Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding

BOTW-50w  Source:  Science Direct – Nuclear Engineering and Technology

The goal of this initiative is to demonstrate the feasibility of developing coated Mo-alloy cladding for LWR fuel cladding to enhance the accident tolerance of fuel rods in several loss of coolant accidents. The target is to demonstrate that coated Mo-alloy cladding can meet: (1) performance and reliability requirements for normal operation; (2) licensing safety requirements during power transients; and (3) significantly enhanced tolerance to severe accidents. A measurable goal is to demonstrate that the coated Mo-alloy cladding can survive in a steam environment at 1,200–1,500°C for at least 24 hours.

Read More: Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding by Bo Cheng, Young-Jin Kim, Peter Chou