Performance study and optimal design of Gd/316L neutron absorbing material for Spent Nuclear Fuel transportation and storage
Zheng-Dong Qi, Zhong Yang, Xi‐Gang Yang, Liying Wang, Chang-Yuan Li, Ye Dai
Topics & Concepts
Materials scienceUltimate tensile strengthElectromagnetic shieldingElongationNeutronCorrosionMicrostructureComposite materialYield (engineering)GadoliniumNeutron temperatureNeutron poisonMetallurgyNuclear physicsPhysicsNuclear Materials and PropertiesGraphite, nuclear technology, radiation studiesAluminum Alloys Composites Properties