International Reactor Dosimetry and Fusion File
IRDFF v.1.05, 09 October, 2014

(Cross-section data supersede IRDF-2002 and all previous versions of IRDFF)

IAEA Coordinator: A.Trkov

IRDFF REFERENCES:
R. Capote, K.I. Zolotarev, V.G. Pronyaev, and A. Trkov
Journal of ASTM International (JAI)- Volume 9, Issue 4, April 2012, JAI104119
E.M.Zsolnay, R. Capote, H.K. Nolthenius, and A. Trkov
Technical report INDC(NDS)-0616, IAEA, Vienna, 2012.



Overview

The International Reactor Dosimetry and Fusion File (IRDFF-v1.05) is a standardized evaluated cross section library of neutron dosimetry reactions and uncertainty information that supersedes the widely used IRDF-2002 library. The new IRDFF library contains cross section data and related decay data for 79 dosimetry reactions, and absorption data for three cover materials B, Cd and Gd used for suppressing the themal neutron flux in the irradiation of some material samples. All reaction cross section data (except cover materials) include state-of-the-art covariance information.

The library can be used in a broad range of applications from lifetime management and assessments of nuclear power reactors and other neutron metrology applications such as boron neutron capture therapy, therapeutic use of medical isotopes, nuclear physics measurements, and reactor safety applications. Library evaluations are based mainly on comprehensive experimental data, therefore the reaction library also represents an ideal benchmark collection for validation and improvement of theoretical nuclear reaction modelling.





IRDFF data files (current version version 1.05, 08 October, 2014)


IRDFF data web retrieval


Plots of IRDFF cumulative reaction rate integrals in reference neutron spectra (IRDFF v1.03)


IRDFF neutron spectra (Version 1.05)

The IRDFF library includes the neutron spectra listed below. The fission spectra taken from evaluated files were converted from MF5,MF35/MT18 to MF3,MF33/MT261 representation, respectively (ENDF file convention).
Links to the spectra in 640-group and 725-group form are available from the shortcuts on the right-handside and include the dummy spectrum 9900, which simulates the thermal point. For 1/v absorbers the cross sections at 0.0253 eV are reconstructed exactly with this spectrum.

Verification




Validation

Preliminary validation of data is described in the IAEA Technical Report INDC(NDS)-0616. For additional information follow the link to the new Co-ordinated Research Project "Testing and Improving the IAEA International Dosimetry Library for Fission and Fusion (IRDFF)".

Codes