Development of an MCNP-tally based burnup code and validation through PWR benchmark exercises

Annals of Nuclear Energy

Volumn 36, Issue 5, 2009, Pages 626-633

  El Bakkari, B ^a   El Bardouni, T ^a   Merroun, O ^a   El Younoussi, Ch ^a   Boulaich, Y ^a   Chakir, E ^b  

^a FACULTÉ DES SCIENCES   (Morocco)

^b IBN TOFAIL UNIVERSITY   (Morocco)

Author keywords

[No Author keywords available]

Indexed keywords

BURN-UP; CASMO-4; EIGEN VALUES; FOURTH-ORDER RUNGE-KUTTA METHODS; FUEL COMPOSITIONS; INTEGRATION METHODS; MONTE CARLO CODES; MULTI GROUPS; PREDICTOR CORRECTORS; TRANSPORT CODES; TWO-DIMENSIONAL;

EIGENVALUES AND EIGENFUNCTIONS; ISOTOPES; PRESSURIZED WATER REACTORS; RUNGE KUTTA METHODS; SMALL NUCLEAR REACTORS; TRANSURANIUM ELEMENTS; URANIUM;

ACTINIDES;

EID: 64249132477     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2008.12.025     Document Type: Article

References (10)

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