Nuclear data for fusion reactor technology

The need of specific fusion-oriented evaluated data libraries is stressed. A review is made of the nuclear data requirements: data types needed for fusion reactor functions, proposed materials for fusion reactors, typical accuracy requirements for neutron transport calculations. In more detail the situation of the experimental and theoretical double-differential neutron emission cross section is analyzed. The angle-integrated neutron emission spectra from different experiments (IRK, OSA, TUD, etc.) for Pb, Ni and '238U are presented. Creation of a specific Engineering Test Reactor nuclear data file for neutron and proton transport calculations based on reevaluations of the existing recent evaluations is discussed. The status and availability of current evaluations is given. The necessity of calculational and experimental benchmarks for testing the whole apparatus of fusion neutronics calculations is pointed out -including microscopic nuclear data libraries, determination of group constants, transport calculations and methods for experimental determination of reaction rates and particle spectra - by means of benchmarks using simple geometric conditions and composition. 5 tabs., 10 figs., 26 refs