Abstract
A Data Development Project was instigated by the International Atomic Energy Agency (IAEA) to update the library of dosimetry cross-sections “International Reactor Dosimetry File: IRDF-2002” and this was completed recently. Thermal capture cross-sections and resonance integrals were compared against the database of integral constants for neutron activation analysis in a validation exercise; this new IRDF-2002 file was also used in the analysis of several benchmark experiments performed at the Frascati Neutron Generator (FNG), ENEA, Frascati, and in the ASPIS facility, AEA Technology, Winfrith. The results exhibited good consistency and improved the “calculation/experiment” ratios. Reduction of some uncertainties in the new IRDF-2002 file is supported by the analysis. Inclusion of pointwise cross-section data is an important enhancement of the library for the Monte Carlo methods, as well as for codes using multigroup data for cases where self-shielding of the resonances is important.
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