UO2-UN composites with enhanced uranium density and thermal conductivity

Journal of Nuclear Materials

Volumn 465, Issue , 2015, Pages 509-515

  Yang, Jae Ho ^a   Kim, Dong Joo ^a   Kim, Keon Sik ^a   Koo, Yang Hyun ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Accident tolerant fuel pellets; Composite; High thermal conductivity; High uranium density; Uranium nitride; Uranium oxide

Indexed keywords

ALUMINUM NITRIDE; COMPOSITE MATERIALS; HOT PRESSING; MIXTURES; PELLETIZING; POWDER METALS; URANIUM DIOXIDE; X RAY DIFFRACTION;

ACCIDENT TOLERANT FUELS; HIGH THERMAL CONDUCTIVITY; MIXED CERAMIC; PHASE ANALYSIS; POWDER MIXTURES; TEMPERATURE RANGE; URANIUM NITRIDE; URANIUM OXIDES;

THERMAL CONDUCTIVITY;

EID: 84933531891     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2015.06.039     Document Type: Article

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