Difference between revisions of "Output parameters"
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*The few-group structure is defined using option [[Input syntax manual#set nfg|set nfg]]. | *The few-group structure is defined using option [[Input syntax manual#set nfg|set nfg]]. | ||
*The universes in which the group constants are calculated are listed in option [[Input syntax manual#set gcu|set gcu]]. The calculation is performed for root universe 0 by default, and can be switched off with "set gcu -1". | *The universes in which the group constants are calculated are listed in option [[Input syntax manual#set gcu|set gcu]]. The calculation is performed for root universe 0 by default, and can be switched off with "set gcu -1". | ||
− | *The parameter names can be listed in the [[Input syntax manual#set coefpara|set coefpara]] option, and they will be included in the [[Automated burnup sequence#Output|group constant output file]]. | + | *The parameter names can be listed in the [[Input syntax manual#set coefpara|set coefpara]] option, and they will be included in the [[Automated burnup sequence#Output|group constant output file]] when the automated burnup sequence is invoked. |
=== Group constants homogenized in infinite spectrum === | === Group constants homogenized in infinite spectrum === |
Revision as of 07:24, 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".
- The parameter names can be listed in the set coefpara option, and they will be included in the group constant output file when the automated burnup sequence is invoked.
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.
- Fluxes and currents are normalized average values.
- When the homogenized region is surrounded by reflective boundary conditions (zero net-current) the homogeneous flux becomes flat and equal to the volume-averaged heterogeneous flux. When the net currents are non-zero, the homogeneous flux is obtained using the Built-in diffusion flux solver.
- 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
on surface/corner 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 | 2G ![]() |
Heterogeneous corner flux |
DF_HOM_VOL_FLUX | 2G | Homogeneous flux over homogenized cell |
DF_HOM_SURF_FLUX | 2G ![]() |
Homogeneous surface flux |
DF_HOM_CORN_FLUX | 2G ![]() |
Homogeneous corner flux |
DF_SURF_DF | 2G ![]() |
Surface discontinuity factors |
DF_CORN_DF | 2G ![]() |
Corner discontinuity factors |