The development of an MCNP tally-based burnup code

Author: Bakkari Bilal El   Bardouni Tarek El   Merroun Ossama   Younoussi Chafik El   Boulaich Yassine   Chakir El Mahjoub  

Publisher: Inderscience Publishers

ISSN: 1741-6361

Source: International Journal of Nuclear Energy Science and Technology, Vol.4, Iss.3, 2009-07, pp. : 179-195

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Abstract