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https://github.com/openmc-dev/openmc.git
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Add diff tally for keff---density or nuc. density
This commit is contained in:
Sterling Harper
parent
39e246ed38
commit
199d4af9c5
22 changed files with 732 additions and 4 deletions
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@ -259,7 +259,7 @@ module constants
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EVENT_ABSORB = 2
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! Tally score type
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integer, parameter :: N_SCORE_TYPES = 22
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integer, parameter :: N_SCORE_TYPES = 23
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integer, parameter :: &
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SCORE_FLUX = -1, & ! flux
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SCORE_TOTAL = -2, & ! total reaction rate
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@ -282,7 +282,8 @@ module constants
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SCORE_NU_SCATTER_YN = -19, & ! angular flux-weighted nu-scattering moment (0:N)
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SCORE_EVENTS = -20, & ! number of events
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SCORE_DELAYED_NU_FISSION = -21, & ! delayed neutron production rate
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SCORE_INVERSE_VELOCITY = -22 ! flux-weighted inverse velocity
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SCORE_INVERSE_VELOCITY = -22, & ! flux-weighted inverse velocity
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SCORE_KEFF = -23 ! multiplication factor
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! Maximum scattering order supported
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integer, parameter :: MAX_ANG_ORDER = 10
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@ -348,6 +349,11 @@ module constants
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K_TRACKLENGTH = 3, &
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LEAKAGE = 4
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! Differential tally dependent variables
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integer, parameter :: &
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DIFF_DENSITY = 1, &
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DIFF_NUCLIDE_DENSITY = 2
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! ============================================================================
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! RANDOM NUMBER STREAM CONSTANTS
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@ -831,6 +831,7 @@ contains
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! Change density in g/cm^3 to atom/b-cm. Since all values are now in atom
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! percent, the sum needs to be re-evaluated as 1/sum(x*awr)
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if (.not. density_in_atom) then
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mat % density_gpcc = -mat % density
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sum_percent = ZERO
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do j = 1, mat%n_nuclides
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index_list = xs_listing_dict%get_key(mat%names(j))
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@ -2197,6 +2197,7 @@ contains
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type(Node), pointer :: node_tal => null()
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type(Node), pointer :: node_filt => null()
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type(Node), pointer :: node_trigger=>null()
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type(Node), pointer :: node_deriv => null()
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type(NodeList), pointer :: node_mesh_list => null()
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type(NodeList), pointer :: node_tal_list => null()
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type(NodeList), pointer :: node_filt_list => null()
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@ -2407,7 +2408,7 @@ contains
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t % estimator = ESTIMATOR_TRACKLENGTH
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! Copy material id
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! Copy tally id
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if (check_for_node(node_tal, "id")) then
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call get_node_value(node_tal, "id", t % id)
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else
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@ -2843,6 +2844,52 @@ contains
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end do
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end if
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! =======================================================================
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! READ DATA FOR DERIVATIVES
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if (check_for_node(node_tal, "derivative")) then
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call get_node_ptr(node_tal, "derivative", node_deriv)
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allocate(t % deriv)
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temp_str = ""
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call get_node_value(node_deriv, "variable", temp_str)
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temp_str = to_lower(temp_str)
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select case(temp_str)
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case("density")
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t % deriv % dep_var = DIFF_DENSITY
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call get_node_value(node_deriv, "material", t % deriv % diff_material)
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case("nuclide_density")
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t % deriv % dep_var = DIFF_NUCLIDE_DENSITY
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call get_node_value(node_deriv, "material", t % deriv % diff_material)
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call get_node_value(node_deriv, "nuclide", word)
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word = trim(to_lower(word))
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pair_list => nuclide_dict % keys()
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do while (associated(pair_list))
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if (starts_with(pair_list % key, word)) then
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word = pair_list % key(1:150)
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exit
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end if
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! Advance to next
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pair_list => pair_list % next
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end do
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! Check if no nuclide was found
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if (.not. associated(pair_list)) then
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call fatal_error("Could not find the nuclide " &
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&// trim(word) // " specified in tally " &
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&// trim(to_str(t % id)) // " in any material.")
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end if
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deallocate(pair_list)
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t % deriv % diff_nuclide = nuclide_dict % get_key(word)
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end select
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end if
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! =======================================================================
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! READ DATA FOR SCORES
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@ -2991,6 +3038,11 @@ contains
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call fatal_error("Cannot tally flux with an outgoing energy &
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&filter.")
