Effects of irradiation on K/sub Ic/ curves for high-copper welds
The Fifth Irradiation Series in the Heavy-Section Steel Technology (HSST) Program is aimed at obtaining a statistically significant fracture toughness data base on two weldments with high-copper contents to determine the shift and shape of the K/sub Ic/ curve as a consequence of irradiation. The program includes irradiated Charpy V-notch impact, tensile, and drop-weight specimens in addition to compact fracture toughness specimens. Compact specimens (CS) with thicknesses of 25.4, 50.8, and 101.6 mm (1TCS, 2TCS, and 4TCS, respectively) have been irradiated. Additionally, unirradiated 6TCS and 8TCS have been tested to attain the same K/sub Ic/ measuring capacity as the irradiated specimens. The materials for this irradiation series are two weldments fabricated from special heats of weld wire with copper added to the melt. One lot of Linde 0124 flux was used for all the welds. Copper levels for the two welds are 0.23 and 0.31 wt %, while the nickel contents are 0.60 wt %. 17 refs., 16 figs., 9 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6266444
- Report Number(s):
- CONF-880613-31; ON: DE89012343
- Country of Publication:
- United States
- Language:
- English
Similar Records
Irradiation effects on fracture toughness of two high-copper submerged-arc welds, HSSI Series 5. Volume 1, Main report and Appendices A, B, C, and D
Radiation-induced temperature shift of thhe ASME K/sub Ic/ curve
Related Subjects
360101 -- Metals & Alloys-- Preparation & Fabrication
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
CARBON STEELS
CHARPY TEST
CONTAINERS
COPPER ADDITIONS
COPPER ALLOYS
DESTRUCTIVE TESTING
DUCTILITY
FRACTURE PROPERTIES
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
METALLURGICAL EFFECTS
NEUTRON FLUENCE
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR VESSELS
REACTORS
STEEL-ASTM-A533-B
STEELS
TENSILE PROPERTIES
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS