Abstract
The cross-section processing code NJOY has been modified to calculate flux-averaged partially integrated differential displacement kerma cross sections, or displacement kerma matrix elements, for neutron interactions. These, and total displacement kerma cross sections, have been calculated using ENDF/B-V and ENDL-84 data files for Si, Ga, and As. The displacement kerma matrices for Si and GaAs allow calculations of the distribution of displacement energy between displacement cascades.
| Original language | English |
|---|---|
| Pages (from-to) | 2219-2228 |
| Number of pages | 10 |
| Journal | IEEE Transactions on Nuclear Science |
| Volume | 37 |
| Issue number | 6 |
| DOIs | |
| State | Published - Dec 1990 |
| Externally published | Yes |
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