Interaction of defects with dislocations in reactor pressure vessel steels
Book
·
OSTI ID:140000
- Ecole Polytechnique Federale de Lausanne (Switzerland). Dept. of Physique
- Paul Scherrer Inst., Villigen (Switzerland)
The radiation embrittlement of reactor pressure vessel steels may be partially explained by the creation of irradiation-induced defects that interact with the moving dislocations during plastic deformation. This research studies the nature of the interaction mechanisms and the microstructural properties and the mobility of the dislocations. Internal friction measurements, torsional plastic deformation tests, and transmission electron microscopy observations have been performed in ferritic steels used for reactor pressure vessels, more precisely the JRQ (Japanese Reference Quality) steel (International Atomic Energy Agency [IAEA] correlation monitoring material). The influence of neutron irradiation and of annealing treatments is discussed.
- OSTI ID:
- 140000
- Report Number(s):
- CONF-9009544--; ISBN 0-8031-1478-8
- Country of Publication:
- United States
- Language:
- English
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