A5049564042- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Fusion materials and technologies
- High Temperature Alloys and Creep
- Nuclear and radioactivity studies
- Nuclear Physics and Applications
- Advanced Materials Characterization Techniques
- Radioactive contamination and transfer
- Radioactive element chemistry and processing
- Radioactivity and Radon Measurements
- Cyclone Separators and Fluid Dynamics
- Hydrogen embrittlement and corrosion behaviors in metals
- Nuclear Engineering Thermal-Hydraulics
- Advanced materials and composites
- Particle Dynamics in Fluid Flows
- Graphite, nuclear technology, radiation studies
- Atomic and Molecular Physics
- Nuclear materials and radiation effects
- Molten salt chemistry and electrochemical processes
- Isotope Analysis in Ecology
- Advanced Frequency and Time Standards
- Titanium Alloys Microstructure and Properties
- Arctic and Antarctic ice dynamics
- Advanced Radiotherapy Techniques
- Microstructure and mechanical properties
Westinghouse Electric (Sweden)
2011-2023
Westinghouse Electric (United States)
2004-2018
General Motors (United States)
2011
Wiss Janney Elstner Associates
2010
National Research Council Canada
2010
Westinghouse Electric (Japan)
2007
ABB (Sweden)
1992
Lund University
1977-1989
Institute for Energy Technology
1987
The desire to improve the corrosion resistance of Zr cladding material for high burn-up has resulted in a general trend among fuel manufacturers develop alloys with reduced levels Sn. While commonly accepted, reason improved performance observed low-tin zirconium high-temperature aqueous environments remains unclear. High-energy synchrotron X-ray diffraction was used characterize oxides formed by autoclave exposure on Zr–Sn–Nb tin concentration ranging from 0.01 0.92 wt.%. studied included...
Advancements in transmission electron microscopy allow us to draw correlations between evolving matrix chemistry environments and the resulting dislocation structures that form. Such phenomena are essential predicting lifetime of neutron reactor components, but not well understood at fundamental level. We investigate effect nano-scale chemical evolution Zircaloy-2 on formation after emulating commercial irradiation conditions a proton beamline. Similarity type, morphology, density different...
The nuclear industry strives to reduce the fuel cycle cost, enhance flexibility and improve reliability of operation. This can be done by both increasing weight optimizing rod internal properties that affect operational margins. Further, there is focus on reducing consequences failures. To meet these demands Westinghouse has developed ADOPT (Advanced Doped Pellet Technology) UO2 containing additions chromium aluminium oxides. paper presents results from extensive investigation program which...
Dislocation structures in neutron irradiated Zircaloy-2 fuel cladding and channel material have been characterized by means of high-resolution synchrotron x-ray diffraction combined with whole peak profile analysis transmission electron microscopy (TEM). The samples available for this characterization were taken from high burnup assemblies offer insight into the evolution dislocation structure after formation loops containing a c component. Absolute density values are about 4–15 times higher...
Structural, thermodynamic and elastic properties of the hydrogen-zirconium system including all major hydrides are studied from first principles. Interstitial hydrogen atoms occupy preferentially tetrahedral sites. The calculations show that a single vacancy in α-Zr can trap up to nine atoms. Self-interstitial Zr attract lesser extent. Accumulation near self-interstitials may become nucleation site for hydrides. By temperature-dependent terms free energy based on ab initio calculations,...
Abstract Understanding the key corrosion mechanisms in a light water reactor primary environment is critical to developing and exploiting improved zirconium alloy fuel cladding. In this paper, we report recent research highlights from new collaborative programme involving 3 U.K. universities 5 partners nuclear industry. A major part of our strategy use most advanced analytical tools characterise oxide metal/oxide interface microstructure, residual stresses, as well transport properties...
Abstract Although the complete mechanisms are not yet fully understood, it is well established that secondary phase particle (SPP) size distribution and chemical composition have a crucial affects in reactor corrosion rate hydrogen uptake boiling water (BWR) cladding. To further study these effects, different selected fuel rod assemblies with standard LK3 cladding materials been irradiated KernKraftwerk Leibstadt (KKL) for three, five, six, seven, nine annual cycles were investigated using...
Gamma emission tomography is a method based on gamma-ray spectroscopy and tomographic reconstruction techniques, which can be used for rod-wise characterization of nuclear fuel assemblies without dismantling the fuel. By performing large number measurements flux intensity around assembly using well-collimated detector, internal source distribution in may reconstructed algorithms. If spectroscopic detection system used, different emitting isotopes selected analysis, enabling nondestructive...