Physics and Verification

Inclusive Cross-sections

All cross-section data are taken from the ENDF/B-VI [Gro91] evaluated data library.

All inclusive cross-sections are treated as point-wise cross-sections for reasons of performance. For this purpose, the data from the evaluated data library have been processed, to explicitly include all neutron nuclear resonances in the form of point-like cross-sections rather than in the form of parametrisations. The resulting data have been transformed into a linearly interpolable format, such that the error due to linear interpolation between adjacent data points is smaller than a few percent.

The inclusive cross-sections comply with the cross-sections data set interface of the Geant4 hadronic design. They are, when registered with the tool-kit at initialisation, used to select the basic process. In the case of fission and inelastic scattering, point-wise semi-inclusive cross-sections are also used in order to decide on the active channel for an individual interaction. As an example, in the case of fission this could be first, second, third, or fourth chance fission.

Bibliography

Gro91

ENDF/B-VI: Cross Section Evaluation Working Group. Endf/b-vi summary document. Technical Report BNL-NCS-17541 (ENDF-201), Brookhaven National Laboratory, Upton, NY, USA, 1991. edited by P.F. Rose, National Nuclear Data Center.