Uncertainty Quantification and Management for Multi-scale Nuclear Materials Modeling

McDowell, David¹  Deo, Chaitanya¹  Zhu, Ting¹  Wang, Yan¹ 

[1] Georgia Inst. of Technology, Atlanta, GA (United States)

关键词: FERRITIC STEELS;    MARTENSITIC STEELS;    VACANCIES;    INTERSTITIALS;    DISLOCATIONS;    BCC LATTICES;    FAST REACTORS;    SWELLING;    REACTOR CORES;    DUCTILITY;    STATISTICAL MODELS;    ABSORPTION;    POINT DEFECTS;    DESORPTION;    MANAGEMENT;    AGGLOMERATION;    PHYSICAL RADIATION EFFECTS;    DESIGN;    TIME DEPENDENCE;    IMPURITIES;    INTERFACES;    IRRADIATION;    KINETICS;    MICROSTRUCTURE;    NUCLEATION;    SEGREGATION;    SINKS;    SLIP;    STABILITY;    FUEL CANS;   

DOI  :  10.2172/1226258
RP-ID  :  DOE/NEUP--12-3507
PID  :  OSTI ID: 1226258
Others  :  Other: 12-3507
Others  :  TRN: US1500875

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来源: SciTech Connect

【 摘 要 】

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.