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end if
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if (allocated(t % deriv)) then
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t % estimator = ESTIMATOR_COLLISION
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end if
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case ('flux-yn')
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! Prohibit user from tallying flux for an individual nuclide
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if (.not. (t % n_nuclide_bins == 1 .and. &
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@ -3188,6 +3240,12 @@ contains
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case ('events')
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t % score_bins(j) = SCORE_EVENTS
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case ('keff')
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t % score_bins(j) = SCORE_KEFF
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if (allocated(t % deriv)) then
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t % estimator = ESTIMATOR_COLLISION
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end if
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case ('elastic', '(n,elastic)')
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t % score_bins(j) = ELASTIC
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case ('(n,2nd)')
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@ -13,6 +13,7 @@ module material_header
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integer, allocatable :: nuclide(:) ! index in nuclides array
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real(8) :: density ! total atom density in atom/b-cm
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real(8), allocatable :: atom_density(:) ! nuclide atom density in atom/b-cm
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real(8) :: density_gpcc ! total density in g/cm^3
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! Energy grid information
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integer :: n_grid ! # of union material grid points
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@ -986,6 +986,7 @@ contains
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score_names(abs(SCORE_NU_SCATTER_YN)) = "Scattering Prod. Rate Moment"
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score_names(abs(SCORE_DELAYED_NU_FISSION)) = "Delayed-Nu-Fission Rate"
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score_names(abs(SCORE_INVERSE_VELOCITY)) = "Flux-Weighted Inverse Velocity"
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score_names(abs(SCORE_KEFF)) = "k_eff, multiplaction factor"
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! Create filename for tally output
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filename = trim(path_output) // "tallies.out"
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110
src/tally.F90
110
src/tally.F90
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@ -654,6 +654,13 @@ contains
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end if
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end if
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case (SCORE_KEFF)
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if (t % estimator == ESTIMATOR_COLLISION) then
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score = p % last_wgt * material_xs % nu_fission / material_xs % total
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else if (t % estimator == ESTIMATOR_TRACKLENGTH) then
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score = flux * material_xs % nu_fission
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end if
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case default
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if (t % estimator == ESTIMATOR_ANALOG) then
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! Any other score is assumed to be a MT number. Thus, we just need
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@ -732,6 +739,35 @@ contains
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end select
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!#########################################################################
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! Add derivative information on score for differential tallies.
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if (allocated(t % deriv) .and. t % estimator == ESTIMATOR_COLLISION) then
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select case (score_bin)
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case (SCORE_KEFF)
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select case (t % deriv % dep_var)
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case (DIFF_DENSITY)
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score = score * t % deriv % accumulator
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case (DIFF_NUCLIDE_DENSITY)
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mat => materials(p % material)
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if (mat % id == t % deriv % diff_material .and. &
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micro_xs(t % deriv % diff_nuclide) % nu_fission /= ZERO) then
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do l = 1, mat % n_nuclides
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if (mat % nuclide(l) == t % deriv % diff_nuclide) exit
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end do
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score = score * (t % deriv % accumulator + ONE &
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/ mat % atom_density(l))
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else
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score = score * t % deriv % accumulator
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end if
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end select
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end select
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end if
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!#########################################################################
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! Expand score if necessary and add to tally results.
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@ -2210,6 +2246,80 @@ contains
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end subroutine score_surface_current
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!===============================================================================
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! SCORE_DIFF_ACCUMULATORS
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!===============================================================================
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subroutine score_diff_accumulators(p, distance, collision)
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type(particle), intent(in) :: p
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real(8), intent(in) :: distance
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logical, intent(in) :: collision
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integer :: i, j
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type(TallyObject), pointer :: t
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type(Material), pointer :: mat
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do i = 1, n_user_tallies
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t => user_tallies(i)
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if (allocated(t % deriv)) then
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select case (t % deriv % dep_var)
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case (DIFF_DENSITY)
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if (p % material == MATERIAL_VOID) cycle
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mat => materials(p % material)
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if (mat % id == t % deriv % diff_material) then
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if (collision) then
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t % deriv % accumulator = t % deriv % accumulator &
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+ ONE / mat % density_gpcc &
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- distance * material_xs % total / mat % density_gpcc
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else
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t % deriv % accumulator = t % deriv % accumulator &
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- distance * material_xs % total / mat % density_gpcc
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end if
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end if
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case (DIFF_NUCLIDE_DENSITY)
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if (p % material == MATERIAL_VOID) cycle
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mat => materials(p % material)
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if (mat % id == t % deriv % diff_material) then
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do j = 1, mat % n_nuclides
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if (mat % nuclide(j) == t % deriv % diff_nuclide) exit
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end do
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if (mat % nuclide(j) /= t % deriv % diff_nuclide) then
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call fatal_error("Couldn't find the right nuclide.")
