OPENMC_FINALIZE frees up memory by deallocating arrays and resetting global
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! variables
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!===============================================================================
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subroutine openmc_finalize() bind(C)
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integer :: hdf5_err
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! Clear results
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call openmc_reset()
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! Reset global variables
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assume_separate = .false.
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check_overlaps = .false.
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confidence_intervals = .false.
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create_fission_neutrons = .true.
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current_batch = 0
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current_gen = 0
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energy_cutoff = ZERO
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energy_max_neutron = INFINITY
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energy_min_neutron = ZERO
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entropy_on = .false.
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gen_per_batch = 1
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i_user_tallies = -1
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i_cmfd_tallies = -1
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keff = ONE
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legendre_to_tabular = .true.
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legendre_to_tabular_points = 33
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n_batch_interval = 1
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n_particles = 0
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n_source_points = 0
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n_state_points = 0
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output_summary = .true.
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output_tallies = .true.
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particle_restart_run = .false.
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pred_batches = .false.
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reduce_tallies = .true.
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res_scat_on = .false.
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res_scat_method = RES_SCAT_ARES
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res_scat_energy_min = 0.01_8
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res_scat_energy_max = 1000.0_8
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restart_run = .false.
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root_universe = -1
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run_CE = .true.
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run_mode = NONE
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satisfy_triggers = .false.
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seed = 1_8
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source_latest = .false.
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source_separate = .false.
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source_write = .true.
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survival_biasing = .false.
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temperature_default = 293.6_8
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temperature_method = TEMPERATURE_NEAREST
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temperature_multipole = .false.
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temperature_range = [ZERO, ZERO]
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temperature_tolerance = 10.0_8
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total_gen = 0
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trigger_on = .false.
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ufs = .false.
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urr_ptables_on = .true.
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verbosity = 7
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weight_cutoff = 0.25_8
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weight_survive = ONE
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write_all_tracks = .false.
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write_initial_source = .false.
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! Deallocate arrays
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call free_memory()
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! Release compound datatypes
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call h5tclose_f(hdf5_bank_t, hdf5_err)
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! Close FORTRAN interface.
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call h5close_f(hdf5_err)
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#ifdef MPI
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! Free all MPI types
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call MPI_TYPE_FREE(MPI_BANK, mpi_err)
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#endif
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end subroutine openmc_finalize
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!===============================================================================
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! OPENMC_FIND determines the ID or a cell or material at a given point in space
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!===============================================================================
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@ -291,12 +375,14 @@ contains
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subroutine openmc_reset() bind(C)
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integer :: i
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do i = 1, size(tallies)
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tallies(i) % n_realizations = 0
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if (allocated(tallies(i) % results)) then
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tallies(i) % results(:, :, :) = ZERO
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end if
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end do
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if (allocated(tallies)) then
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do i = 1, size(tallies)
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tallies(i) % n_realizations = 0
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if (allocated(tallies(i) % results)) then
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tallies(i) % results(:, :, :) = ZERO
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end if
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end do
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end if
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! Reset global tallies
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n_realizations = 0
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@ -1,40 +0,0 @@
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module finalize
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use, intrinsic :: ISO_C_BINDING
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use hdf5, only: h5tclose_f, h5close_f
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use global
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use hdf5_interface, only: hdf5_bank_t
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use message_passing
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implicit none
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contains
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!===============================================================================
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! FINALIZE_RUN does all post-simulation tasks such as calculating tally
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! statistics and writing out tallies
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!===============================================================================
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subroutine openmc_finalize() bind(C)
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integer :: hdf5_err
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! Deallocate arrays
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call free_memory()
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! Release compound datatypes
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call h5tclose_f(hdf5_bank_t, hdf5_err)
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! Close FORTRAN interface.
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call h5close_f(hdf5_err)
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#ifdef MPI
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! Free all MPI types
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call MPI_TYPE_FREE(MPI_BANK, mpi_err)
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#endif
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end subroutine openmc_finalize
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end module finalize
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@ -140,7 +140,7 @@ module global
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integer :: max_order
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! Whether or not to convert Legendres to tabulars
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logical :: legendre_to_tabular = .True.
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logical :: legendre_to_tabular = .true.
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! Number of points to use in the Legendre to tabular conversion
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integer :: legendre_to_tabular_points = 33
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@ -466,6 +466,7 @@ contains
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if (allocated(surfaces)) deallocate(surfaces)
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if (allocated(materials)) deallocate(materials)
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if (allocated(plots)) deallocate(plots)
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if (allocated(volume_calcs)) deallocate(volume_calcs)
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! Deallocate geometry debugging information
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if (allocated(overlap_check_cnt)) deallocate(overlap_check_cnt)
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@ -478,6 +479,7 @@ contains
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end do
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deallocate(nuclides)
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end if
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if (allocated(libraries)) deallocate(libraries)
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if (allocated(res_scat_nuclides)) deallocate(res_scat_nuclides)
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@ -486,7 +488,6 @@ contains
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if (allocated(macro_xs)) deallocate(macro_xs)
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if (allocated(sab_tables)) deallocate(sab_tables)
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if (allocated(micro_xs)) deallocate(micro_xs)
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! Deallocate external source
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if (allocated(external_source)) deallocate(external_source)
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@ -501,21 +502,24 @@ contains
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if (allocated(meshes)) deallocate(meshes)
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if (allocated(filters)) deallocate(filters)
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if (allocated(tallies)) deallocate(tallies)
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if (allocated(filter_matches)) deallocate(filter_matches)
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! Deallocate fission and source bank and entropy
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!$omp parallel
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if (allocated(fission_bank)) deallocate(fission_bank)
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if (allocated(filter_matches)) deallocate(filter_matches)
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if (allocated(tally_derivs)) deallocate(tally_derivs)
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!$omp end parallel
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#ifdef _OPENMP
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if (allocated(master_fission_bank)) deallocate(master_fission_bank)
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#endif
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if (allocated(source_bank)) deallocate(source_bank)
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if (allocated(entropy_p)) deallocate(entropy_p)
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! Deallocate array of work indices
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if (allocated(work_index)) deallocate(work_index)
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if (allocated(energy_bins)) deallocate(energy_bins)
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if (allocated(energy_bin_avg)) deallocate(energy_bin_avg)
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! Deallocate CMFD
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call deallocate_cmfd(cmfd)
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@ -541,6 +545,7 @@ contains
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call plot_dict % clear()
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call nuclide_dict % clear()
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call sab_dict % clear()
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call library_dict % clear()
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! Clear statepoint and sourcepoint batch set
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call statepoint_batch % clear()
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@ -1,14 +1,11 @@
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program main
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use constants
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use finalize, only: openmc_finalize
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use global
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use initialize, only: openmc_init
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use message_passing
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use particle_restart, only: run_particle_restart
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use plot, only: openmc_plot_geometry
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use simulation, only: openmc_run
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use volume_calc, only: openmc_calculate_volumes
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use openmc_api, only: openmc_init, openmc_finalize, openmc_run, &
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openmc_plot_geometry, openmc_calculate_volumes
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use particle_restart, only: run_particle_restart
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implicit none
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