Makes data and post-processing scripts available for reproducibility to support publication. Be aware that the files included here allow to reproduce (for the most part) the results from the publication. However, some of the software developed for this publication should be treated as export control and it is not included in this repository.

Files:

• plots.py: plots figures comparing reference and repeated structures cases

All the following cases contain:

• mcnp1: MCNP input file for the burnup calculation
• results_heat_cell991.csv: csv files with delayed heating "H_T" by decay time step

MOAA calculates the depletion of cells:

101,102,103,104,105,106,107,108,109,110, 111,112,113,114,115,116,117,118,119,120, 121,122,123,124,125,126,127,128,129,130, 131,132,133,134,135,136,137,138,139,140, 141,142,143,144,145,146,147,148,149,150, 151,152,153,154,155,156,157,158,159,160, 161,162,163,164,991,

MOAA calculates the depletion of cells:

100,991

MOAA calculates the depletion of cells:

101,102,103,104,105,106,107,108,109,110, 111,112,113,114,115,116,991

Files:

• bench.template: contains ATR quarter model, with some fillable sections
• MOAA_burnup_FIMA.csv: MOAA burnup results
• *.csv files: contain benchmark data for power, neck shim insertion condition, and control drum angle
• create_files.py: automates the creation of the input files based on the *.csv files:
  • bench_{cycle}: MCNP input files for each irradiation cycle
  • sdr-agr.i: creates MCNP geometry for shutdown-dose rate calculation (source is not included as it is calculated by the shutdown-dose rate calculation workflow not included here)
• plots.py: plots burnup vs axial location and calculates the contribution from each photon source

MOAA calculates the depletion of cells:

• Stainless steel sections: 99971,91000,92000,93000,94000, 95000,96000,91091,92091,93091, 94091,95091,96091,91098,92098, 93098,94098,95098,96098,99980, 99981,99982,99983,99984,99985,

• Graphite spacers: 91001,92001,93001,94001,95001, 96001,91081,92081,93081,94081, 95081,96081,

• Borated graphite holder: 91080,92080,93080,94080,95080, 96080,

• Hf shroud: 91092,92092,93092,94092,95092, 96092,

• Fuel cells: 91101,91121,91141,91161,91201, 91221,91241,91261,91301,91321, 91341,91361,92101,92121,92141, 92161,92201,92221,92241,92261, 92301,92321,92341,92361,93101, 93121,93141,93161,93201,93221, 93241,93261,93301,93321,93341, 93361,94101,94121,94141,94161, 94201,94221,94241,94261,94301, 94321,94341,94361,95101,95121, 95141,95161,95201,95221,95241, 95261,95301,95321,95341,95361, 96101,96121,96141,96161,96201, 96221,96241,96261,96301,96321, 96341,96361,

Files:

• input_definition.py: holds several parameters shared by the burnup and shutdown-dose rate geometries.
• create_input_burnup.py: creates MCNP input file for burnup calculation (only core)
• create_input_sdr.py: creates MCNP geometry for shutdown-dose rate calculation (source is not included as it is calculated by the shutdown-dose rate calculation workflow not included here)

MOAA calculates the depletion of cells:

Fuel cells: 20101,20201,20301,20401,20501, 20601,21101,21201,21301,21401, 21501,21601,21701,21801,21901, 22001,22101,22201,23101,23201, 23301,23401,23501,23601,23701, 23801,23901,24001,24101,24201, 24301,24401,24501,24601,24701, 24801,

Block Graphite: 20111,20112,20114,20211,20212, 20214,20311,20312,20314,20411, 20412,20414,20511,20512,20514, 20611,20612,20614,21111,21112, 21114,21211,21212,21214,21311, 21312,21314,21411,21412,21414, 21511,21512,21514,21611,21612, 21614,21711,21712,21714,21811, 21812,21814,21911,21912,21914, 22011,22012,22014,22111,22112, 22114,22211,22212,22214,23111, 23112,23114,23211,23212,23214, 23311,23312,23314,23411,23412, 23414,23511,23512,23514,23611, 23612,23614,23711,23712,23714, 23811,23812,23814,23911,23912, 23914,24011,24012,24014,24111, 24112,24114,24211,24212,24214, 24311,24312,24314,24411,24412, 24414,24511,24512,24514,24611, 24612,24614,24711,24712,24714, 24811,24812,24814,

Reflector: 9990,9991,9992,9993,9994, 9995,