This page lists the output parameters in the main _res.m output file.
Homogenized group constants
Group constants homogenized in infinite spectrum
| Parameter
|
Size
|
Description
|
| INF_MICRO_FLX
|
2H
|
Multi-group flux
|
| INF_FLX
|
2G
|
Few-group flux
|
| INF_KINF
|
2
|
Infinite multiplication factor
|
Reaction cross sections
| Parameter
|
Size
|
Description
|
| INF_TOT
|
2G
|
Total cross section
|
| INF_CAPT
|
2G
|
Capture cross section
|
| INF_FISS
|
2G
|
Fission cross section
|
| INF_NSF
|
2G
|
Fission neutron production cross section
|
| INF_KAPPA
|
2G
|
Average deposited fission energy (MeV)
|
| INF_INVV
|
2G
|
Inverse neutron speed (s/cm)
|
| INF_NUBAR
|
2G
|
Average neutron yield
|
| INF_ABS
|
2G
|
Absorption cross section (capture + fission)
|
| INF_REMXS
|
2G
|
Removal cross section (group-removal + absorption)
|
| INF_RABSXS
|
2G
|
Reduced absorption cross section (total - scattering production)
|
Fission spectra
| Parameter
|
Size
|
Description
|
| INF_CHIT
|
2G
|
Fission spectrum (total)
|
| INF_CHIP
|
2G
|
Fission spectrum (prompt neutrons)
|
| INF_CHID
|
2G
|
Fission spectrum (delayed neutrons)
|
Scattering cross sections
NOTE: Scattering production includes multiplying (n,2n), (n,3n), etc. reactions.
| Parameter
|
Size
|
Description
|
| INF_SCATT0
|
2G
|
Total P0 scattering cross section
|
| INF_SCATT1
|
2G
|
Total P1 scattering cross section
|
| INF_SCATT2
|
2G
|
Total P2 scattering cross section
|
| INF_SCATT3
|
2G
|
Total P3 scattering cross section
|
| INF_SCATT4
|
2G
|
Total P4 scattering cross section
|
| INF_SCATT5
|
2G
|
Total P5 scattering cross section
|
| INF_SCATT6
|
2G
|
Total P6 scattering cross section
|
| INF_SCATT7
|
2G
|
Total P7 scattering cross section
|
| INF_SCATTP0
|
2G
|
Total P0 scattering production cross section
|
| INF_SCATTP1
|
2G
|
Total P1 scattering production cross section
|
| INF_SCATTP2
|
2G
|
Total P2 scattering production cross section
|
| INF_SCATTP3
|
2G
|
Total P3 scattering production cross section
|
| INF_SCATTP4
|
2G
|
Total P4 scattering production cross section
|
| INF_SCATTP5
|
2G
|
Total P5 scattering production cross section
|
| INF_SCATTP6
|
2G
|
Total P6 scattering production cross section
|
| INF_SCATTP7
|
2G
|
Total P7 scattering production cross section
|
Scattering matrices
NOTE: Scattering production includes multiplying (n,2n), (n,3n), etc. reactions. The order of values (.coe) or value pairs (_res.m) is: 
where 
refers to scattering from group g to g'. The data in the _res.m file can be read into a G by G matrix with Matlab reshape-command, for example: reshape(INF_S0(idx,1:2:end), G, G).
| Parameter
|
Size
|
Description
|
| INF_S0
|
4G2
|
P0 scattering matrix
|
| INF_S1
|
4G2
|
P1 scattering matrix
|
| INF_S2
|
4G2
|
P2 scattering matrix
|
| INF_S3
|
4G2
|
P3 scattering matrix
|
| INF_S4
|
4G2
|
P4 scattering matrix
|
| INF_S5
|
4G2
|
P5 scattering matrix
|
| INF_S6
|
4G2
|
P6 scattering matrix
|
| INF_S7
|
4G2
|
P7 scattering matrix
|
| INF_SP0
|
4G2
|
P0 scattering production matrix
|
| INF_SP1
|
4G2
|
P1 scattering production matrix
|
| INF_SP2
|
4G2
|
P2 scattering production matrix
|
| INF_SP3
|
4G2
|
P3 scattering production matrix
|
| INF_SP4
|
4G2
|
P4 scattering production matrix
|
| INF_SP5
|
4G2
|
P5 scattering production matrix
|
| INF_SP6
|
4G2
|
P6 scattering production matrix
|
| INF_SP7
|
4G2
|
P7 scattering production matrix
|
Diffusion parameters
| Parameter
|
Size
|
Description
|
| INF_TRANSPXS
|
2G
|
Transport cross section
|
| INF_DIFFCOEF
|
2G
|
Diffusion coefficient
|
Poison cross sections
NOTE: Printed only if poison cross section option is on (see set poi).
