Experimental investigation of multicycle irradiation and annealing effects on notch ductility of a 533-b weld deposits
Postirradiation heat treatment (annealing) at 399 degree C has demonstrated a capability for the relief of radiation embrittlement to reactor vessel steels. Building on an earlier investigation, this report describes a study of Charpy-V Cv) notch ductility and tensile properties behavior of two representative reactor vessel welds under cyclic 399 degree C postirradiation annealing and 288 degree C reirradiation. The study clearly demonstrates the capability of the annealing method for maintaining property changes for reactor steels, including Cv upper-shelf reduction and transition temperature elevation, below prefixed limits. In addition, the study confirms a significantly greater rate of embrittlement by heat-treated material compared with nonheat-treated material. Pronounced dissimilarities between Cv upper-shelf energy and transition temperature behavior were observed, but parallels were shown with tensile ductility and strength changes, respectively, during annealing and reirradiation.
- Research Organization:
- US Nav Res Lab, Washington, DC, USA
- OSTI ID:
- 6312866
- Report Number(s):
- CONF-800609-
- Journal Information:
- Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States); ISSN ASTTA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
CHARPY TEST
CONTAINERS
DESTRUCTIVE TESTING
DUCTILITY
EMBRITTLEMENT
HEAT TREATMENTS
HIGH TEMPERATURE
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
NOTCHES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR MATERIALS
REACTOR VESSELS
STEELS
TENSILE PROPERTIES
TESTING
WELDED JOINTS