Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices

Nuclear Engineering and Design

Volumn 240, Issue 4, 2010, Pages 918-924

  Bomboni, E ^a   Cerullo, N ^a,b   Fridman, E ^c   Lomonaco, G ^a,b   Shwageraus, E ^d  

^a UNIVERSITY OF PISA   (Italy)

^b UNIVERSITY OF GENOA   (Italy)

^c INSTITUTE OF ION BEAM PHYSICS AND MATERIALS RESEARCH   (Germany)

^d BEN GURION UNIVERSITY OF THE NEGEV   (Israel)

Author keywords

[No Author keywords available]

Indexed keywords

BRANCHING RATIO; BURN UP; BURNUP CALCULATION; CALCULATION TOOLS; COMPARATIVE ANALYSIS; COMPUTATIONAL SYSTEM; DEPLETION CALCULATION; EXECUTION TIME; INFINITE LATTICES; MICROSCOPIC CROSS SECTIONS; MONTE CARLO; MONTEBURNS; MONTEBURNS CODE; PEBBLE-BED; REFERENCE MODELS; SUPPLY PROBLEMS;

ACTINIDES; HIGH TEMPERATURE REACTORS; ISOTOPES; PLUTONIUM;

PEBBLE BED REACTORS;

EID: 76849083360     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2009.12.006     Document Type: Article

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