Trkov, A., Griffin, P.J., Simakov, S.P., Greenwood, L.R., Zolotarev, K.I., Capote, R., Aldama, D.L., Chechev, V., Destouches, C., Kahler, A.C., Konno, C., Koštál, M., Majerle, M., Malambu, E., Ohta, M., Pronyaev, V.G., Radulović, V., Sato, S., Schulc, M., and Šimečková, E.
High quality nuclear data is the most fundamental underpinning for all neutron metrology applications. This paper describes the release of version II of the International Reactor Dosimetry and Fusion File (IRDFF-II) that contains a consistent set of nuclear data for fission and fusion neutron metrology applications up to 60 MeV neutron energy. The library is intended to support: a) applications in research reactors; b) safety and regulatory applications in the nuclear power generation in commercial fission reactors; and c) material damage studies in support of the research and development of advanced fusion concepts. The paper describes the contents of the library, documents the thorough verification process used in its preparation, and provides an extensive set of validation data gathered from a wide range of neutron benchmark fields. The new IRDFF-II library includes 119 metrology reactions, four cover material reactions to support self-shielding corrections, five metrology metrics used by the dosimetry community, and cumulative fission products yields for seven fission products in three different neutron energy regions. In support of characterizing the measurement of the residual nuclei from the dosimetry reactions and the fission product decay modes, the present document lists the recommended decay data, particle emission energies and probabilities for 68 activation products. It also includes neutron spectral characterization data for 29 neutron benchmark fields for the validation of the library contents. Additional six reference fields were assessed (four from plutonium critical assemblies, two measured fields for thermal-neutron induced fission on 233U and 239Pu targets) but not used for validation due to systematic discrepancies in C/E reaction rate values or lack of reaction-rate experimental data. Another ten analytical functions are included that can be useful for calculating average cross sections, average energy, thermal spectrum average cross sections and resonance integrals. The IRDFF-II library and comprehensive documentation is available online at www.nds.iaea.org/IRDFF/. Evaluated cross sections can be compared with experimental data and other evaluations at www.nds.iaea.org/exfor/endf.htm. The new library is expected to become the international reference in neutron metrology for multiple applications. [ABSTRACT FROM AUTHOR]