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Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation
- Source :
- Journal of Nuclear Materials. 375:26-37
- Publication Year :
- 2008
- Publisher :
- Elsevier BV, 2008.
-
Abstract
- Ferritic–martensitic (FM) alloys are expected to play an important role as cladding or structural components in Generation IV systems operating in the temperature range 350–700 °C and to doses up to 200 dpa. Oxide dispersion strengthened (ODS) ferritic–martensitic steels have been developed to operate at higher temperatures than traditional FM steels. These steels contain nanometer-sized Y–Ti–O nanoclusters as a strengthening mechanism. Heavy ion irradiation has been used to determine the nanocluster stability over a temperature range of 500–700 °C to doses of 150 dpa. At all temperatures, the average nanocluster size decreases but the nanocluster density increases. The increased density of smaller nanoclusters under radiation should lead to strengthening of the matrix. While a reduction in size under irradiation has been reported in some other studies, many report oxide stability. The data from this study are contrasted to the available literature to highlight the differences in the reported radiation response.
- Subjects :
- Cladding (metalworking)
Nuclear and High Energy Physics
Materials science
Metallurgy
Oxide
chemistry.chemical_element
Atmospheric temperature range
Radiation
Nanoclusters
Chromium
chemistry.chemical_compound
Nuclear Energy and Engineering
chemistry
General Materials Science
Irradiation
Dispersion (chemistry)
Subjects
Details
- ISSN :
- 00223115
- Volume :
- 375
- Database :
- OpenAIRE
- Journal :
- Journal of Nuclear Materials
- Accession number :
- edsair.doi...........b23f7f86620b3ed3d9647f4275f7ddb8