Difference between revisions of "Output parameters"

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(→‎Poison cross sections)
(→‎Group constants homogenized in infinite spectrum)
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|-
 
|-
 
| INF_SM149_MACRO_ABS
 
| INF_SM149_MACRO_ABS
 +
| 2''G''
 +
| Macroscopic absorption cross section of Sm-149
 +
|-
 +
|}
 +
==== Reaction cross sections ====
 +
 +
{|class="wikitable" style="text-align: left;"
 +
! Parameter
 +
! Size
 +
! Description
 +
|- 
 +
| B1_MICRO_FLX
 +
| 2''H''
 +
| Flux spectrum on the multi-group structure
 +
|-
 +
| B1_FLX
 +
| 2''G''
 +
| Flux
 +
|-
 +
| B1_KINF
 +
| 2
 +
| Infinite multiplication factor
 +
|-
 +
| B1_TOT
 +
| 2''G''
 +
| Total cross section
 +
|-
 +
| B1_CAPT
 +
| 2''G''
 +
| Capture cross section
 +
|-
 +
| B1_FISS
 +
| 2''G''
 +
| Fission cross section
 +
|-
 +
| B1_NSF
 +
| 2''G''
 +
| Fission neutron production cross section
 +
|-
 +
| B1_KAPPA
 +
| 2''G''
 +
| Average deposited fission energy (MeV)
 +
|-
 +
| B1_INVV
 +
| 2''G''
 +
| Inverse neutron speed (s/cm)
 +
|-
 +
| B1_NUBAR
 +
| 2''G''
 +
| Average neutron yield
 +
|-
 +
| B1_ABS
 +
| 2''G''
 +
| Absorption cross section (capture + fission)
 +
|-
 +
| B1_REMXS
 +
| 2''G''
 +
| Removal cross section (group-removal + absorption)
 +
|-
 +
| B1_RABSXS
 +
| 2''G''
 +
| Reduced absorption cross section (total - scattering production)
 +
|-
 +
|-
 +
|}
 +
 +
==== Fission spectra ====
 +
 +
{|class="wikitable" style="text-align: left;"
 +
! Parameter
 +
! Size
 +
! Description
 +
|-
 +
| B1_CHIT
 +
| 2''G''
 +
| Fission spectrum (total)
 +
|-
 +
| B1_CHIP
 +
| 2''G''
 +
| Fission spectrum (prompt neutrons)
 +
|-
 +
| B1_CHID
 +
| 2''G''
 +
| Fission spectrum (delayed neutrons)
 +
|-
 +
|}
 +
 +
==== Scattering cross sections ====
 +
 +
NOTE: Scattering production includes multiplying (n,2n), (n,3n), etc. reactions.
 +
 +
{|class="wikitable" style="text-align: left;"
 +
! Parameter
 +
! Size
 +
! Description
 +
|-
 +
| B1_SCATT0
 +
| 2''G''
 +
| Total ''P''<sub>0</sub> scattering cross section
 +
|-
 +
| B1_SCATT1
 +
| 2''G''
 +
| Total ''P''<sub>1</sub> scattering cross section
 +
|-
 +
| B1_SCATT2
 +
| 2''G''
 +
| Total ''P''<sub>2</sub> scattering cross section
 +
|-
 +
| B1_SCATT3
 +
| 2''G''
 +
| Total ''P''<sub>3</sub> scattering cross section
 +
|-
 +
| B1_SCATT4
 +
| 2''G''
 +
| Total ''P''<sub>4</sub> scattering cross section
 +
|-
 +
| B1_SCATT5
 +
| 2''G''
 +
| Total ''P''<sub>5</sub> scattering cross section
 +
|-
 +
| B1_SCATT6
 +
| 2''G''
 +
| Total ''P''<sub>6</sub> scattering cross section
 +
|-
 +
| B1_SCATT7
 +
| 2''G''
 +
| Total ''P''<sub>7</sub> scattering cross section
 +
|-
 +
| B1_SCATTP0
 +
| 2''G''
 +
| Total ''P''<sub>0</sub> scattering production cross section
 +
|-
 +
| B1_SCATTP1
 +
| 2''G''
 +
| Total ''P''<sub>1</sub> scattering production cross section
 +
|-
 +
| B1_SCATTP2
 +
| 2''G''
 +
| Total ''P''<sub>2</sub> scattering production cross section
 +
|-
 +
| B1_SCATTP3
 +
| 2''G''
 +
| Total ''P''<sub>3</sub> scattering production cross section
 +
|-
 +
| B1_SCATTP4
 +
| 2''G''
 +
| Total ''P''<sub>4</sub> scattering production cross section
 +
|-
 +
| B1_SCATTP5
 +
| 2''G''
 +
| Total ''P''<sub>5</sub> scattering production cross section
 +
|-
 +
| B1_SCATTP6
 +
| 2''G''
 +
| Total ''P''<sub>6</sub> scattering production cross section
 +
|-
 +
| B1_SCATTP7
 +
| 2''G''
 +
| Total ''P''<sub>7</sub> 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: <math>\Sigma_{1,1} \, \Sigma_{1,2} \, ... \, \Sigma_{2,1} \, \Sigma_{2,2}  \, ...</math> where <math>\Sigma_{g,g'}</math> 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).
 +
 +
{|class="wikitable" style="text-align: left;"
 +
! Parameter
 +
! Size
 +
! Description
 +
|-
 +
| B1_S0
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>0</sub> scattering matrix
 +
|-
 +
| B1_S1
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>1</sub> scattering matrix
 +
|-
 +
| B1_S2
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>2</sub> scattering matrix
