The International Reactor Dosimetry File: IRDF-2002

Introduction

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.

Within the scope of the project the following tasks were considered:

• Intercomparison of reactor dosimetry cross-section data and their uncertainties in various libraries including IRDF-90.2, JENDL/D-99 and RRDF-98.


• Reaction rates in a standard neutron field were compared. Select best data based on the above comparison of data for IRDF-2002.


• Evaluate and test new reaction cross sections requested by the reactor dosimetry community for extension of the database. Include evaluated decay radiation characteristics in the files.


• Comparison of experimental and calculated fission and thermal spectrum averaged cross sections.

Contents

The following data files and documentation are available:

• Damage cross sections
• Decay data
• Standard spectra
• Dosimetry cross sections, pointwise (zip-file, 17 Mb)
• Dosimetry cross sections, groupwise (640 groups, flat spectrum, 2 Mb)
• Documentation: IAEA-TECDOC-452 (ISBN 92–0–105106–9)

Last updated: 14 Dec 2007.