Zirconium in the Nuclear Industry: Fourteenth International Symposium
Rudling P
This STP, Zirconium in the Nuclear Industry: Fourteenth International Symposium, contains papers presented at the symposium with the same name held in June of 2004. The sponsor of the symposium was ASTM International Committee B 10 on Reactive and Refractory Metals and Alloys. In addition to the forty-one papers included in this publication, the STP also contains the most significant parts of the discussions that followed the oral presentation of each paper at the symposium.
The papers presented at the symposium covered all aspects of the fuel cycle. The papers in this publication are divided into several groupings
- basic metallurgy
- processing
- BWR corrosion
- PWR corrosion
- deformation behavior
- primary failure
- high temperature and transients
The papers reflect current material-related issues facing the nuclear industry. The papers cover the beginning of the fuel cycle from component design and manufacture through component performance under nominal service conditions and the useful service life of the component.
Purchasing this STP gives you access to critical observations and research from the nuclear industry. Examples of topics covered in this STP include:
- TEM investigations
- microstructure evolution
- corrosion
- irradiation defects
- dislocation loops
- precipitates
- growth behavior
- zirconium alloys
- synchrotron radiation
- X-ray diffraction
- LOCA
- high temperature oxidation
- residual ductility
- embrittlement
- hydriding
- pellet-cladding interaction