Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

Capsules containing NaCl–MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed this purpose, and details on its design construction are given. Stainless that during exposure had less corrosive attack than exposed to same conditions without irradiation. Alloy showed no significant effect of This work shows a method conducting in-reactor irradiation–corrosion experiments static molten salts presents preliminary data showing neutron may decelerate corrosion alloys chloride salts. Molten reactor, Corrosion, Irradiation, High-temperature experiment.