Title :
Neutronic behavior evaluation of an Accelerator Driven Subcritical Reactor based on Th-U fuel cycle using computational method
Author :
Feghhi, S.A.H. ; Gholamzadeh, Z. ; Tenreiro, C. ; Kim, Heonhwan
Author_Institution :
Dept. of Radiat. Applic., Shahid Beheshti Univ., Tehran, Iran
fDate :
Oct. 27 2013-Nov. 2 2013
Abstract :
Accelerator Driven Subcritical Reactor (ADSR), offer advantages in terms of flexibility in using exotic fuels, allowing operation with reactivity variations and in term of intrinsic safety. Neutronic parameters of a modeled ADSR has been investigated using MCNPX 2.6 computational method. According to the obtained data, a neutron flux of ~ 1014 (n/s.cm2) is suitable for minor actinide incineration. The system can efficiently burn minor actinide with a ~1017 atom/s rate and produce power in the fission region with good fission per absorption ratio of 0.863.
Keywords :
Monte Carlo methods; fission reactor fuel; fission reactor safety; neutron flux; radioactive waste processing; MCNPX 2.6 computational method; Th-U fuel cycle; accelerator driven subcritical reactor; exotic fuels; fission region; fission-per-absorption ratio; intrinsic safety; minor actinide incineration; neutron flux; neutronic behavior evaluation; neutronic parameters; reactivity variations; Assembly; Density measurement; Fuels; Incineration; Neutrons; Power system measurements; Protons;
Conference_Titel :
Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC), 2013 IEEE
Conference_Location :
Seoul
Print_ISBN :
978-1-4799-0533-1
DOI :
10.1109/NSSMIC.2013.6829493