| Parameter
|
Size
|
Description
|
| INF_I135_YIELD
|
2G
|
Fission yield of I-135 (cumulative, includes all precursors)
|
| INF_XE135_YIELD
|
2G
|
Fission yield of Xe-135
|
| INF_PM149_YIELD
|
2G
|
Fission yield of Pm-149 (cumulative, includes all precursors)
|
| INF_SM149_YIELD
|
2G
|
Fission yield of Sm-149
|
| INF_I135_MICRO_ABS
|
2G
|
Microscopic absorption cross section of I-135
|
| INF_XE135_MICRO_ABS
|
2G
|
Microscopic absorption cross section of Xe-135
|
| INF_PM149_MICRO_ABS
|
2G
|
Microscopic absorption cross section of Pm-149
|
| INF_SM149_MICRO_ABS
|
2G
|
Microscopic absorption cross section of Sm-149
|
| INF_I135_MACRO_ABS
|
2G
|
Macroscopic absorption cross section of I-135
|
| INF_XE135_MACRO_ABS
|
2G
|
Macroscopic absorption cross section of Xe-135
|
| INF_PM149_MACRO_ABS
|
2G
|
Macroscopic absorption cross section of Pm-149
|
| INF_SM149_MACRO_ABS
|
2G
|
Macroscopic absorption cross section of Sm-149
|
Group constants homogenized in B1 leakage-corrected spectrum
| Parameter
|
Size
|
Description
|
| B1_MICRO_FLX
|
2H
|
Multi-group flux
|
| B1_FLX
|
2G
|
Few-group flux
|
| B1_KINF
|
2
|
Infinite multiplication factor
|
| B1_KEFF
|
2
|
Effective multiplication factor
|
| B1_B2
|
2
|
Critical buckling
|
| B1_ERR
|
2
|
Absolute deviation of keff from unity
|
Reaction cross sections
| Parameter
|
Size
|
Description
|
| B1_TOT
|
2G
|
Total cross section
|
| B1_CAPT
|
2G
|
Capture cross section
|
| B1_FISS
|
2G
|
Fission cross section
|
| B1_NSF
|
2G
|
Fission neutron production cross section
|
| B1_KAPPA
|
2G
|
Average deposited fission energy (MeV)
|
| B1_INVV
|
2G
|
Inverse neutron speed (s/cm)
|
| B1_NUBAR
|
2G
|
Average neutron yield
|
| B1_ABS
|
2G
|
Absorption cross section (capture + fission)
|
| B1_REMXS
|
2G
|
Removal cross section (group-removal + absorption)
|
| B1_RABSXS
|
2G
|
Reduced absorption cross section (total - scattering production)
|
Fission spectra
| Parameter
|
Size
|
Description
|
| B1_CHIT
|
2G
|
Fission spectrum (total)
|
| B1_CHIP
|
2G
|
Fission spectrum (prompt neutrons)
|
| B1_CHID
|
2G
|
Fission spectrum (delayed neutrons)
|
Scattering cross sections
NOTE: Scattering production includes multiplying (n,2n), (n,3n), etc. reactions.
