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.
Contact: Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161
The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium.
Stay tuned for further details.
The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.