Uncertainty Quantification and Management for Multi-scale Nuclear Materials Modeling

Technical Report · Wed Oct 21 00:00:00 EDT 2015

DOI:https://doi.org/10.2172/1226258· OSTI ID:1226258

McDowell, David ^[1]; Deo, Chaitanya ^[2]; Zhu, Ting ^[2]; Wang, Yan ^[2]

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1. Georgia Inst. of Technology, Atlanta, GA (United States); Nuclear Energy University Programs
2. Georgia Inst. of Technology, Atlanta, GA (United States)

Understanding and improving microstructural mechanical stability in metals and alloys is central to the development of high strength and high ductility materials for cladding and cores structures in advanced fast reactors. Design and enhancement of radiation-induced damage tolerant alloys are facilitated by better understanding the connection of various unit processes to collective responses in a multiscale model chain, including: dislocation nucleation, absorption and desorption at interfaces; vacancy production, radiation-induced segregation of Cr and Ni at defect clusters (point defect sinks) in BCC Fe-Cr ferritic/martensitic steels; investigation of interaction of interstitials and vacancies with impurities (V, Nb, Ta, Mo, W, Al, Si, P, S); time evolution of swelling (cluster growth) phenomena of irradiated materials; and energetics and kinetics of dislocation bypass of defects formed by interstitial clustering and formation of prismatic loops, informing statistical models of continuum character with regard to processes of dislocation glide, vacancy agglomeration and swelling, climb and cross slip.

• Research Organization: Georgia Inst. of Technology, Atlanta, GA (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE). Nuclear Energy University Programs (NEUP)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1226258
• Report Number(s): DOE/NEUP--12-3507; 12-3507
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
ABSORPTION
AGGLOMERATION
BCC LATTICES
DESIGN
DESORPTION
DISLOCATIONS
DUCTILITY
FAST REACTORS
FERRITIC STEELS
FUEL CANS
IMPURITIES
INTERFACES
INTERSTITIALS
IRRADIATION
KINETICS
MANAGEMENT
MARTENSITIC STEELS
MICROSTRUCTURE
NUCLEATION
PHYSICAL RADIATION EFFECTS
POINT DEFECTS
REACTOR CORES
SEGREGATION
SINKS
SLIP
STABILITY
STATISTICAL MODELS
SWELLING
TIME DEPENDENCE
VACANCIES