Accession Number:

AD0701322

Title:

CHARPY-V NOTCH DUCTILITY CHARACTERISTICS OF NEUTRON-IRRADIATED A537-B AND A350-LF2 STEEL WELDMENTS,

Descriptive Note:

Corporate Author:

NAVAL RESEARCH LAB WASHINGTON D C

Personal Author(s):

• Gray,Robert A. , Jr

Report Date:

1970-01-16

Pagination or Media Count:

17.0

Abstract:

The nuclear service performance of thin 34-inch structural steel plate irradiated at 150F 65C to a fluence of 2.5 x 10 to the 18th power neutrons sq cm of energies greater than 1 MeV has been examined and documented with experimental results. Five 34-inch A537-B steel plates, an A350-LF2 forging, and weldments of both types of steel provided the specimen stock for the irradiation assessments. The two steels responded to low-temperature irradiation in a manner similar to a well-documented A212-B pressure vessel steel. However, both A537-B and A350-LF2 steels have an inherently greater tolerance to the effects of irradiation damage by virtue of their lower initial transition temperature. Embrittlement due to irradiation produced increases in transition temperature, but for no component of the weldments studied was the 30-ft-lb value greater than 65F 18C. The postirradiation assessments of the Charpy-V notch shelf energy values of A537-B plate in the ASTM WR orientation weak direction revealed a marked reduction in the steels fracture resistance at maximum shelf-level ductility. This is believed to be due to the high cross-rolling ratio and points up the need to maintain ratios near unity to insure WR notch ductility properties approximating those for the RW strong direction. Author

Descriptors:

• (*STEEL
• DAMAGE)
• (*WELDS
• DAMAGE)
• (*REACTOR MATERIALS
• STEEL)
• METAL PLATES
• DUCTILITY
• IMPACT TESTS
• (U)IMPACT TESTS

Subject Categories:

• Metallurgy and Metallography
• Couplers, Fasteners and Joints
• Radioactivity, Radioactive Wastes and Fission Products
• Fission Reactor Materials

Distribution Statement:

APPROVED FOR PUBLIC RELEASE