Output parameters: Difference between revisions

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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: 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

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: 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
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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