Abstract
Irradiated AISI 304 stainless steel extracted from the
Chooz A center filler assembly has been the subject of a
number of studies. Previously the results of slow strain
rate tensile and constant load autoclave tests of 30 dpa
material have been reported. They showed an influence of
temperature, strain rate and environment on the fracture
behavior of the material. The irradiated microstructure
and deformation microstructures of those materials
following testing have now been examined by TEM. The
findings suggest that substantial channel deformation was
associated with the purely ductile fracture following
SSRT testing in argon, while the intergranular fractures
following SSRT in simulated PWR environment and constant
load testing in both simulated PWR and argon environments
were associated with very localized deformation primarily
exhibiting alpha martensite. This possibility is
discussed in the light of literature.
Original language | English |
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Title of host publication | 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors |
Editors | Jeremy T. Busby, Gabriel Ilevbare, Peter L. Andresen |
Publisher | Wiley |
Pages | 1352-1366 |
ISBN (Electronic) | 978-1-1184-5683-5 |
ISBN (Print) | 978-1-1181-3241-8 |
DOIs | |
Publication status | Published - 2011 |
MoE publication type | A4 Article in a conference publication |
Event | 15th international Conference on Environmental Degradation of Materials in Nuclear power Systems - Water reactors - Colorado Springs, CO, United States Duration: 7 Aug 2011 → 11 Aug 2011 |
Conference
Conference | 15th international Conference on Environmental Degradation of Materials in Nuclear power Systems - Water reactors |
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Country/Territory | United States |
City | Colorado Springs, CO |
Period | 7/08/11 → 11/08/11 |
Keywords
- irradiated
- stainless steel
- TEM