 +
|-
 +
| B1_S3
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>3</sub> scattering matrix
 +
|-
 +
| B1_S4
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>4</sub> scattering matrix
 +
|-
 +
| B1_S5
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>5</sub> scattering matrix
 +
|-
 +
| B1_S6
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>6</sub> scattering matrix
 +
|-
 +
| B1_S7
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>7</sub> scattering matrix
 +
|-
 +
| B1_SP0
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>0</sub> scattering production matrix
 +
|-
 +
| B1_SP1
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>1</sub> scattering production matrix
 +
|-
 +
| B1_SP2
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>2</sub> scattering production matrix
 +
|-
 +
| B1_SP3
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>3</sub> scattering production matrix
 +
|-
 +
| B1_SP4
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>4</sub> scattering production matrix
 +
|-
 +
| B1_SP5
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>5</sub> scattering production matrix
 +
|-
 +
| B1_SP6
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>6</sub> scattering production matrix
 +
|-
 +
| B1_SP7
 +
| 4''G''<sup>2</sup>
 +
| ''P''<sub>7</sub> scattering production matrix
 +
|-
 +
|}
 +
 +
==== Diffusion parameters ====
 +
 +
{|class="wikitable" style="text-align: left;"
 +
! Parameter
 +
! Size
 +
! Description
 +
|-
 +
| B1_TRANSPXS
 +
| 2''G''
 +
| Transport cross section
 +
|-
 +
| B1_DIFFCOEF
 +
| 2''G''
 +
| Diffusion coefficient
 +
|-
 +
|}
 +
 +
==== Poison cross sections ====
 +
 +
NOTE: Printed only if poison cross section option is on (see [[Input syntax manual#set poi|set poi]]).
 +
 +
{|class="wikitable" style="text-align: left;"
 +
! Parameter
 +
! Size
 +
! Description
 +
|-
 +
| B1_I135_YIELD
 +
| 2''G''
 +
| Fission yield of I-135 (cumulative, includes all precursors)
 +
|-
 +
| B1_XE135_YIELD
 +
| 2''G''
 +
| Fission yield of Xe-135
 +
|-
 +
| B1_PM149_YIELD
 +
| 2''G''
 +
| Fission yield of Pm-149 (cumulative, includes all precursors)
 +
|-
 +
| B1_SM149_YIELD
 +
| 2''G''
 +
| Fission yield of Sm-149
 +
|-
 +
| B1_I135_MICRO_ABS
 +
| 2''G''
 +
| Microscopic absorption cross section of I-135
 +
|-
 +
| B1_XE135_MICRO_ABS
 +
| 2''G''
 +
| Microscopic absorption cross section of Xe-135
 +
|-
 +
| B1_PM149_MICRO_ABS
 +
| 2''G''
 +
| Microscopic absorption cross section of Pm-149
 +
|-
 +
| B1_SM149_MICRO_ABS
 +
| 2''G''
 +
| Microscopic absorption cross section of Sm-149
 +
|-
 +
| B1_I135_MACRO_ABS
 +
| 2''G''
 +
| Macroscopic absorption cross section of I-135
 +
|-
 +
| B1_XE135_MACRO_ABS
 +
| 2''G''
 +
| Macroscopic absorption cross section of Xe-135
 +
|-
 +
| B1_PM149_MACRO_ABS
 +
| 2''G''
 +
| Macroscopic absorption cross section of Pm-149
 +
|-
 +
| B1_SM149_MACRO_ABS
 
| 2''G''
 
| 2''G''
 
| Macroscopic absorption cross section of Sm-149
 
| Macroscopic absorption cross section of Sm-149

Revision as of 20:40, 22 February 2016

Homogenized group constants

Group constants homogenized in infinite spectrum

Reaction cross sections

Parameter Size Description
INF_MICRO_FLX 2H Flux spectrum on the multi-group structure
INF_FLX 2G Flux
INF_KINF 2 Infinite multiplication factor
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: \Sigma_{1,1} \, \Sigma_{1,2} \, ... \, \Sigma_{2,1} \, \Sigma_{2,2} \, ... where \Sigma_{g,g'} 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

Reaction cross sections

Parameter Size Description
B1_MICRO_FLX 2H Flux spectrum on the multi-group structure
B1_FLX 2G Flux
B1_KINF 2 Infinite multiplication factor
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: \Sigma_{1,1} \, \Sigma_{1,2} \, ... \, \Sigma_{2,1} \, \Sigma_{2,2} \, ... where \Sigma_{g,g'} 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
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
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