Effects of Radiation on Materials: 22nd Symposium
Allen TR
This STP is a compilation of technical papers which were peer reviewed used as the proceedings of the 22nd Symposium on Effects of Radiation on Materials. The symposium, held in June 2004, was sponsored by ASTM Committee E10 on Nuclear Technology and Applications. This meeting drew international participation with nearly half the papers presented by sources outside the United States.
In general, topics covered austenitic stainless steels (17 presentations), ferritic-martensitic stainless steels (11 presentations), pressure vessel steels (15 presentations), radiation damage fundamentals (12 presentations), and ceramics and other nuclear energy system materials (6 presentations).
The paper s presented included detailed information on topics such as
- aging effects
- reduced activation
- radiation-induced stress relaxation
- neutron irradiation
- irradiation dose dependence
- neutron diffraction
- pressure vessel steel
- carbide precipitation
- thermally-induced segregation
- Charpy impact
- fracture toughness
- thermal annealing
- grain boundary fracture ratio
- non-hardening embrittlement
- finite element modeling
- Vickers micro-hardness
- irradiation hardening
- radiation damage
- flexural strength
- modeling
- master curve analysis
The content of this STP provides useful information to material engineers and researchers and scientists working on Generations IV nuclear power plant designs. The papers provide a background to more fully understands the challenges facing the materials development in Generation IV systems. Order your copy today to access research results for the embrittlement of pressure vessel steels and the use of austenitic and ferritic-martensitic steels, as well as ceramics, for application in Generation IV systems.