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Abstracts and Available Papers Presented at the
2004 International RERTR Meeting

PHOTON SOURCE AND SHIELDING STUDIES RELATED TO THE SPENT FUEL STORAGE OF THE RA REACTOR

Miodrag Milošević
Centre for Nuclear Technologies and Research
Vinča Institute of Nuclear Sciences
P.O.Box 522, 11001 Belgrade, Serbia


ABSTRACT
 

The paper presents the methods developed and calculations carried out to analyse the photon source term and equivalent dose rates of the Vinča RA reactor spent fuel load inside the aluminium barrels. An analysis methodology for the radiological characteristics evolution, based on the SAS2H, MCNP-4C/ORIGEN2.1 and KENO-V.a/ORIGEN2.1 utility codes is presented along with information representing the validation of the methods and geometrical models. The sequence SAS4 with the MORSE-SGC code, and the MCNP-4C, a Monte Carlo code has been used for solving the shielding problem. Gamma dose rates estimated at 1 cm and 100 cm in radial direction from the water reflector surface of the aluminium are presented and discussed.


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Last modified on July 29, 2008 11:33 +0200