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end if
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t % deriv % accumulator = t % deriv % accumulator &
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- distance * micro_xs(t % deriv % diff_nuclide) % total
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if (collision) then
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if (p % event == EVENT_SCATTER) then
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t % deriv % accumulator = t % deriv % accumulator &
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+ micro_xs(t % deriv % diff_nuclide) % elastic &
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/ material_xs % elastic
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else if (p % event == EVENT_ABSORB) then
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t % deriv % accumulator = t % deriv % accumulator &
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+ micro_xs(t % deriv % diff_nuclide) % absorption &
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/ material_xs % absorption
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end if
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end if
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end if
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end select
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end if
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end do
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end subroutine
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subroutine clear_diff_accumulators()
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integer :: i
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type(TallyObject), pointer :: t
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do i = 1, n_user_tallies
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t => user_tallies(i)
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if (allocated(t % deriv)) then
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t % deriv % accumulator = ZERO
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end if
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end do
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end subroutine
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!===============================================================================
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! GET_NEXT_BIN determines the next scoring bin for a particular filter variable
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!===============================================================================
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@ -64,6 +64,18 @@ module tally_header
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procedure :: clear => tallyfilter_clear ! Deallocates TallyFilter
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end type TallyFilter
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!===============================================================================
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! TALLYDERIVATIVE
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!===============================================================================
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type TallyDerivative
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real(8) :: accumulator
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integer :: dep_var
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integer :: diff_material
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integer :: diff_nuclide
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end type TallyDerivative
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!===============================================================================
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! TALLYOBJECT describes a user-specified tally. The region of phase space to
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! tally in is given by the TallyFilters and the results are stored in a
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@ -130,6 +142,9 @@ module tally_header
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integer :: n_triggers = 0 ! # of triggers
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type(TriggerObject), allocatable :: triggers(:) ! Array of triggers
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! Derivative for differentially tallies
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type(TallyDerivative), allocatable :: deriv
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! Type-Bound procedures
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contains
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procedure :: clear => tallyobject_clear ! Deallocates TallyObject
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@ -204,6 +219,9 @@ module tally_header
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this % n_triggers = 0
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if (allocated(this % deriv)) &
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deallocate (this % deriv)
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end subroutine tallyobject_clear
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end module tally_header
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@ -13,7 +13,8 @@ module tracking
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use random_lcg, only: prn
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use string, only: to_str
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use tally, only: score_analog_tally, score_tracklength_tally, &
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score_collision_tally, score_surface_current
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score_collision_tally, score_surface_current, &
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score_diff_accumulators, clear_diff_accumulators
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use track_output, only: initialize_particle_track, write_particle_track, &
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add_particle_track, finalize_particle_track
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@ -60,6 +61,9 @@ contains
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call initialize_particle_track()
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endif
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! Every particle starts with no accumulated flux derivative.
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call clear_diff_accumulators()
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EVENT_LOOP: do
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! If the cell hasn't been determined based on the particle's location,
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! initiate a search for the current cell. This generally happens at the
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@ -114,6 +118,9 @@ contains
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distance * material_xs % nu_fission
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end if
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! Score flux derivative accumulators for differential tallies.
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call score_diff_accumulators(p, distance, d_boundary > d_collision)
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if (d_collision > d_boundary) then
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! ====================================================================
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! PARTICLE CROSSES SURFACE
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150
tests/test_diff_density/build_xml.py
Normal file
150
tests/test_diff_density/build_xml.py
Normal file
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@ -0,0 +1,150 @@
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import openmc
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def make_mats(mod_density=0.7420582):
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water = openmc.Material(name='water')
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water.set_density('g/cm3', mod_density)
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water.add_nuclide(openmc.Nuclide('H-1'), 2.0)
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water.add_nuclide(openmc.Nuclide('O-16'), 1.0)
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fuel = openmc.Material(name='fuel 2.4%')
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fuel.set_density('g/cm3', 10.29769)
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fuel.add_nuclide(openmc.Nuclide('U-234'), 5.7987e-06)
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fuel.add_nuclide(openmc.Nuclide('U-235'), 7.2175e-04)
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fuel.add_nuclide(openmc.Nuclide('U-238'), 2.2253e-02)
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fuel.add_nuclide(openmc.Nuclide('O-16'), 4.5750e-02)
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fuel.add_nuclide(openmc.Nuclide('O-17'), 9.4222e-05)
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zirc4 = openmc.Material(name='zircaloy 4')
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zirc4.set_density('g/cm3', 6.55)
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zirc4.add_nuclide(openmc.Nuclide('O-16'), 3.0743e-04)
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zirc4.add_nuclide(openmc.Nuclide('O-17'), 1.1711e-07)
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# O-18 omitted
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zirc4.add_nuclide(openmc.Nuclide('Cr-50'), 3.2962e-06)
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zirc4.add_nuclide(openmc.Nuclide('Cr-52'), 6.3564e-05)
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zirc4.add_nuclide(openmc.Nuclide('Cr-53'), 7.2076e-06)
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zirc4.add_nuclide(openmc.Nuclide('Cr-54'), 1.7941e-06)
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zirc4.add_nuclide(openmc.Nuclide('Fe-54'), 8.6699e-06)
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zirc4.add_nuclide(openmc.Nuclide('Fe-56'), 1.3610e-04)
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zirc4.add_nuclide(openmc.Nuclide('Fe-57'), 3.1431e-06)
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zirc4.add_nuclide(openmc.Nuclide('Fe-58'), 4.1829e-07)
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zirc4.add_nuclide(openmc.Nuclide('Zr-90'), 2.1827e-02)
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zirc4.add_nuclide(openmc.Nuclide('Zr-91'), 4.7600e-03)
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zirc4.add_nuclide(openmc.Nuclide('Zr-92'), 7.2758e-03)
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zirc4.add_nuclide(openmc.Nuclide('Zr-94'), 7.3734e-03)
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zirc4.add_nuclide(openmc.Nuclide('Zr-96'), 1.1879e-03)
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zirc4.add_nuclide(openmc.Nuclide('Sn-112'), 4.6735e-06)
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zirc4.add_nuclide(openmc.Nuclide('Sn-114'), 3.1799e-06)
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zirc4.add_nuclide(openmc.Nuclide('Sn-115'), 1.6381e-06)
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zirc4.add_nuclide(openmc.Nuclide('Sn-116'), 7.0055e-05)
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zirc4.add_nuclide(openmc.Nuclide('Sn-117'), 3.7003e-05)
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zirc4.add_nuclide(openmc.Nuclide('Sn-118'), 1.1669e-04)
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zirc4.add_nuclide(openmc.Nuclide('Sn-119'), 4.1387e-05)
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zirc4.add_nuclide(openmc.Nuclide('Sn-120'), 1.5697e-04)
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zirc4.add_nuclide(openmc.Nuclide('Sn-122'), 2.2308e-05)
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zirc4.add_nuclide(openmc.Nuclide('Sn-124'), 2.7897e-05)
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materials_file = openmc.MaterialsFile()
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materials_file.default_xs = '71c'
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materials_file.add_materials([water, fuel, zirc4])
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return (materials_file,
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{'mod':water,
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'fuel':fuel,
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'clad':zirc4})
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def make_geom(mats):
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# Instantiate surfaces.
