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Appendix B: Tabulations of Data

The evaluated nuclear reaction cross sections are presented both as printed tabulations in Appendices C and D of this Report, and as electronic files on the CD accompanying the Report. For each element, there are three types of electronic file on the CD which contain data in ENDF and ENDF-easy formats, as well as electronic versions of the printed table, and these are discussed in detail later in this section. Owing to space limitations, the tables printed in the Report (particularly the extensive Tables C.5 and D.2 of production cross section spectra) are on a coarse incident energy grid, and omit certain types of information. In particular, emission spectra of gamma-rays and recoils are omitted (deuteron, triton, and alpha-particle ejectiles are also omitted for incident protons in Table D.2), as are elastic scattering angular distributions. However, this information is given on the accompanying ENDF and ENDF-easy electronic files on the CD (see below). Since a knowledge of nuclear recoil spectra is important in certain dosimetry applications (e.g., for studying RBE), illustrative recoil spectra for p + 160 reactions are shown in Table D.3, and the reader is referred to the ENDF and ENDF-easy files for the full tabulations. Also, electronic versions of the printed Tables C.5 and D.2 on the CD (the Icrutab files) contain cross section data on a much finer incident-energy grid. Most of the emission spectra tabulated in Tables C.5 and D.2 have been re-binned on a coarser emission energy grid to limit the size of the printed tables. While this re-binning preserved the essential details of the spectra, it can result in small deviations in the average energy of the ejectiles. Therefore, the values of the average energies and kerma coefficients in these tables have been taken from the fine-grid (pre-binned) calculations. In Tables C.5 and D.2, an energy deposition summary is presented at the beginning of each section, which includes partial kerma coefficients for incident neutron reactions. Also given is f. , the average fraction of the incident kinetic energy transferred to ejectile i per nonelastic reaction. This quantity is useful in the implementation of these cross section data in a radiation transport code, since, if the user does not wish to explicitly transport radiation of type i, then f; can be used to determine the amount of energy that should be deposited locally in a collision. The sum of ti over all ejectile types does not equal unity due to finite reaction Q-values (some kinetic energy is converted to mass).