Fracture Mechanism Maps in Unirradiated and Irradiated Metals

Journal Article · Mon Jan 01 00:00:00 EST 2007 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2006.12.017· OSTI ID:1001270

Li, Meimei ^[1]; Zinkle, Steven J ^[1]

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1. ORNL

This paper presents a methodology for computing a fracture mechanism map in two-dimensional space of tensile stress and temperature using physically-based constitutive equations. Four principal fracture mechanisms were considered: cleavage fracture, low temperature ductile fracture, transgranular creep fracture, and intergranular creep fracture. The methodology was applied to calculate fracture mechanism maps for several selected reactor materials, CuCrZr, 316 type stainless steel, F82H ferritic-martensitic steel, V4Cr4Ti and Mo. The calculated fracture maps are in good agreement with empirical maps obtained from experimental observations. The fracture mechanism maps of unirradiated metals and alloys were modified to include radiation hardening effects on cleavage fracture and high temperature helium embrittlement. Future refinement of fracture mechanism maps is discussed.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1001270
• Journal Information: Journal of Nuclear Materials, Vol. 367, Issue 2-3; ISSN 0022-3115
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
ALLOYS
CLEAVAGE
CREEP
FRACTURES
HELIUM EMBRITTLEMENT
RADIATION HARDENING
REACTOR MATERIALS
STAINLESS STEELS