FRACTURE TOUGHNESS OF 9Cr-1MoV AND THERMALLY AGED ALLOY 617 FOR ADVANCED REACTOR APPLICATIONS

Journal Article · Sun Jan 01 04:00:00 EST 2012 · TMS Letters

OSTI ID:1049189

Nanstad, Randy K ^[1]; Sokolov, Mikhail A ^[1]; Chen, Xiang ^[1]

---

1. ORNL

Nickel-base Alloy 617 is being considered as a structural material for application in the secondary heat exchanger of the New Generation Nuclear Plant, a very high temperature gas-cooled reactor. Thermal aging of Alloy 617 plate and welds is being performed with tensile, Charpy impact, and fracture toughness tests conducted at temperatures to 950 C. Results of testing for thermal aging to 5,300 h have been obtained and are presented; varying effects of thermal aging temperature and time on fracture toughness are observed. The 9Cr-1MoV (Grade 91) ferritic steel is a candidate for structural applications in the sodium fast reactor. Fracture toughness testing of unaged Grade 91 steel has been performed to evaluate specimen size effects in preparation for future testing of the material in the thermally aged condition. Results for material in the mill-annealed and heat treated conditions are presented and show that this heat of Grade 91 steel does not indicate a small specimen bias on the fracture toughness Master Curve reference temperature.

• Research Organization: Oak Ridge National Laboratory (ORNL)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1049189
• Journal Information: TMS Letters, Journal Name: TMS Letters
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
AGING
ALLOYS
BUILDING MATERIALS
FAST REACTORS
FERRITIC STEELS
FRACTURE PROPERTIES
GAS COOLED REACTORS
HEAT EXCHANGERS
NICKEL BASE ALLOYS
PLATES
SODIUM
STEELS
TESTING