The International Reactor Dosimetry File: IRDF-2002 is a standardized, updated, and benchmarked evaluated cross section library of neutron dosimetry reactions with uncertainty information for use in lifetime management 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.

The following data files and computer code packages are available:

• irdf2002_damage.dat: Damage cross sections (ENDF-6 format)
• irdf2002_decay.dat: Decay data (ENDF-6 format)
• irdf2002_spectra.dat: Standard spectra (ENDF-6 format)
• irdf2002p.tgz, irdf2002p.zip: Dosimetry cross sections in pointwise ENDF-6 format (compressed)
• irdf2002g.dat: Dosimetry cross sections in groupwise ENDF-6 format
• irdf2002m.dat: Dosimetry cross sections in metrology format (ENDF-like format. See documentation for details)
• Microsoft Windows-based computer code packages by L.R. Greenwood (Pacific Northwest National Laboratory, Richland, WA 99352, USA, larry.greenwood@pnl.gov):
  • specter.zip: Radiation damage parameter calculations
  • staysl.zip: Least-squares neutron spectral adjustment

IRDF-2002 was developed under an IAEA Data Development Project (2001-2004). See the Summary Report of the Final Technical Meeting on "International Reactor Dosimetry File: IRDF-2002" (indc-nds-448.pdf). Also, see http://www-nds.iaea.org/irdf2002/ for additional information related to this project.

The previous version of the International Reactor Dosimetry File (IRDF-90 Version 2) is available here.

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Web: Thomas W. Burrows, NNDC, Brookhaven National Laboratory
Last Modified: April 20, 2005