Difference between revisions of "Output parameters"
(→Group constants homogenized in infinite spectrum) |
(→Reaction cross sections) |
||
| Line 63: | Line 63: | ||
| Reduced absorption cross section (total - scattering production) | | Reduced absorption cross section (total - scattering production) | ||
|- | |- | ||
| + | |- | ||
| + | |} | ||
| + | |||
| + | ==== Fission spectra ==== | ||
| + | |||
| + | {|class="wikitable" style="text-align: left;" | ||
| + | ! Parameter | ||
| + | ! Size | ||
| + | ! Description | ||
| INF_CHIT | | INF_CHIT | ||
| 2''G'' | | 2''G'' | ||
| Line 74: | Line 83: | ||
| 2''G'' | | 2''G'' | ||
| Fission spectrum (delayed neutrons) | | Fission spectrum (delayed neutrons) | ||
| + | |- | ||
| + | |} | ||
| + | |||
| + | ==== Poison cross sections ==== | ||
| + | |||
| + | {|class="wikitable" style="text-align: left;" | ||
| + | ! Parameter | ||
| + | ! Size | ||
| + | ! Description | ||
|- | |- | ||
| INF_I135_YIELD | | INF_I135_YIELD | ||
Revision as of 18:19, 22 February 2016
Contents
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) |
Poison cross sections
| 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 |
