科技报告详细信息
Status Report on Irradiation Capsules Designed to Evaluate FeCrAl-UO2 Interactions
Field, Kevin G.1  Howard, Richard H.1 
[1] Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
关键词: URANIUM DIOXIDE;    IRRADIATION CAPSULES;    NEUTRONS;    CHEMICAL REACTIONS;    ACCIDENT-TOLERANT NUCLEAR FUELS;    FUEL PELLETS;    FUEL-CLADDING INTERACTIONS;    TEMPERATURE RANGE 0400-1000 K;    IRON BASE ALLOYS;    CHRO;   
DOI  :  10.2172/1287032
RP-ID  :  ORNL/TM--2016/267
PID  :  OSTI ID: 1287032
Others  :  Other: AF5810000
Others  :  NEAF278
美国|英语
来源: SciTech Connect
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【 摘 要 】

This status report provides the background and current status of a series of irradiation capsules that were designed and are being built to test the interactions between candidate FeCrAl cladding for enhanced accident tolerant applications and prototypical enriched commercial UO2 fuel in a neutron radiation environment. These capsules will test the degree, if any, of fuel cladding chemical interactions (FCCI) between FeCrAl and UO2. The capsules are to be irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory to burn-ups of 10, 30, and 50 GWd/MT with a nominal target temperature at the interfaces between the pellets and clad of 350?��C.

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