Difference between revisions of "Output parameters"
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| DF_HET_VOL_FLUX | | DF_HET_VOL_FLUX | ||
| ''2G'' | | ''2G'' | ||
− | | | + | | Heterogeneous flux over homogenized cell |
|- | |- | ||
| DF_HET_SURF_FLUX | | DF_HET_SURF_FLUX | ||
− | | '' | + | | ''2G'' <math>\times</math> ''N''<sub>S</sub> |
− | | | + | | Heterogeneous surface flux |
|- | |- | ||
| DF_HET_CORN_FLUX | | DF_HET_CORN_FLUX | ||
| ''G'' <math>\times</math> ''N''<sub>C</sub> | | ''G'' <math>\times</math> ''N''<sub>C</sub> | ||
− | | | + | | Heterogeneous corner flux |
|- | |- | ||
| DF_HOM_VOL_FLUX | | DF_HOM_VOL_FLUX | ||
− | | '' | + | | ''2G'' |
− | | | + | | Homogeneous flux over homogenized cell |
|- | |- | ||
| DF_HOM_SURF_FLUX | | DF_HOM_SURF_FLUX | ||
| ''G'' <math>\times</math> ''N''<sub>C</sub> | | ''G'' <math>\times</math> ''N''<sub>C</sub> | ||
− | | | + | | Homogeneous surface flux |
|- | |- | ||
| DF_HOM_CORN_FLUX | | DF_HOM_CORN_FLUX | ||
| ''G'' <math>\times</math> ''N''<sub>C</sub> | | ''G'' <math>\times</math> ''N''<sub>C</sub> | ||
− | | | + | | Homogeneous corner flux |
|- | |- | ||
| DF_SURF_DF | | DF_SURF_DF |
Revision as of 07:13, 23 February 2016
This page lists the output parameters in the main _res.m output file.
Contents
Homogenized group constants
Notes:
- Group constants are calculated by first homogenizing the geometry using a multi-group structure with H energy groups. The data is then collapsed into the final few-group structure with G groups using the infinite and B1 leakage-corrected flux spectra.
- The B1 calculation is off by default, and invoked by the set fum option.
- The intermediate multi-group structure is defined using option set micro.
- The few-group structure is defined using option set nfg.
- The universes in which the group constants are calculated are listed in option set gcu. The calculation is performed for root universe 0 by default, and can be switched off with "set gcu -1".
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
Notes:
- 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
Notes:
- 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
Notes:
- 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
Notes:
- 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
Notes:
- 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
Notes:
- 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
Notes:
- 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.
- The actual number of groups depends on the cross section library used in the calculations. JEFF-3.1, JEFF.3.2 and later evaluations use 8 precursor groups, while earlier evaluations, as well as all ENDF/B and JENDL data is based on 6 groups.
Parameter | Size | Description |
---|---|---|
BETA_EFF | 9 | Effective delayed neutron fraction (currently calculated using the Meulekamp method) |
LAMBDA | 9 | Decay constants |
Assembly discontinuity factors
Notes:
- Calculation of assembly discontinuity factors requires the set adf option.
- Surface flux and current tallies are used to calculate the boundary currents and fluxes. Mid-point and corner values are approximated by integrating over a small surface segment.
- The calculation currently supports only a limited number of surface types: infinite planes and square and hexagonal prisms.
- The order of surface and mid-point values for square prisms is:
and the order of corner values:
where
refers to parameter X on surface/corned k and energy group g.
- The order of surface and mid-point values for hexagonal prims runs clockwise starting from the north (Y-type) or east (X-type) face. The corner values start from the next corner in clockwise direction.
- Note to developers: the description may be wrong for for X-type hexagonal prism.
Parameter | Size | Description |
---|---|---|
DF_SURFACE | (string) | Name of the surface used for the calculation |
DF_SYM | 1 | Symmetry option defined in the input |
DF_N_SURF | 1 | Number of surface values (denoted as NS below) |
DF_N_CORN | 1 | Number of corner values (denoted as NC below) |
DF_VOLUME | 1 | Volume (3D) or cross sectional area (2D) of the homogenized cell |
DF_SURF_AREA | NS | Area (3D) or perimeter length (2D) of the surface region |
DF_MID_AREA | NS | Area (3D) or perimeter length (2D) of the mid-point region |
DF_CORN_AREA | NS | Area (3D) or perimeter length (2D) of the corner region |
DF_SURF_IN_CURR | 2G ![]() |
Inward surface currents |
DF_SURF_OUT_CURR | 2G ![]() |
Outward surface currents |
DF_SURF_NET_CURR | 2G ![]() |
Net surface currents |
DF_MID_IN_CURR | 2G ![]() |
Inward mid-point currents |
DF_MID_OUT_CURR | 2G ![]() |
Outward mid-point currents |
DF_MID_NET_CURR | 2G ![]() |
Net mid-point currents |
DF_CORN_IN_CURR | 2G ![]() |
Inward corner currents |
DF_CORN_OUT_CURR | 2G ![]() |
Outward corner currents |
DF_CORN_NET_CURR | 2G ![]() |
Net corner currents |
DF_HET_VOL_FLUX | 2G | Heterogeneous flux over homogenized cell |
DF_HET_SURF_FLUX | 2G ![]() |
Heterogeneous surface flux |
DF_HET_CORN_FLUX | G ![]() |
Heterogeneous corner flux |
DF_HOM_VOL_FLUX | 2G | Homogeneous flux over homogenized cell |
DF_HOM_SURF_FLUX | G ![]() |
Homogeneous surface flux |
DF_HOM_CORN_FLUX | G ![]() |
Homogeneous corner flux |
DF_SURF_DF | G ![]() |
|
DF_CORN_DF | G ![]() |