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rfo = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.39218, name='fuel outer')
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rci = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.40005, name='clad inner')
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rco = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.45720, name='clad outer')
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|
||||
x0 = openmc.XPlane(x0=-0.62992)
|
||||
x1 = openmc.XPlane(x0=0.62992)
|
||||
y0 = openmc.YPlane(y0=-0.62992)
|
||||
y1 = openmc.YPlane(y0=0.62992)
|
||||
z0 = openmc.ZPlane(z0=-1.0)
|
||||
z1 = openmc.ZPlane(z0=1.0)
|
||||
x0.boundary_type = 'reflective'
|
||||
x1.boundary_type = 'reflective'
|
||||
y0.boundary_type = 'reflective'
|
||||
y1.boundary_type = 'reflective'
|
||||
z0.boundary_type = 'reflective'
|
||||
z1.boundary_type = 'reflective'
|
||||
|
||||
# Instantiate cells.
|
||||
fuel_c = openmc.Cell(name='fuel')
|
||||
fuel_c.add_surface(rfo, halfspace=-1)
|
||||
fuel_c.add_surface(z0, halfspace=+1)
|
||||
fuel_c.add_surface(z1, halfspace=-1)
|
||||
|
||||
gap = openmc.Cell(name='gap')
|
||||
gap.add_surface(rci, halfspace=-1)
|
||||
gap.add_surface(rfo, halfspace=+1)
|
||||
gap.add_surface(z0, halfspace=+1)
|
||||
gap.add_surface(z1, halfspace=-1)
|
||||
|
||||
clad_c = openmc.Cell(name='clad')
|
||||
clad_c.add_surface(rco, halfspace=-1)
|
||||
clad_c.add_surface(rci, halfspace=+1)
|
||||
clad_c.add_surface(z0, halfspace=+1)
|
||||
clad_c.add_surface(z1, halfspace=-1)
|
||||
|
||||
mod_c = openmc.Cell(name='moderator')
|
||||
mod_c.add_surface(rco, halfspace=+1)
|
||||
mod_c.add_surface(x0, halfspace=+1)
|
||||
mod_c.add_surface(x1, halfspace=-1)
|
||||
mod_c.add_surface(y0, halfspace=+1)
|
||||
mod_c.add_surface(y1, halfspace=-1)
|
||||
mod_c.add_surface(z0, halfspace=+1)
|
||||
mod_c.add_surface(z1, halfspace=-1)
|
||||
|
||||
# Add materials to cells.
|
||||
fuel_c.fill = mats['fuel']
|
||||
gap.fill = 'void'
|
||||
clad_c.fill = mats['clad']
|
||||
mod_c.fill = mats['mod']
|
||||
|
||||
# Instantiate universes.
|
||||
u0 = openmc.Universe(universe_id=0)
|
||||
u0.add_cells([fuel_c, gap, clad_c, mod_c])
|
||||
|
||||
# Write the XML file.
|
||||
geometry = openmc.Geometry()
|
||||
geometry.root_universe = u0
|
||||
geometry_file = openmc.GeometryFile()
|
||||
geometry_file.geometry = geometry
|
||||
|
||||
return geometry_file
|
||||
|
||||
|
||||
def make_settings(**kwargs):
|
||||
if 'batches' in kwargs:
|
||||
batches = kwargs['batches']
|
||||
|
||||
settings_file = openmc.SettingsFile()
|
||||
settings_file.batches = kwargs.setdefault('batches', 100)
|
||||
settings_file.inactive = kwargs.setdefault('inactive', 10)
|
||||
settings_file.particles = kwargs.setdefault('particles', 1000)
|
||||
settings_file.set_source_space('box', (-0.6, -0.6, -0.9,
|
||||
0.6, 0.6, 0.9))
|
||||
settings_file.entropy_lower_left = (-0.7, -0.7, -1.1)
|
||||
settings_file.entropy_upper_right = (0.7, 0.7, 1.1)
|
||||
settings_file.entropy_dimension = (10, 10, 10)
|
||||
return settings_file
|
||||
|
||||
|
||||
def make_inputs(mod_density=0.7420582, **kwargs):
|
||||
(mat_file, mats) = make_mats(mod_density)
|
||||
mat_file.export_to_xml()
|
||||
|
||||
geo_file = make_geom(mats)
|
||||
geo_file.export_to_xml()
|
||||
|
||||
sets_file = make_settings(**kwargs)
|
||||
sets_file.export_to_xml()
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
make_inputs(inactive=5, batches=10, particles=100)
|
||||
16
tests/test_diff_density/geometry.xml
Normal file
16
tests/test_diff_density/geometry.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10001" name="fuel" region="(-10000 10007 -10008)" universe="0" />
|
||||
<cell id="10001" material="void" name="gap" region="(-10001 10000 10007 -10008)" universe="0" />
