A Summary of the Low Upper Shelf Toughness Safety Margin Issue
Conference
·
OSTI ID:6005392
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
The low upper shelf toughness issue has a long history, beginning with the choice of materials for the submerged arc welding process, but also potentially involving the use of A302-B plate. Criteria for vessels containing low upper shelf materials have usually been expressed in terms of the Charpy upper shelf impact energy. Although these criteria have had several different bases, the range of limiting values for wall thicknesses approaching 229 mm (9 in.) has remained between 54 to 68J (40 to 50 ft lbs). Allowable values for vessels with thinner walls and/or only circumferential low upper shelf welds might conceivably be less. A decision on criteria to be incorporated into the ASME Code is now being made. Choices to be made concern the method for estimating the decrease in upper shelf impact energy, flaw geometry for circumferential welds, statistical significance of toughness values, the choice between JD and JM, reference pressure, safety factors and the inclusion of tearing stability calculations by means of R curve extrapolation. NRC research programs have contributed significantly to the resolution of the low upper shelf issue. These programs embrace all aspects of the issue, including material characterization, large scale testing, analysis and criteria development.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE; USNRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6005392
- Report Number(s):
- CONF-910602--25; ON: DE91010775
- Country of Publication:
- United States
- Language:
- English
Similar Records
An overview of the low-upper-shelf toughness safety margin issue
Exploratory investigations of low Charpy-V upper shelf energy steels with irradiation. Final report
Fracture toughness evaluation of a low upper-shelf weld metal from the Midland Reactor using the master curve
Technical Report
·
Wed Aug 01 00:00:00 EDT 1990
·
OSTI ID:6980001
Exploratory investigations of low Charpy-V upper shelf energy steels with irradiation. Final report
Technical Report
·
Thu Dec 29 23:00:00 EST 1977
·
OSTI ID:6561177
Fracture toughness evaluation of a low upper-shelf weld metal from the Midland Reactor using the master curve
Conference
·
Fri Feb 28 23:00:00 EST 1997
·
OSTI ID:503486
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
ARC WELDING
CHARPY TEST
CONTAINERS
DESTRUCTIVE TESTING
ENERGY TRANSFER
FABRICATION
FLUID MECHANICS
FRACTURE MECHANICS
FRACTURE PROPERTIES
HEAT TRANSFER
HYDRAULICS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINING
LOW ALLOY STEELS
MANGANESE ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MECHANICS
MOLYBDENUM ADDITIONS
MOLYBDENUM ALLOYS
PHYSICAL RADIATION EFFECTS
PLATES
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR VESSELS
REACTORS
STEEL-ASTM-A302
STEEL-MNMO
STEELS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDING
WELDING FLUXES
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
ARC WELDING
CHARPY TEST
CONTAINERS
DESTRUCTIVE TESTING
ENERGY TRANSFER
FABRICATION
FLUID MECHANICS
FRACTURE MECHANICS
FRACTURE PROPERTIES
HEAT TRANSFER
HYDRAULICS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINING
LOW ALLOY STEELS
MANGANESE ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MECHANICS
MOLYBDENUM ADDITIONS
MOLYBDENUM ALLOYS
PHYSICAL RADIATION EFFECTS
PLATES
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR VESSELS
REACTORS
STEEL-ASTM-A302
STEEL-MNMO
STEELS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDING
WELDING FLUXES