| Parameter
|
Size
|
Description
|
| B1_SCATT0
|
2G
|
Total P0 scattering cross section
|
| B1_SCATT1
|
2G
|
Total P1 scattering cross section
|
| B1_SCATT2
|
2G
|
Total P2 scattering cross section
|
| B1_SCATT3
|
2G
|
Total P3 scattering cross section
|
| B1_SCATT4
|
2G
|
Total P4 scattering cross section
|
| B1_SCATT5
|
2G
|
Total P5 scattering cross section
|
| B1_SCATT6
|
2G
|
Total P6 scattering cross section
|
| B1_SCATT7
|
2G
|
Total P7 scattering cross section
|
| B1_SCATTP0
|
2G
|
Total P0 scattering production cross section
|
| B1_SCATTP1
|
2G
|
Total P1 scattering production cross section
|
| B1_SCATTP2
|
2G
|
Total P2 scattering production cross section
|
| B1_SCATTP3
|
2G
|
Total P3 scattering production cross section
|
| B1_SCATTP4
|
2G
|
Total P4 scattering production cross section
|
| B1_SCATTP5
|
2G
|
Total P5 scattering production cross section
|
| B1_SCATTP6
|
2G
|
Total P6 scattering production cross section
|
| B1_SCATTP7
|
2G
|
Total P7 scattering production cross section
|
Scattering matrices
NOTE: Scattering production includes multiplying (n,2n), (n,3n), etc. reactions. The order of values (.coe) or value pairs (_res.m) is: where refers to scattering from group g to g'. The data in the _res.m file can be read into a G by G matrix with Matlab reshape-command, for example: reshape(B1_S0(idx,1:2:end), G, G).
| Parameter
|
Size
|
Description
|
| B1_S0
|
4G2
|
P0 scattering matrix
|
| B1_S1
|
4G2
|
P1 scattering matrix
|
| B1_S2
|
4G2
|
P2 scattering matrix
|
| B1_S3
|
4G2
|
P3 scattering matrix
|
| B1_S4
|
4G2
|
P4 scattering matrix
|
| B1_S5
|
4G2
|
P5 scattering matrix
|
| B1_S6
|
4G2
|
P6 scattering matrix
|
| B1_S7
|
4G2
|
P7 scattering matrix
|
| B1_SP0
|
4G2
|
P0 scattering production matrix
|
| B1_SP1
|
4G2
|
P1 scattering production matrix
|
| B1_SP2
|
4G2
|
P2 scattering production matrix
|
| B1_SP3
|
4G2
|
P3 scattering production matrix
|
| B1_SP4
|
4G2
|
P4 scattering production matrix
|
| B1_SP5
|
4G2
|
P5 scattering production matrix
|
| B1_SP6
|
4G2
|
P6 scattering production matrix
|
| B1_SP7
|
4G2
|
P7 scattering production matrix
|
Diffusion parameters
| Parameter
|
Size
|
Description
|
| B1_TRANSPXS
|
2G
|
Transport cross section (calculated from diffusion coefficient)
|
| B1_DIFFCOEF
|
2G
|
Diffusion coefficient
|
Poison cross sections
NOTE: Printed only if poison cross section option is on (see set poi).
| Parameter
|
Size
|
Description
|
| B1_I135_YIELD
|
2G
|
Fission yield of I-135 (cumulative, includes all precursors)
|
| B1_XE135_YIELD
|
2G
|
Fission yield of Xe-135
|
| B1_PM149_YIELD
|
2G
|
Fission yield of Pm-149 (cumulative, includes all precursors)
|
| B1_SM149_YIELD
|
2G
|
Fission yield of Sm-149
|
| B1_I135_MICRO_ABS
|
2G
|
Microscopic absorption cross section of I-135
|
| B1_XE135_MICRO_ABS
|
2G
|
Microscopic absorption cross section of Xe-135
|
| B1_PM149_MICRO_ABS
|
2G
|
Microscopic absorption cross section of Pm-149
|
| B1_SM149_MICRO_ABS
|
2G
|
Microscopic absorption cross section of Sm-149
|
| B1_I135_MACRO_ABS
|
2G
|
Macroscopic absorption cross section of I-135
|
| B1_XE135_MACRO_ABS
|
2G
|
Macroscopic absorption cross section of Xe-135
|
| B1_PM149_MACRO_ABS
|
2G
|
Macroscopic absorption cross section of Pm-149
|
| B1_SM149_MACRO_ABS
|
2G
|
Macroscopic absorption cross section of Sm-149
|
Delayed neutron data
NOTE: The output always consists of 9 values: total, followed by precursor group-wise values. If the number of groups is 6, the last two values are zero.
| Parameter
|
Size
|
Description
|
| BETA_EFF
|
9
|
Effective delayed neutron fraction (currently calculated using the Meulekamp method)
|
| LAMBDA
|
9
|
Decay constants
|