|
||||
<cell id="10002" material="10002" name="clad" region="(-10002 10001 10007 -10008)" universe="0" />
|
||||
<cell id="10003" material="10000" name="moderator" region="(10002 10003 -10004 10005 -10006 10007 -10008)" universe="0" />
|
||||
<surface boundary="transmission" coeffs="0.0 0.0 0.39218" id="10000" name="fuel outer" type="z-cylinder" />
|
||||
<surface boundary="transmission" coeffs="0.0 0.0 0.40005" id="10001" name="clad inner" type="z-cylinder" />
|
||||
<surface boundary="transmission" coeffs="0.0 0.0 0.4572" id="10002" name="clad outer" type="z-cylinder" />
|
||||
<surface boundary="reflective" coeffs="-0.62992" id="10003" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.62992" id="10004" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="-0.62992" id="10005" type="y-plane" />
|
||||
<surface boundary="reflective" coeffs="0.62992" id="10006" type="y-plane" />
|
||||
<surface boundary="reflective" coeffs="-1.0" id="10007" type="z-plane" />
|
||||
<surface boundary="reflective" coeffs="1.0" id="10008" type="z-plane" />
|
||||
</geometry>
|
||||
45
tests/test_diff_density/materials.xml
Normal file
45
tests/test_diff_density/materials.xml
Normal file
|
|
@ -0,0 +1,45 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<default_xs>71c</default_xs>
|
||||
<material id="10000" name="water">
|
||||
<density units="g/cm3" value="0.7420582" />
|
||||
<nuclide ao="2.0" name="H-1" />
|
||||
<nuclide ao="1.0" name="O-16" />
|
||||
</material>
|
||||
<material id="10001" name="fuel 2.4%">
|
||||
<density units="g/cm3" value="10.29769" />
|
||||
<nuclide ao="5.7987e-06" name="U-234" />
|
||||
<nuclide ao="0.00072175" name="U-235" />
|
||||
<nuclide ao="0.022253" name="U-238" />
|
||||
<nuclide ao="0.04575" name="O-16" />
|
||||
<nuclide ao="9.4222e-05" name="O-17" />
|
||||
</material>
|
||||
<material id="10002" name="zircaloy 4">
|
||||
<density units="g/cm3" value="6.55" />
|
||||
<nuclide ao="0.00030743" name="O-16" />
|
||||
<nuclide ao="1.1711e-07" name="O-17" />
|
||||
<nuclide ao="3.2962e-06" name="Cr-50" />
|
||||
<nuclide ao="6.3564e-05" name="Cr-52" />
|
||||
<nuclide ao="7.2076e-06" name="Cr-53" />
|
||||
<nuclide ao="1.7941e-06" name="Cr-54" />
|
||||
<nuclide ao="8.6699e-06" name="Fe-54" />
|
||||
<nuclide ao="0.0001361" name="Fe-56" />
|
||||
<nuclide ao="3.1431e-06" name="Fe-57" />
|
||||
<nuclide ao="4.1829e-07" name="Fe-58" />
|
||||
<nuclide ao="0.021827" name="Zr-90" />
|
||||
<nuclide ao="0.00476" name="Zr-91" />
|
||||
<nuclide ao="0.0072758" name="Zr-92" />
|
||||
<nuclide ao="0.0073734" name="Zr-94" />
|
||||
<nuclide ao="0.0011879" name="Zr-96" />
|
||||
<nuclide ao="4.6735e-06" name="Sn-112" />
|
||||
<nuclide ao="3.1799e-06" name="Sn-114" />
|
||||
<nuclide ao="1.6381e-06" name="Sn-115" />
|
||||
<nuclide ao="7.0055e-05" name="Sn-116" />
|
||||
<nuclide ao="3.7003e-05" name="Sn-117" />
|
||||
<nuclide ao="0.00011669" name="Sn-118" />
|
||||
<nuclide ao="4.1387e-05" name="Sn-119" />
|
||||
<nuclide ao="0.00015697" name="Sn-120" />
|
||||
<nuclide ao="2.2308e-05" name="Sn-122" />
|
||||
<nuclide ao="2.7897e-05" name="Sn-124" />
|
||||
</material>
|
||||
</materials>
|
||||
5
tests/test_diff_density/results_true.dat
Normal file
5
tests/test_diff_density/results_true.dat
Normal file
|
|
@ -0,0 +1,5 @@
|
|||
k-combined:
|
||||
1.502605E+00 2.273838E-02
|
||||
tally 1:
|
||||
5.280104E+00
|
||||
1.379258E+01
|
||||
18
tests/test_diff_density/settings.xml
Normal file
18
tests/test_diff_density/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<settings>
|
||||
<eigenvalue>
|
||||
<particles>100</particles>
|
||||
<batches>10</batches>
|
||||
<inactive>5</inactive>
|
||||
</eigenvalue>
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-0.6 -0.6 -0.9 0.6 0.6 0.9</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<entropy>
