Inert matrix fuel neutronic, thermal-hydraulic, and transient behavior in a light water reactor : Nuclear Materials

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Bibliographic Details
Published inJournal of nuclear materials Vol. 352; no. 1-3; pp. 276 - 284
Main Authors CARMACK, W. J, TODOSOW, M, MEYER, M. K, PASAMEHMETOGLU, K. O
Format Conference Proceeding
LanguageEnglish
Published Amsterdam Elsevier 2006
Subjects
Applied sciences
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Fuels
Installations for energy generation and conversion: thermal and electrical energy
Nuclear fuels
Preparation and processing of nuclear fuels
United States
America
North America
Toxicity
Fuel cycle
Nuclear fuel
Combustion
Isotopic composition
Proliferation
Experimental study
Long term
Light water reactor
Transients
Nuclear reactor
Storage
Actinide isotopes
Fast reactor
Mixed fuel
Thermohydraulics
Feasibility
Thermal analysis
Inert matrix fuel
Comparative study
Irradiated nuclear fuel
Transuranium element
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ISSN:0022-3115
1873-4820