Properties of zirconium carbide for nuclear fuel applications

Journal of Nuclear Materials

Volumn 441, Issue 1-3, 2013, Pages 718-742

  Katoh, Yutai ^a   Vasudevamurthy, Gokul ^a,b   Nozawa, Takashi ^a,c   Snead, Lance L ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

^b VIRGINIA COMMONWEALTH UNIVERSITY   (United States)

^c JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

APPLICATION PROGRAMS; CARBIDES; CARBON; FISSION PRODUCTS; FUELS; HIGH TEMPERATURE REACTORS; MICROSTRUCTURAL EVOLUTION; NEUTRON IRRADIATION; NUCLEAR FUELS; PHASE SEPARATION;

ADVANCED HIGH-TEMPERATURE REACTORS; ELEVATED TEMPERATURE; FISSION PRODUCT RETENTION; FUEL APPLICATIONS; MICROSTRUCTURAL FEATURES; MICROSTRUCTURAL INHOMOGENEITY; UNITED STATES DEPARTMENT OF ENERGIES; ZIRCONIUM CARBIDE;

ZIRCONIUM COMPOUNDS;

EID: 84885187995     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2013.05.037     Document Type: Article

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