Effects of neutron activation on candidate fuel cladding for SCWR design

Research groups in Canada have been actively contributing to the study of the cladding materials for the Supercritical Water Cooled Reactor. This contribution reports on the second of a set of neutron activation experiments of the alloys 304 SS, I 600 and E-Brite. Samples were exposed to neutrons at the research reactor of Saskatchewan Research Council, Saskatoon. The activated samples were analyzed for the induced activities of certain elements. From the intensities of the characteristic lines, we deduce the specific activities. This data is useful to estimate the radiation hardness of the alloys as cladding materials for high temperature reactors.