Abstract
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.
Original language | English |
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Place of Publication | United States |
DOIs | |
State | Published - 2016 |
Keywords
- 36 MATERIALS SCIENCE
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
- AUSTENITIC STEELS
- FERRITIC STEELS
- STAINLESS STEELS
- MARTENSITIC STEELS
- GRAIN BOUNDARIES
- SEGREGATION
- WATER MODERATED REACTORS
- CRACKING
- STRESS CORROSION
- WATER COOLED REACTORS
- SEMIMETALS
- SOLUTES
- PHYSICAL RADIATION EFFECTS
- TEMPERATURE DEPENDENCE
- COMPUTERIZED SIMULATION
- MATHEMATICAL MODELS