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1 | All cross-section data are taken from the ENDF/B-VI\cite{ENDF} |
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2 | evaluated data library. |
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3 | |
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4 | All inclusive cross-sections |
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5 | are treated as point-wise cross-sections for reasons of performance. |
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6 | For this purpose, the data from the evaluated data library have been processed, |
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7 | to explicitly include all neutron nuclear resonances in the form of |
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8 | point-like cross-sections rather than in the form of parametrisations. |
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9 | The resulting data have been transformed into a linearly interpolable format, |
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10 | such that the error due to linear interpolation between adjacent data points |
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11 | is smaller than a few percent. |
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12 | |
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13 | The inclusive cross-sections comply with the cross-sections data set interface |
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14 | of the {\sc Geant4} hadronic design. |
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15 | They are, when registered with the tool-kit at initialisation, used |
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16 | to select the basic process. |
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17 | In the case of fission and inelastic scattering, point-wise |
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18 | semi-inclusive cross-sections are also used in order to decide on the active |
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19 | channel |
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20 | for an individual interaction. As an example, in the case of fission |
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21 | this could be first, second, third, or forth chance fission. |
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