Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels

McDeavitt, Sean¹  Shao, Lin¹  Tsvetkov, Pavel¹  Wirth, Brian² 

[1] Texas A & M Univ., College Station, TX (United States);Univ. of Tennessee, Knoxv

关键词: ALLOY NUCLEAR FUELS;    FISSION PRODUCTS;    PERFORMANCE;    FAST REACTORS;    BUBBLES;    COMPUTERIZED SIMULATION;    FISSION;    GASES;    URANIUM ALLOYS;    ZIRCONIUM ALLOYS;    PLUTONIUM ALLOYS;    NUCLEATION;    FUEL CYCLE;    MOLYBDENUM ALLOYS;    MOBILITY;   

DOI  :  10.2172/1154735
RP-ID  :  DOE/NEUP--09-816
PID  :  OSTI ID: 1154735
Others  :  TRN: US1500345

美国|英语

来源: SciTech Connect

【 摘 要 】

Advanced fast reactor systems being developed under the DOE's Advanced Fuel Cycle Initiative are designed to destroy TRU isotopes generated in existing and future nuclear energy systems. Over the past 40 years, multiple experiments and demonstrations have been completed using U-Zr, U-Pu-Zr, U-Mo and other metal alloys. As a result, multiple empirical and semi-empirical relationships have been established to develop empirical performance modeling codes. Many mechanistic questions about fission as mobility, bubble coalescience, and gas release have been answered through industrial experience, research, and empirical understanding. The advent of modern computational materials science, however, opens new doors of development such that physics-based multi-scale models may be developed to enable a new generation of predictive fuel performance codes that are not limited by empiricism.