Experimental investigation of multicycle irradiation and annealing effects on notch ductility of a 533-b weld deposits
Conference
·
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
OSTI ID:6312866
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-
- Conference Information:
- Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
- Country of Publication:
- United States
- Language:
- English
Similar Records
Exploratory investigations of cyclic irradiation and annealing effects on notch ductility of A533-B weld deposits
Exploratory assessment of postirradiation heat-treatment variables in notch-ductility recovery of A5333-B steel
Experimental tests of irradiation-anneal-reirradiation effects on mechanical properties of RPV plate and weld materials
Journal Article
·
Sun Dec 31 23:00:00 EST 1978
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
·
OSTI ID:5711227
Exploratory assessment of postirradiation heat-treatment variables in notch-ductility recovery of A5333-B steel
Technical Report
·
Thu Mar 31 23:00:00 EST 1983
·
OSTI ID:6312901
Experimental tests of irradiation-anneal-reirradiation effects on mechanical properties of RPV plate and weld materials
Conference
·
Fri Oct 01 00:00:00 EDT 1999
·
OSTI ID:679498
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
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
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