Neutronics and material attractiveness for PWR thorium systems using monte carlo techniques

Progress in Nuclear Energy

Volumn 53, Issue 6, 2011, Pages 698-707

  Trellue, Holly R ^a   Bathke, Charles G ^a   Sadasivan, Pratap ^a  

^a LOS ALAMOS NATIONAL LABORATORY   (United States)

Author keywords

Burnup; Material attractiveness; MCNP; PWR; Thorium; U 233

Indexed keywords

BURN UP; BURNUP CALCULATION; BURNUPS; DELAYED NEUTRONS; DEPLETED URANIUM; DESIGN CHANGE; ENRICHED URANIUM; FISSILE ISOTOPES; FUEL TYPES; FULL-CORE; LOW-ENRICHED URANIUM; MCNP; MONTE CARLO; MONTE CARLO CODES; MONTE CARLO TECHNIQUES; MONTEBURNS; MOX FUEL; NEUTRONICS; OXIDE FUELS; PWR; SAFETY LIMITS; SAFETY PARAMETERS; THORIUM FUELS; U-233;

FUELS; ISOTOPES; LIGHT WATER REACTORS; MONTE CARLO METHODS; PLUTONIUM; PRESSURIZED WATER REACTORS; URANIUM;

THORIUM;

EID: 79960566219     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2011.04.007     Document Type: Conference Paper

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