Facility for stress corrosion cracking of irradiated specimens in supercritical water

This paper presents the capability to conduct stress corrosion cracking experiments on neutron-irradiated material in supercritical water for application to the GenIV supercritical water reactor concept. The Irradiated Materials Testing Laboratory (IMTL) is dedicated to performing stress corrosion cracking experiments of neutron-irradiated specimens in supercritical water in both content extension rate tensile mode and crack growth rate mode and to conduct analysis of the morphology and composition of the fracture surface via scanning electron microscopy with energy dispersive X-ray analysis.