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

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.
Authors:
 [1] ;  [1] ;  [1] ;  [2] ;  [3]
  1. Texas A & M Univ., College Station, TX (United States)
  2. Univ. of Tennessee, Knoxville, TN (United States)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
1154735
Report Number(s):
DOE/NEUP--09-816
TRN: US1500345
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Texas A & M Univ., College Station, TX (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE). Nuclear Energy University Programs (NEUP)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 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