International Reactor Dosimetry File

The objective of the project is 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.

The objective of the project is 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.

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Resource Characteristics


Last Resource Update : 2007


Subject
Nuclear Power | Physics

Organizational Source
NAPC - Nuclear Data Section

Data Type
Evaluated Data Library

Keywords
lifetime management assessments, neutron dosimetry reactions, spectrum-averaged cross-sections, evaluated nuclear data library, ACE dosimetry