The fuel channels and fuel assemblies of all conventional nuclear reactors that generate
power from the fission of uranium by thermal neutrons are made from zirconium alloys …

Zirconium (Zr) hydrides threaten the reliability of fuel assembly and have repeatedly induced
failures in cladding tubes and pressure vessels. Thus, they attract a broad range of research …

In-situ irradiations with 30 keV He+ were performed on tungsten in an investigation of the
influences of irradiation temperature and fluence, pre-existing dislocation and sample …

In-situ TEM observation and molecular dynamics simulation were used to investigate the
evolution of irradiation-induced dislocation loops and their interactions with the pre-existing …

In this chapter, the effects of neutron irradiation on zirconium alloys are described. Irradiation
effects on the microstructure are first discussed, describing damage creation, point-defect …

In situ phase transformation experiments have been carried out using neutron diffraction to
monitor the texture evolution during the α→ β→ α phase transformation in a common …

Hydride precipitates that develop in Zr after absorbing hydrogen can impart significant
material hardening and embrittlement. Here, we use electrolytic hydrogen charging to …

A knowledge of the dimensional stability of reactor structural components, under irradiation
conditions, is of major importance in the design of thermal, fast, and fusion reactors. When …

Using finite element and polycrystalline plasticity modeling, we explore the influence of die
design and material behavior on the extrusion of bimetallic tubes. Three distinctly different …

The usage and long-term storage of nuclear fuel cladding motivate efforts to understand the
effect of external stress on hydride precipitation. Here, by using in situ bending device in …