Reactor vessel cladding separate effects studies
Conference
·
OSTI ID:6404079
The existence of a layer of tough weld overlay cladding on the interior of a light-water reactor pressure vessel could mitigate damage caused during certain overcooling transients. The potential benefit of the cladding is that it could keep a short surface flaw, which would otherwise become long, from growing either by impeding crack initiation or by arresting a running crack. Two aspects critical to cladding behavior will be reported: irradiation effects on cladding toughness and the response of mechanically loaded, flawed structures in the presence of cladding. 15 refs., 24 figs., 6 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6404079
- Report Number(s):
- CONF-8510173-6; ON: TI86002199
- Resource Relation:
- Conference: 13. water reactor safety research information meeting, Gaithersburg, MD, USA, 22 Oct 1985
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
PRESSURE VESSELS
REACTOR MATERIALS
CLADDING
CRACK PROPAGATION
PWR TYPE REACTORS
PHYSICAL RADIATION EFFECTS
TENSILE PROPERTIES
STAINLESS STEEL-308
STAINLESS STEEL-309
STEEL-ASTM-A533-B
DUCTILE-BRITTLE TRANSITIONS
SUBMERGED ARC WELDING
THERMAL STRESSES
TRANSIENTS
ALLOYS
ARC WELDING
CARBON STEELS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION RESISTANT ALLOYS
DEPOSITION
FABRICATION
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
JOINING
MATERIALS
MECHANICAL PROPERTIES
NICKEL ALLOYS
RADIATION EFFECTS
REACTORS
STAINLESS STEELS
STEELS
STRESSES
SURFACE COATING
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDING
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360106 - Metals & Alloys- Radiation Effects
36 MATERIALS SCIENCE
BWR TYPE REACTORS
PRESSURE VESSELS
REACTOR MATERIALS
CLADDING
CRACK PROPAGATION
PWR TYPE REACTORS
PHYSICAL RADIATION EFFECTS
TENSILE PROPERTIES
STAINLESS STEEL-308
STAINLESS STEEL-309
STEEL-ASTM-A533-B
DUCTILE-BRITTLE TRANSITIONS
SUBMERGED ARC WELDING
THERMAL STRESSES
TRANSIENTS
ALLOYS
ARC WELDING
CARBON STEELS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION RESISTANT ALLOYS
DEPOSITION
FABRICATION
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
JOINING
MATERIALS
MECHANICAL PROPERTIES
NICKEL ALLOYS
RADIATION EFFECTS
REACTORS
STAINLESS STEELS
STEELS
STRESSES
SURFACE COATING
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDING
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360106 - Metals & Alloys- Radiation Effects