Effects of irradiation temperature on Charpy and tensile properties of high-copper, low upper-shelf, submerged-arc welds

Conference · Thu Dec 31 00:00:00 EST 1992

OSTI ID:10178510

Nanstad, R K; Berggren, R G

This paper presents 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 of the different welds. Analyses revealed dependence of yield and ultimate strength on irradiation temperature {minus}0.8 MPA/{degrees}C, respectively. Similarly, the Charpy impact energy changes due to irradiation temperature were {minus}0.5{degrees}C/{degrees}C for transition shift and {minus}0.05 J/{degrees}C for upper-shelf energy decrease. After adjustment to an irradiation temperature of 288{degrees}C and normalization to a fluence of 8 {times} 10{sup 18} neutrons/cm{sup 2} percentage increases in yield strength due to irradiation ranged from about 21 to 35% while those for ultimate strength ranged from about 13 to 20%. The Charpy transition temperature shifts ranged from 59 to 123{degrees}C while the postirradiation upper-shelf energies ranged from 58 to 79 J.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States); Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 10178510
• Report Number(s): CONF-920673-23; ON: DE93017858
• Resource Relation: Conference: 16. annual symposium of American Society of Testing and Materials (ASTM) on effects of radiation on materials,Denver, CO (United States),21-25 Jun 1992; Other Information: PBD: [1992]
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
WELDED JOINTS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
FAST NEUTRONS
SUBMERGED ARC WELDING
COPPER ADDITIONS
PWR TYPE REACTORS
STEELS
TENSILE PROPERTIES
CHARPY TEST
TRANSITION TEMPERATURE
BRITTLE-DUCTILE TRANSITIONS
360106
210200
360103
RADIATION EFFECTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MECHANICAL PROPERTIES