8. Appendices

8.1 Appendix 1

Examples of different types of neutron spectra used in an effective cross-section processing system to determine multi-group effective cross-sections

Some spectra depend on parameters that can be set by the user of the cross-section processing codes. In the following, parameters and their default values are indicated; energies are expressed in electron volts (eV). Spectra are not necessarily normalized to unity: the spectra normalization constant is simplified when constructing the multi-group cross-section.

1. Maxwell spectrum

The Maxwell spectrum is defined by :

ϕ_{M} (E) = \frac{2 π}{{(π k T)}^{\frac{3}{2}}} exp (- \frac{E}{k T})

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Bibliography

(1) - ENDF-102 – ENDF-6 Formats Manual - Data formats and procedures for the evaluated nuclear data file ENDF/B- VI and ENDF/B- VII . - National Nuclear Data Center (NNDC), Brookhaven National Laboratory, Rapport faisant l'objet de versions révisées, État-Unis, juin 2009....

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