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| procedure, public | init => orgneut__init |
| | Constructor. More...
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| procedure, public | destroy => orgneut__destroy |
| | Destructor. More...
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| procedure | nucalc => orgneut__nucalc |
| | Perform the neutron calculations. More...
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| procedure, public | output => orgneut__output |
| | Print the neutron output tables. More...
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| procedure, public | output_detailed_source => orgneut__output_detailed_source |
| | Print the detailed neutron source data. More...
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| procedure | output_source => orgneut__output_source |
| | Prints the neutron source tables. More...
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| procedure | output_spectra => orgneut__output_spectra |
| | Print neutron spectra: alpha-n, spon-fiss, delayed neutron, total. More...
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| procedure | define_matrix_uo2 => orgneut__define_matrix_uo2 |
| | Define UO2 (a,n) source matrix. More...
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| procedure | define_matrix_glass => orgneut__define_matrix_glass |
| | Define borosilicate glass (a,n) source matrix. More...
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| procedure | define_arbitrary_matrix => orgneut__define_arbitrary_matrix |
| | Define (a,n) source matrix based on actual concentrations in the NSTAR step. More...
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| procedure | order_sources => orgneut__order_sources |
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| procedure | order_target => orgneut__order_target |
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| procedure, public | get_spectrum => orgneut__get_spectrum |
| | Get the spectrum for a specific case: More...
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| |
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| integer | nsteps |
| | Number of steps. More...
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| type(origen_librarywrapper), pointer | lib => NULL() |
| | associated ORIGEN library More...
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| type(neutron_library_class), pointer | nlib => NULL() |
| | associated neutron library More...
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| type(origen_neutron_options) | opts |
| | set of options More...
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| real(c_double), dimension(:,:), allocatable | source_sf |
| | final spontaneous fission source by nuclide [libiact * 0:nsteps] More...
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| real(c_double), dimension(:,:), allocatable | source_an |
| | alpha,n source term by nuclide [libiact+libifp * 0:nsteps] More...
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| real(c_double), dimension(:,:), allocatable | source_dn |
| | delayed neutron sources [libifp * 0:nsteps] More...
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| real(c_double), dimension(:,:), allocatable | spectrum_an |
| | alpha,n neutron spectra [ngroups * 0:nsteps] More...
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| real(c_double), dimension(:,:), allocatable | spectrum_sf |
| | spontaneous fission neutron spectra [ngroups * 0:nsteps] More...
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| real(c_double), dimension(:,:), allocatable | spectrum_dn |
| | delayed neutron spectra [ngroups * 0:nsteps] More...
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| real(c_double), dimension(:,:), allocatable | spectrum |
| | final total neutron spectra [ngroups * 0:nsteps] More...
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| integer | n_source_nuclides |
| | number of sources nuclides More...
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| integer, dimension(:), allocatable | source_nuclides |
| | list of source nuclides - ZAI [n_source_nuclides] More...
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| integer, dimension(:), allocatable | source_nuclide_indexes |
| | list of source nuclides - M [n_source_nuclides] More...
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| real(c_double), dimension(:), allocatable | source_branching |
| | source nuclide total alpha branching ratios [n_source_nuclides] More...
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| real(c_double), dimension(:), allocatable | source_lambdas |
| | decay constants of source nuclides [n_source_nuclides] More...
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| real(c_double), dimension(:,:), allocatable | source_concentrations |
| | concentrations of the source nuclides [n_source_nuclides,0:nsteps] More...
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| integer | sf_source_n |
| | number of SF neutron sources More...
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| character(len=20), dimension(:), allocatable | sf_source_nuclides |
| | spontaneous fission neutron source nuclides [itot] More...
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| real(c_double), dimension(:,:), allocatable | sf_source_data |
| | spontaneous fission neutron source data [itot, 6] More...
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| real(c_double), dimension(:,:), allocatable | sf_source_spectra |
| | spontaneous fission neutron spectra by source nuclide [ngroups, itot] More...
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| integer | dn_source_n |
| | number of delayed neutron source nuclides More...
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| character(20), dimension(:), allocatable | dn_source_nuclides |
| | delayed neutron source nuclides [itot] More...
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| real(c_double), dimension(:,:), allocatable | dn_source_data |
| | delayed neutron source [itot, 5] More...
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| real(c_double), dimension(:,:), allocatable | dn_source_spectra |
| | delayed neutron spectra by source nuclide [ngroups, itot] More...
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| real(c_double) | average_energy_an |
| | average neutron energy (a,n) More...
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| real(c_double) | average_energy_sf |
| | average neutron energy (SF) More...
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| real(c_double) | average_energy_dn |
| | average neutron energy (DN) More...
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| real(c_double) | average_energy |
| | average neutron energy (total) More...
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| real(c_double), dimension(:,:), allocatable | an_target_spectra |
| | [ngroups, n_target] More...
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| integer | n_matrix |
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| integer, dimension(:), allocatable | matrix_z |
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| real(c_double), dimension(:), allocatable | matrix_x |
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| integer | n_target |
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| integer, dimension(:), allocatable | target_n |
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| real(c_double), dimension(:), allocatable | target_x |
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| logical | noneut |
| | flag for lack of neutron calculations data More...
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| |
Class handling the neutron calculations.
