ZZ DLC-15 STORM-ISRAEL, Gamma Interaction Cross-Section Library in ENDF/B Format for Transport

1 - Nature of physical problem solved: Format: Data in ENDF/B file 23 format. Number of groups: energies from 1 KeV to 100 MeV; Nuclides: elements Z=1 to 100. Origin: E. Storm and H.I. Israel compilation. For use in general purpose gamma-ray transport codes. 2 - Method of solution: A discussion of the evaluation and much of the data were published in ref.1. The data are given in barns/atom for energies 1 keV to 100 MeV and for elements Z=1 to 100. The material numbers (MAT) are equal to the atomic numbers (Z). D.J. Dudziak placed the data in ENDF/B BCD format. The reaction type numbers (MT) used are consistent with those recommended in ENDF publications where possible, although several had to be assigned for the purpose. In the newer nomenclature σa(tot) and σh(tot) may be regarded as kerma factors which should be applied to the spectral flux density in a fashion consistent with the transport calculation which determined the flux density. That is, if the transport model assumes bound-electron incoherent scattering and treats secondary photons from pair production and photoelectric reactions, σa(tot) should be used to calculate Kerma. If the model assumes free-electron incoherent scattering and treats pair production and photoelectric reactions as absorption, σh(tot) should be used