|
||||
<dimension>10 10 10</dimension>
|
||||
<lower_left>-0.7 -0.7 -1.1</lower_left>
|
||||
<upper_right>0.7 0.7 1.1</upper_right>
|
||||
</entropy>
|
||||
</settings>
|
||||
7
tests/test_diff_density/tallies.xml
Normal file
7
tests/test_diff_density/tallies.xml
Normal file
|
|
@ -0,0 +1,7 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<tallies>
|
||||
<tally id="1">
|
||||
<scores>keff</scores>
|
||||
<derivative variable="density" material="10000"/>
|
||||
</tally>
|
||||
</tallies>
|
||||
11
tests/test_diff_density/test_diff_density.py
Executable file
11
tests/test_diff_density/test_diff_density.py
Executable file
|
|
@ -0,0 +1,11 @@
|
|||
#!/usr/bin/env python
|
||||
|
||||
import os
|
||||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*', True)
|
||||
harness.main()
|
||||
164
tests/test_diff_nuclide_density/build_xml.py
Normal file
164
tests/test_diff_nuclide_density/build_xml.py
Normal file
|
|
@ -0,0 +1,164 @@
|
|||
import openmc
|
||||
|
||||
|
||||
def make_mats(**kwargs):
|
||||
water_dict = {
|
||||
'B-10': 8.0042e-06,
|
||||
'B-11': 3.2218e-05,
|
||||
'H-1': 4.9457e-02,
|
||||
'H-2': 7.4196e-06,
|
||||
'O-16': 2.4672e-02,
|
||||
'O-17': 9.3982e-06 + 5.0701e-05}
|
||||
water = openmc.Material(name='water')
|
||||
water.set_density('sum')
|
||||
for nuclide in water_dict:
|
||||
water.add_nuclide(nuclide, water_dict[nuclide])
|
||||
|
||||
U235_dens = kwargs.setdefault('U235_dens', 5.5814e-04)
|
||||
fuel_dict = {
|
||||
'B-10': 8.0042e-06,
|
||||
'U-234': 4.4842e-06,
|
||||
'U-235': U235_dens,
|
||||
'U-238': 2.2407e-02,
|
||||
'O-16': 4.5828e-02,
|
||||
'O-17': 1.7457e-05 + 9.4176e-05}
|
||||
fuel = openmc.Material(name='fuel 2.4%')
|
||||
fuel.set_density('sum')
|
||||
for nuclide in fuel_dict:
|
||||
fuel.add_nuclide(nuclide, fuel_dict[nuclide])
|
||||
|
||||
zirc4_dict = {
|
||||
'O-16': 3.0743e-04,
|
||||
'O-17': 1.1711e-07 + 6.3176e-07,
|
||||
'Cr-50': 3.2962e-06,
|
||||
'Cr-52': 6.3564e-05,
|
||||
'Cr-53': 7.2076e-06,
|
||||
'Cr-54': 1.7941e-06,
|
||||
'Fe-54': 8.6699e-06,
|
||||
'Fe-56': 1.3610e-04,
|
||||
'Fe-57': 3.1431e-06,
|
||||
'Fe-58': 4.1829e-07,
|
||||
'Zr-90': 2.1827e-02,
|
||||
'Zr-91': 4.7600e-03,
|
||||
'Zr-92': 7.2758e-03,
|
||||
'Zr-94': 7.3734e-03,
|
||||
'Zr-96': 1.1879e-03,
|
||||
'Sn-112': 4.6735e-06,
|
||||
'Sn-114': 3.1799e-06,
|
||||
'Sn-115': 1.6381e-06,
|
||||
'Sn-116': 7.0055e-05,
|
||||
'Sn-117': 3.7003e-05,
|
||||
'Sn-118': 1.1669e-04,
|
||||
'Sn-119': 4.1387e-05,
|
||||
'Sn-120': 1.5697e-04,
|
||||
'Sn-122': 2.2308e-05,
|
||||
'Sn-124': 2.7897e-05}
|
||||
zirc4 = openmc.Material(name='zircaloy 4')
|
||||
zirc4.set_density('sum')
|
||||
for nuclide in zirc4_dict:
|
||||
zirc4.add_nuclide(nuclide, zirc4_dict[nuclide])
|
||||
|
||||
materials_file = openmc.MaterialsFile()
|
||||
materials_file.default_xs = '71c'
|
||||
materials_file.add_materials([water, fuel, zirc4])
|
||||
|
||||
return (materials_file,
|
||||
{'mod':water,
|
||||
'fuel':fuel,
|
||||
'clad':zirc4})
|
||||
|
||||
|
||||
def make_geom(mats):
|
||||
# Instantiate surfaces.
|
||||
rfo = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.39218, name='fuel outer')
|
||||
rci = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.40005, name='clad inner')
|
||||
rco = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.45720, name='clad outer')
|
||||
|
||||
x0 = openmc.XPlane(x0=-0.62992)
|
||||
x1 = openmc.XPlane(x0=0.62992)
|
||||
y0 = openmc.YPlane(y0=-0.62992)
|
||||
y1 = openmc.YPlane(y0=0.62992)
|
||||
z0 = openmc.ZPlane(z0=-1.0)
|
||||
z1 = openmc.ZPlane(z0=1.0)
|
||||
x0.boundary_type = 'reflective'
|
||||
x1.boundary_type = 'reflective'
|
||||
y0.boundary_type = 'reflective'
|
||||
y1.boundary_type = 'reflective'
|
||||
z0.boundary_type = 'reflective'
|
||||
z1.boundary_type = 'reflective'
