BS ISO 27468:2011

Foreword
Introduction
1 Scope
2 Normative references
3 Terms and definitions
4 Methodology for criticality safety evaluations considering
  burnup of the fuel
5 Implementation of criticality safety evaluations considering
  burnup of the fuel
Annex A (informative) - Validation of the depletion codes
        against post-irradiation examination data
Annex B (informative) - Operational implementation of a burnup
        credit application
Bibliography

Specifies an evaluation methodology for nuclear criticality safety with burnup credit.

This International Standard establishes an evaluation methodology for nuclear criticality safety with burnup credit. It identifies important parameters and specifies requirements, recommendations, and precautions to be taken into account in the evaluations. It also highlights the main important technical fields to ensure that the fuel composition or history considered in calculations provides a bounding value of the effective neutron multiplication factor, k_eff.

This International Standard is applicable to transport, storage, disposal or reprocessing units implying irradiated fissile material from pressurized water reactor (PWR) fuels that initially contain uranium oxide (UOX).

Fuels irradiated in other reactors (e.g. boiling water reactors) and fuels that initially contain mixed uranium-plutonium oxide are not covered in this International Standard.

This International Standard does not specify requirements related to overall criticality safety evaluation or eventual implementation of burnup credit.