Difference between revisions of "Output parameters"

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! Description
 
! Description
 
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| B1_MICRO_FLX
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| INF_MICRO_FLX
 
| 2''H''
 
| 2''H''
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| Flux spectrum on the multi-group structure
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| Multi-group flux
 
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|-
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| B1_FLX
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| 2''G''
 
| 2''G''
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| Flux
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| Few-group flux
 
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| B1_KINF
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| 2
 
| 2
 
| Infinite multiplication factor
 
| Infinite multiplication factor
 
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==== Reaction cross sections ====
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{|class="wikitable" style="text-align: left;"
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! Parameter
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! Size
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! Description
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| B1_TOT
 
| B1_TOT
 
| 2''G''
 
| 2''G''
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| 2''G''
 
| 2''G''
 
| Reduced absorption cross section (total - scattering production)
 
| Reduced absorption cross section (total - scattering production)
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Revision as of 19:43, 22 February 2016

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: \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
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
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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