Difference between revisions of "Description of output files"
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*Neutron transport mode includes either reactions that affect neutron balance (absorption, fission, neutron-multiplying scattering) or all reactions, depending on the value of the input option. | *Neutron transport mode includes either reactions that affect neutron balance (absorption, fission, neutron-multiplying scattering) or all reactions, depending on the value of the input option. | ||
*All reaction modes are included in photon transport mode. | *All reaction modes are included in photon transport mode. | ||
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Revision as of 17:01, 23 November 2015
Contents
Default output files
The following output files are always produced.
Nuclide and material data
Optional output files
The following output files are produced by invoking various input options.
Reaction rate output
Calculation of analog reaction rates by counting the number of sampled interactions is invoked using the set arr option. The output is printed in file:
<input>_arr<bi>.m
Where:
| <input> | : is the name of the input file |
| <bi> | : is the burnup index (zero for first step or if no burnup calculation is run) |
The data is printed in Matlab format in two variables: string array "nuc", which contains the nuclide identifiers (ZA.id), and table "rr", consisting one row for each reaction and 7 columns:
- Nuclide index corresponding to the entries in the nuc array
- Reaction mt
- Nuclide ZAI
- Minimum energy of the reaction mode
- Maximum energy of the reaction mode
- Reaction rate
- Relative statistical error of reaction rate
Notes:
- The values are normalized microscopic reaction rates integrated over all materials and energies.
- Neutron transport mode includes either reactions that affect neutron balance (absorption, fission, neutron-multiplying scattering) or all reactions, depending on the value of the input option.
- All reaction modes are included in photon transport mode.
