Differential displacement kerma cross sections for neutron interactions in Si and GaAs
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, along with total displacement kerma cross sections, have been calculated usin...
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Veröffentlicht in: | IEEE transactions on nuclear science 1990-12, Vol.37 (6), p.2219-2228 |
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Sprache: | eng |
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Zusammenfassung: | 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, along with total displacement kerma cross sections, have been calculated using ENDF/B-V and ENDL-84 data files for Si, Ga, and As. These displacement kerma matrices for Si and GaAs allow calculations of the distribution of displacement energy between displacement cascades. The tabulation of kerma cross sections for Si constitutes a complete revision of the data used in current standard practices. Another contribution is the tabulated kerma cross sections for GaAs.< > |
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ISSN: | 0018-9499 1558-1578 |
DOI: | 10.1109/TNS.1990.574218 |