Hydrogen absorbed into zirconium alloy nuclear fuel cladding as a result of the waterside
corrosion reaction can affect the properties of nuclear fuel, principally through the …

Zirconium-based alloys (Zr alloys) are key materials in the nuclear industry due to their
thermal stability, mechanical durability, and low thermal neutron cross section. However …

The role of dry storage in spent nuclear fuel management becomes more and more
important. Originally intended to serve as a temporary solution for a few decades until final …

Abstract Structure of the pellet/cladding-interaction (PCI) layer of a high-burnup nuclear fuel
with niobium-bearing cladding was investigated using modern transmission electron …

Ultrasonic additive manufacturing (UAM) was successfully applied to the zirconium material
system to create a planar geometry. Following fabrication, SS-J3 type tensile specimens of …

The delta hydrides formation in zirconium cladding under irradiation and thermal aging is
studied by the rate theory modeling. The precipitates may lead to cracking of the clad and …

A review is presented of work performed in our group over the years in the areas of radiation
damage, corrosion, hydrogen pickup, hydriding, and the mechanical behavior of zirconium …

In dry interim storage of spent nuclear fuel, thermal creep is one of the major threats to the
fuel cladding integrity due to the constant decay heat generation from the fission products …

During the transportation of spent fuel assemblies, filling gas and fission gas release
pressurize the fuel rods contained in the transportation cask. The rods are heated by their …

During the operation of a light water reactor, a fraction of the hydrogen produced by
waterside corrosion is absorbed into the nuclear fuel cladding. When the hydrogen …