Compilation of data averaged over incident neutron spectra for EXFOR library. Appendix 8

Cross section and other experimental neutron-induced reaction data measured under broad neutron spectra have been compiled in the EXFOR Library maintained by the International Network of Nuclear Reaction Data Centres (NRDC). In the current EXFOR Formats rule, the neutron field used in the measurement is indicated by a 'modifier' as a part of the code under the keyword REACTION, and its characteristic energy is coded with the measured cross section. Following the introduction of Westcott's convention, two spectrum modifiers MXW and SPA and two definitions of Maxwellian averaged cross sections (MACS) are presently used in compilation practice. To remove ambiguity, the compilation rules for neutron spectrum averaged quantity and representative energy are discussed in this Appendix.