Data Development Project (2001-2004)
International Reactor Dosimetry File: IRDF-2002

Project Officer: Raquel Paviotti-Corcuera

Objectives

The objective of the project was to prepare and distribute a standardised, updated and benchmarked evaluated cross section library of neutron dosimetry reactions with uncertainty information (IRDF-2002) for use in lifetime management assessments of nuclear power reactors and other applications.

Data files and codes

The following data files and code packages are available:

• Damage cross sections


• Decay data


• Standard spectra


• Dosimetry cross sections in pointwise ENDF-6 format (compressed)


• Dosimetry cross sections in groupwise ENDF-6 format


• Dosimetry cross sections in metrology format


• Codes for damage parameter and spectral adjustment calculations

Activities / Meetings

Data Development Project approved by the INDC (International Nuclear Data Committee) in May 2000

Technical Meeting (TM)  held in Vienna, 27 - 29 August 2002.
Summary report of the TM: IINDC(NDS)-435

Final Technical Meeting (TM)  held in Vienna, 1 - 3 October 2003.
Summary report of the TM: INDC(NDS)-448

Documents Related to the Project

Related Links