Fuel-cladding chemical interaction (FCCI) is a phenomenon that occurs at the fuel-cladding
interface during the irradiation of U-Zr and U-Pu-Zr metallic nuclear fuel and stainless steel …

Metallic alloy U-Zr nuclear fuels remain a candidate for future US fast reactors. However,
with more than 30 years of investigation into the system, U-Zr fuel remains unqualified and …

Abstract Uranium-10 wt.% zirconium (U-10 wt.% Zr) is a primary candidate for fast reactor
nuclear fuels. However, there is a lack of data characterizing the crystallographic phases …

Ternary alloys consisting primarily of uranium, plutonium, and zirconium (U-Pu-Zr) are
among the leading candidate fuel systems considered for fast spectrum nuclear reactors …

This article reports the results of the microstructural examination of the irradiated U–19Pu–
10Zr fuel. New insights gained using selective area electron diffraction analysis in a …

The development of nuclear fuel and materials requires is a continuous effort to investigate
the acute and prolonged effects of irradiation, thermal-material stress, chemical change, or …

Any material used in a nuclear reactor facility must go through an extensive review and
qualification, involving many tests and analyses. In late 2019, Alloy 617 was added to the …

Metallic uranium-10 weight percent zirconium (U-10wt.% Zr) nuclear fuels are classified as
potential fuels for fast breeder reactors as they possess a high fissile density and have …

Metallic uranium-zirconium (U-Zr) nuclear fuel is a primary candidate for future fast reactors.
The U-Zr system has been studied for decades with thousands of fuel pins being irradiated …

Uranium-free nonfertile Pu-based alloys, including Pu–40Zr and Pu-12Am–40Zr, represent
two candidate fuel alloys for Generation IV (GEN-IV) and transuranic (TRU) type burner …