Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels and Alloy 690 from Halden Phase-II Irradiations

Technical Report · Mon Sep 01 00:00:00 EDT 2008

DOI:https://doi.org/10.2172/1224948· OSTI ID:1224948

Chen, Y. ^[1]; Chopra, O. K. ^[1]; Soppet, W. K. ^[1]; Dietz Rago, Nancy L. ^[1]; Shack, W. J. ^[1]

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1. Argonne National Lab. (ANL), Argonne, IL (United States)

This work is an ongoing effort at Argonne National Laboratory on the mechanistic study of irradiation-assisted stress corrosion cracking (IASCC) in the core internals of light water reactors.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1224948
• Report Number(s): NUREG/CR-6965; 118693; TRN: US1500892
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CRACKS
STAINLESS STEEL-304
STAINLESS STEEL-304L
STAINLESS STEEL-316
STAINLESS STEEL-316L
INCONEL 690
STRESS CORROSION
WATER MODERATED REACTORS
REACTOR INTERNALS
IRRADIATION
WATER COOLED REACTORS
RADIATION DOSES
NEUTRONS
TEMPERATURE RANGE 0400-1000 K
DUCTILITY
RADIATION HARDENING
METALLURGICAL EFFECTS
EMBRITTLEMENT