|
||||
|
||||
# Instantiate cells.
|
||||
fuel_c = openmc.Cell(name='fuel')
|
||||
fuel_c.add_surface(rfo, halfspace=-1)
|
||||
fuel_c.add_surface(z0, halfspace=+1)
|
||||
fuel_c.add_surface(z1, halfspace=-1)
|
||||
|
||||
gap = openmc.Cell(name='gap')
|
||||
gap.add_surface(rci, halfspace=-1)
|
||||
gap.add_surface(rfo, halfspace=+1)
|
||||
gap.add_surface(z0, halfspace=+1)
|
||||
gap.add_surface(z1, halfspace=-1)
|
||||
|
||||
clad_c = openmc.Cell(name='clad')
|
||||
clad_c.add_surface(rco, halfspace=-1)
|
||||
clad_c.add_surface(rci, halfspace=+1)
|
||||
clad_c.add_surface(z0, halfspace=+1)
|
||||
clad_c.add_surface(z1, halfspace=-1)
|
||||
|
||||
mod_c = openmc.Cell(name='moderator')
|
||||
mod_c.add_surface(rco, halfspace=+1)
|
||||
mod_c.add_surface(x0, halfspace=+1)
|
||||
mod_c.add_surface(x1, halfspace=-1)
|
||||
mod_c.add_surface(y0, halfspace=+1)
|
||||
mod_c.add_surface(y1, halfspace=-1)
|
||||
mod_c.add_surface(z0, halfspace=+1)
|
||||
mod_c.add_surface(z1, halfspace=-1)
|
||||
|
||||
# Add materials to cells.
|
||||
fuel_c.fill = mats['fuel']
|
||||
gap.fill = 'void'
|
||||
clad_c.fill = mats['clad']
|
||||
mod_c.fill = mats['mod']
|
||||
|
||||
# Instantiate universes.
|
||||
u0 = openmc.Universe(universe_id=0)
|
||||
u0.add_cells([fuel_c, gap, clad_c, mod_c])
|
||||
|
||||
# Write the XML file.
|
||||
geometry = openmc.Geometry()
|
||||
geometry.root_universe = u0
|
||||
geometry_file = openmc.GeometryFile()
|
||||
geometry_file.geometry = geometry
|
||||
|
||||
return geometry_file
|
||||
|
||||
|
||||
def make_settings(**kwargs):
|
||||
if 'batches' in kwargs:
|
||||
batches = kwargs['batches']
|
||||
|
||||
settings_file = openmc.SettingsFile()
|
||||
settings_file.batches = kwargs.setdefault('batches', 1610)
|
||||
settings_file.inactive = kwargs.setdefault('inactive', 10)
|
||||
settings_file.particles = kwargs.setdefault('particles', 1000)
|
||||
settings_file.set_source_space('box', (-0.6, -0.6, -0.9,
|
||||
0.6, 0.6, 0.9))
|
||||
settings_file.entropy_lower_left = (-0.7, -0.7, -1.1)
|
||||
settings_file.entropy_upper_right = (0.7, 0.7, 1.1)
|
||||
settings_file.entropy_dimension = (10, 10, 10)
|
||||
return settings_file
|
||||
|
||||
|
||||
def make_inputs(**kwargs):
|
||||
(mat_file, mats) = make_mats(**kwargs)
|
||||
mat_file.export_to_xml()
|
||||
|
||||
geo_file = make_geom(mats)
|
||||
geo_file.export_to_xml()
|
||||
|
||||
sets_file = make_settings(**kwargs)
|
||||
sets_file.export_to_xml()
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
make_inputs(inactive=5, batches=10, particles=100)
|
||||
16
tests/test_diff_nuclide_density/geometry.xml
Normal file
16
tests/test_diff_nuclide_density/geometry.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10001" name="fuel" region="(-10000 10007 -10008)" universe="0" />
|
||||
<cell id="10001" material="void" name="gap" region="(-10001 10000 10007 -10008)" universe="0" />
|
||||
<cell id="10002" material="10002" name="clad" region="(-10002 10001 10007 -10008)" universe="0" />
|
||||
<cell id="10003" material="10000" name="moderator" region="(10002 10003 -10004 10005 -10006 10007 -10008)" universe="0" />
|
||||
<surface boundary="transmission" coeffs="0.0 0.0 0.39218" id="10000" name="fuel outer" type="z-cylinder" />
|
||||
<surface boundary="transmission" coeffs="0.0 0.0 0.40005" id="10001" name="clad inner" type="z-cylinder" />
|
||||
<surface boundary="transmission" coeffs="0.0 0.0 0.4572" id="10002" name="clad outer" type="z-cylinder" />
|
||||
<surface boundary="reflective" coeffs="-0.62992" id="10003" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.62992" id="10004" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="-0.62992" id="10005" type="y-plane" />
|
||||
<surface boundary="reflective" coeffs="0.62992" id="10006" type="y-plane" />
|
||||
<surface boundary="reflective" coeffs="-1.0" id="10007" type="z-plane" />
|
||||
<surface boundary="reflective" coeffs="1.0" id="10008" type="z-plane" />
|
||||
</geometry>
|
||||
50
