|
Volumn 1, Issue , 2008, Pages 814-821
|
Implementation of multi-group cross-section methodology in BGCore MC-depletion code
|
Author keywords
[No Author keywords available]
|
Indexed keywords
CODES (SYMBOLS);
COMPUTER SOFTWARE;
EIGENVALUES AND EIGENFUNCTIONS;
FORECASTING;
FUELS;
ISOTOPES;
OXIDE MINERALS;
URANIUM DIOXIDE;
BURNUP CALCULATION;
COMPUTATION TIME;
FUEL COMPOSITIONS;
MONTE CARLO PARTICLES;
NUCLEAR REACTOR SYSTEMS;
NUCLIDE DENSITIES;
POWER PREDICTIONS;
PREDICTION CAPABILITY;
LIGHT WATER REACTORS;
|
EID: 79953873861
PISSN: None
EISSN: None
Source Type: Conference Proceeding
DOI: None Document Type: Conference Paper |
Times cited : (35)
|
References (9)
|