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Copy pathInput_RMINDD.txt
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84 lines (71 loc) · 2.01 KB
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## Input and data for module EngdepU of RMINDD
Module_number = 1
Module_name = "EngdepU"
Element_isotope =
Raw_ENDF6_file =
Preprocessed_ENDF6_file =
MAT_num =
Num_reaction =
Reaction_num =
Atom_displ_model =
Threshold_Ed =
b_arcdpa =
c_arcdpa =
Output_filenames =
## multigrouping yes=1 or no=0
Multigroup =
Energy_group_type_index =
## input neutron spectrum yes=1 or no=0
## if yes, then there should be Energy group limits in 'Energy-GroupLimits.txt' file and
## the neutron spectrum in 'NeutronSpectrum.txt' file
Input_n_spectrum =
Num_MT_to_multigroup =
MTs_to_multigroup =
## Input and data for module RecedU of RMINDD
Module_number = 2
Module_name = "RecedU"
Element_isotope =
Raw_ENDF6_file =
Preprocessed_ENDF6_file =
MAT_num =
Num_reaction =
Reaction_num =
Num_group_limits =
Num_fine_en_points =
Energy_group_type_index =
## Input and data for module TransmU of RMINDD
Module_number = 3
Module_name = "TransmU"
Element_isotope =
Raw_ENDF6_file =
Preprocessed_ENDF6_file =
MAT_num =
Transmgas_group_file =
Transmnucl_group_file =
Transmgas_point_file =
Transmnucl_point_file =
## Input and data for module CombinU of RMINDD
## CombinU requires output files from EngdepU for its calculations
Module_number = 4
Module_name = "CombinU"
Files_directory =
Num_elements_target =
Elements_target =
## give in the same order as given elements
Element_stoichiometries =
Num_isotopes_total =
## directories with these names will be searched for required files
Isotopes_evaluated =
## to be given in the same order as the isotopes are given
Percent_abundances_all =
## better to arrange data files according to the order of name of elements in the target
Recoil_damage_energy_file =
Recoil_damage_energy_file =
Element_Ed_target =
Element_Ed_target =
Ed_below_no_displacement =
Ed_below_no_displacement =
Atom_dpaXS_type = ## "MD-based", "NRT-based", "Both"
## there should be as many damage efficiency file as the number of target elements
Damage_efficiency_file =
Damage_efficiency_file =