tests/test_diff_nuclide_density/materials.xml
Normal file
50
tests/test_diff_nuclide_density/materials.xml
Normal file
|
|
@ -0,0 +1,50 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<default_xs>71c</default_xs>
|
||||
<material id="10000" name="water">
|
||||
<density units="sum" />
|
||||
<nuclide ao="6.00992e-05" name="O-17" />
|
||||
<nuclide ao="0.024672" name="O-16" />
|
||||
<nuclide ao="8.0042e-06" name="B-10" />
|
||||
<nuclide ao="3.2218e-05" name="B-11" />
|
||||
<nuclide ao="0.049457" name="H-1" />
|
||||
<nuclide ao="7.4196e-06" name="H-2" />
|
||||
</material>
|
||||
<material id="10001" name="fuel 2.4%">
|
||||
<density units="sum" />
|
||||
<nuclide ao="0.022407" name="U-238" />
|
||||
<nuclide ao="0.000111633" name="O-17" />
|
||||
<nuclide ao="8.0042e-06" name="B-10" />
|
||||
<nuclide ao="0.045828" name="O-16" />
|
||||
<nuclide ao="4.4842e-06" name="U-234" />
|
||||
<nuclide ao="0.00055814" name="U-235" />
|
||||
</material>
|
||||
<material id="10002" name="zircaloy 4">
|
||||
<density units="sum" />
|
||||
<nuclide ao="0.00011669" name="Sn-118" />
|
||||
<nuclide ao="4.1387e-05" name="Sn-119" />
|
||||
<nuclide ao="4.6735e-06" name="Sn-112" />
|
||||
<nuclide ao="3.1799e-06" name="Sn-114" />
|
||||
<nuclide ao="1.6381e-06" name="Sn-115" />
|
||||
<nuclide ao="7.0055e-05" name="Sn-116" />
|
||||
<nuclide ao="3.7003e-05" name="Sn-117" />
|
||||
<nuclide ao="0.0001361" name="Fe-56" />
|
||||
<nuclide ao="3.1431e-06" name="Fe-57" />
|
||||
<nuclide ao="8.6699e-06" name="Fe-54" />
|
||||
<nuclide ao="4.1829e-07" name="Fe-58" />
|
||||
<nuclide ao="0.0072758" name="Zr-92" />
|
||||
<nuclide ao="2.7897e-05" name="Sn-124" />
|
||||
<nuclide ao="0.00015697" name="Sn-120" />
|
||||
<nuclide ao="2.2308e-05" name="Sn-122" />
|
||||
<nuclide ao="1.7941e-06" name="Cr-54" />
|
||||
<nuclide ao="6.3564e-05" name="Cr-52" />
|
||||
<nuclide ao="7.2076e-06" name="Cr-53" />
|
||||
<nuclide ao="3.2962e-06" name="Cr-50" />
|
||||
<nuclide ao="7.4887e-07" name="O-17" />
|
||||
<nuclide ao="0.00030743" name="O-16" />
|
||||
<nuclide ao="0.00476" name="Zr-91" />
|
||||
<nuclide ao="0.021827" name="Zr-90" />
|
||||
<nuclide ao="0.0011879" name="Zr-96" />
|
||||
<nuclide ao="0.0073734" name="Zr-94" />
|
||||
</material>
|
||||
</materials>
|
||||
5
tests/test_diff_nuclide_density/results_true.dat
Normal file
5
tests/test_diff_nuclide_density/results_true.dat
Normal file
|
|
@ -0,0 +1,5 @@
|
|||
k-combined:
|
||||
1.055198E+00 5.785829E-02
|
||||
tally 1:
|
||||
3.081784E+03
|
||||
1.905482E+06
|
||||
18
tests/test_diff_nuclide_density/settings.xml
Normal file
18
tests/test_diff_nuclide_density/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<settings>
|
||||
<eigenvalue>
|
||||
<particles>100</particles>
|
||||
<batches>10</batches>
|
||||
<inactive>5</inactive>
|
||||
</eigenvalue>
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-0.6 -0.6 -0.9 0.6 0.6 0.9</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<entropy>
|
||||
<dimension>10 10 10</dimension>
|
||||
<lower_left>-0.7 -0.7 -1.1</lower_left>
|
||||
<upper_right>0.7 0.7 1.1</upper_right>
|
||||
</entropy>
|
||||
</settings>
|
||||
10
tests/test_diff_nuclide_density/tallies.xml
Normal file
10
tests/test_diff_nuclide_density/tallies.xml
Normal file
|
|
@ -0,0 +1,10 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<tallies>
|
||||
<tally id="1">
|
||||
<scores>keff</scores>
|
||||
<!--
|
||||
<derivative variable="density" material="10000"/>
|
||||
-->
|
||||
<derivative variable="nuclide_density" material="10001" nuclide="U-235.71c"/>
|
||||
</tally>
|
||||
</tallies>
|
||||
11
tests/test_diff_nuclide_density/test_diff_nuclide_density.py
Executable file
11
tests/test_diff_nuclide_density/test_diff_nuclide_density.py
Executable file
|
|
@ -0,0 +1,11 @@
|
|||
#!/usr/bin/env python
|
||||
|
||||
import os
|
||||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*', True)
|
||||
harness.main()
|
||||
Loading…
Add table
Add a link
Reference in a new issue