The propagation of uncertainties in a PWR fuel rod under steady-state irradiation is analyzed by computational means. A hypothetical steady-state scenario of the Three Mile Island 1 reactor fuel rod is modeled with the fuel performance FRAPCON, using realistic input uncertainties for the fabrication and model parameters, boundary conditions and material properties. The uncertainty and sensitivi...

Abstract It has been suggested that Cr-coated zircaloy is an excellent material for accident-tolerant fuel (ATF) cladding. found Cr coating shows multi-cracking behavior under external load due to its embrittlement. Different fabrication parameters will lead different crack resistances of the coatings, but brittle cracking characteristic common. The estimation strength and structural integrity ...

Since the nuclear accident at Fukushima Daiichi Nuclear Power Station in 2011, a considerable number of studies have been conducted to develop tolerant fuel (ATF) claddings for safety enhancement light water reactors. Among many potential ATF claddings, silicon carbide is one most promising candidates with superior features suitable applications. In spite benefits SiC cladding, there are some c...