Exploratory assessment of postirradiation heat-treatment variables in notch-ductility recovery of A5333-B steel
Charpy-V specimens of an A533-B steel plate irradiated at 288/sup 0/C to 2.4 x 10/sup 19/ n/cm/sup 2/ > 1 MeV were used to determine the relative effectiveness of seven different heat treatments for notch-ductility recovery. The plate was selected for study because of its 0.20% copper content for high radiation-embrittlement sensitivity. Heat-treatment temperatures were 343/sup 0/, 399/sup 0/, 427/sup 0/ and 454/sup 0/C; heat-treatment times were 24, 168, 336, and 425 hours. The experimental results indicate that full recovery can be obtained in some pressure-vessel steels irradiated at 288/sup 0/C using a 454/sup 0/C to 168h anneal. However, the effectiveness of this treatment is shown to be highly material dependent. The results also demonstrate that heat treatments yielding full upper-shelf recovery may not produce full transition-temperature recovery.
- Research Organization:
- Materials Engineering Associates, Inc., Lanham, MD (USA)
- OSTI ID:
- 6312901
- Report Number(s):
- NUREG/CR-3229; MEA-2011; ON: DE83901754
- 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
Significance of nickel and copper content to radiation sensitivity and postirradiation heat treatment recovery of reactor vessel steels
Significance of nickel and copper content to radiation sensitivity and postirradiation heat-treatment recovery of reactor-vessel steels
Journal Article
·
Sun Dec 31 23:00:00 EST 1978
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
·
OSTI ID:5711227
Significance of nickel and copper content to radiation sensitivity and postirradiation heat treatment recovery of reactor vessel steels
Conference
·
Thu Dec 31 23:00:00 EST 1981
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
·
OSTI ID:5836190
Significance of nickel and copper content to radiation sensitivity and postirradiation heat-treatment recovery of reactor-vessel steels
Technical Report
·
Sun Oct 31 23:00:00 EST 1982
·
OSTI ID:6618279
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
CARBON STEELS
CONTAINERS
DUCTILITY
EMBRITTLEMENT
FRACTURE PROPERTIES
HEAT TREATMENTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
POWER REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STEEL-ASTM-A533-B
STEELS
TENSILE PROPERTIES
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
CARBON STEELS
CONTAINERS
DUCTILITY
EMBRITTLEMENT
FRACTURE PROPERTIES
HEAT TREATMENTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
POWER REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STEEL-ASTM-A533-B
STEELS
TENSILE PROPERTIES