This document provides a procedure for the evaluation of irradiation data in the region between the
reactor core and the inside surface of the containment vessel, through the pressure vessel and the
reactor cavity, between the ends of active fuel assemblies, given the neutron source in the core.
NOTE These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium
production.
The evaluation employs both neutron flux computations and measurement data from in-vessel and
cavity dosimetry, as appropriate. This document applies to pressurized water reactors (PWRs), boiling
water reactors (BWRs), and pressurized heavy water reactors (PHWRs).
This document also provides a procedure for evaluating neutron damage properties at the reactor
pressure vessel and internal components of PWRs, BWRs, and PHWRs. Damage properties are focused
on atomic displacement damage caused by direct displacements of atoms due to collisions with neutrons
and indirect damage caused by gas production, both of which are strongly dependent on the neutron
energy spectrum. Therefore, for a given neutron fluence and neutron energy spectrum, calculations of
the total accumulated number of atomic displacements are important data to be used for reactor life
management.Cross References:ASTM E170-16aANS 19.10ASTM E2006-16ASTM E1297-08ASTM E910-07ASTM E705-13aASTM E844-14ASTM E264-08ASTM E523-16ASTM E261-16ASTM E263-13ASTM E526-08ASTM E181-10ASTM E704-13ISO 8529-1:2001Incorporates the following:Corrigendum, March 2020