Irradiation effects on Charpy impact and tensile properties of low upper-shelf welds, HSSI series 2 and 3
- Oak Ridge National Lab., TN (United States)
When reactor pressure vessel steels exhibit Charpy V-notch impact upper-shelf energy levels of less than 68 J (50 ft-lb), the requirements of Title 10, Code of Federal Regulations, Part 50, Appendix G, are not met. The regulations require, as an option, that a fracture mechanics analysis be performed that conservatively demonstrates adequate safety margins for continued operation. Under conditions where large prefracture crack-tip plastic zones are present, linear-elastic fracture mechanics concepts are not applicable, and the use of elastic-plastic fracture mechanics concepts has been recommended by the US Nuclear Regulatory Commission. A number of Babcock and Wilcox Company-fabricated reactor vessels in commercial pressurized water reactor plants include welds with both relatively low initial Charpy upper-shelf energies and high copper concentrations, which make them highly sensitive to neutron irradiation. As a result, the Charpy upper-shelf energies of many welds are expected to fall below 68 J (50 ft-lb) prior to reaching design life. The Heavy-Section Steel Irradiation Program conducted the Second and Third Irradiation Series to investigate the effects of irradiation on the ductile fracture toughness of seven commercially fabricated, low upper-shelf welds. This report represents analyses of the Charpy impact and tensile test data, including adjustments for irradiation temperature and fluence normalization, which make possible comparison of the irradiation sensitivity the different welds.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5289281
- Report Number(s):
- NUREG/CR-5696; ORNL/TM-11804; ON: TI91018983
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of variability in material properties and chemical composition for Midland reactor weld WF-70
Resolution of the Task A-11 reactor-vessel materials-toughness safety issue. Part I. Main report. Part II. Staff responses to public comments, and Appendices A and B. [PWR; BWR]
Related Subjects
36 MATERIALS SCIENCE
PRESSURE VESSELS
WELDED JOINTS
PHYSICAL RADIATION EFFECTS
TENSILE PROPERTIES
BWR TYPE REACTORS
CHARPY TEST
CHEMICAL COMPOSITION
PWR TYPE REACTORS
STEELS
SUBMERGED ARC WELDING
ALLOYS
ARC WELDING
CONTAINERS
DESTRUCTIVE TESTING
ENRICHED URANIUM REACTORS
FABRICATION
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINING
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
POWER REACTORS
RADIATION EFFECTS
REACTORS
TESTING
THERMAL REACTORS
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
360103 - Metals & Alloys- Mechanical Properties