Development of Computational Tools for Predicting Thermal- and Radiation-Induced Solute Segregation at Grain Boundaries in Fe-based Alloys

Technical Report · Fri Sep 30 04:00:00 EDT 2016

DOI:https://doi.org/10.2172/1328318· OSTI ID:1328318

Yang, Ying ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Radiation-induced segregation (RIS) has been frequently reported in structural materials such as austenitic, ferritic, and ferritic-martensitic stainless steels (SS) that have been widely used in light water reactors (LWRs). RIS has been linked to secondary degradation effects in SS including irradiation-induced stress corrosion cracking (IASCC). Earlier studies on thermal segregation in Fe-based alloys found that metalloids elements such as P, S, Si, Ge, Sn, etc., embrittle the materials when enrichment was observed at grain boundaries (GBs). RIS of Fe-Cr-Ni-based austenitic steels has been modeled in the U.S. 2015 fiscal year (FY2015), which identified the pre-enrichment due to thermal segregation can have an important role on the subsequent RIS. The goal of this work is to develop thermal segregation models for alloying elements in steels for future integration with RIS modeling.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE). Light Water Reactor Sustainability (LWRS) Research and Development Effort
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1328318
• Report Number(s): ORNL/TM--2016/460; RC0304000; NERC006
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
AUSTENITIC STEELS
COMPUTERIZED SIMULATION
CRACKING
FERRITIC STEELS
GRAIN BOUNDARIES
MARTENSITIC STEELS
MATHEMATICAL MODELS
PHYSICAL RADIATION EFFECTS
SEGREGATION
SEMIMETALS
SOLUTES
STAINLESS STEELS
STRESS CORROSION
TEMPERATURE DEPENDENCE
WATER COOLED REACTORS
WATER MODERATED REACTORS