Abstract Zirconium-based (Zr-based) alloys have been widely used as materials for the key
components in light water reactors (LWRs), such as fuel claddings which suffer from …

Zr–Nb alloy is successfully used as structural materials in nuclear reactors. However, its
widespread application is restricted by corrosion due to complex in-pile environments. This …

The oxidation and interdiffusion behavior of Cr-and Cr/Mo-coated Zr single bond 1Nb
zirconium alloy were investigated. A single-layer Cr (8 um) and multilayer Cr (8 μm)/Mo (3 …

Modified 9Cr–1Mo (Grade 91) steel is currently considered as a candidate material for
reactor pressure vessels (RPVs) and reactor internals for the Very High Temperature …

Generation-IV reactor design concepts envisioned thus far cater to a common goal of
providing safer, longer lasting, proliferation-resistant, and economically viable nuclear …

Several methods have been developed to determine the axial creep properties of nuclear
fuel cladding tubes. However, the anisotropic creep properties of nuclear fuel cladding tubes …

The dense and uniform Cr coating is successfully applied to the Zry-4 (zircaloy-4) substrate
using multi-arc ion plating as an accident-tolerant fuel cladding. The isothermal oxidation …

Detailed investigations have been performed to examine the creep deformation behavior
and microstructural evolution of modified 9Cr-1Mo steel which is widely used in high …

For enhanced accident tolerant fuels for light water reactors application, chromium coatings
on zirconium based nuclear fuel claddings are developed and studied at CEA in the …

The impact of internal pressure fatigue treatment on the α-Zr matrix and hydride precipitates
in Zr-1Nb-0.01 Cu cladding tube has been systematically investigated using synchrotron …