BS ISO 19226:2017 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.Cross References:ASTM E170-16aANSI/ANS 19.10ASTM E1297-08ASTM E261-16ASTM E705-13aASTM E526-08ASTM E2006-16ASTM E704-13ASTM E264-08ASTM E263-13ASTM E181-10ASTM E523-16ASTM E844-14ASTM E910-07ISO 8529-1:2001All current amendments available at time of purchase are included with the purchase of this document.