THE INVESTIGATION OF BURNUP CHARACTERISTICS USING THE SERPENT MONTE CARLO CODE FOR A SODIUM COOLED FAST REACTOR | Zendy

Mehmet Emin Korkmaz | Zendy; O. Ağar | Zendy

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THE INVESTIGATION OF BURNUP CHARACTERISTICS USING THE SERPENT MONTE CARLO CODE FOR A SODIUM COOLED FAST REACTOR

Author(s) -

Mehmet Emin Korkmaz,

O. Ağar

Publication year - 2014

Publication title -

nuclear engineering and technology

Language(s) - English

Resource type - Journals

SCImago Journal Rank - 0.737

H-Index - 40

eISSN - 2234-358X

pISSN - 1738-5733

DOI - 10.5516/net.07.2013.050

Subject(s) - burnup , nuclear engineering , fissile material , monte carlo method , sodium cooled fast reactor , nuclear transmutation , mox fuel , plutonium , materials science , nuclear physics , physics , mathematics , engineering , neutron , statistics

In this research, we investigated the burnup characteristics and the conversion of fertile 232Th into fissile 233U in the core of a Sodium-Cooled Fast Reactor (SFR). The SFR fuel assemblies were designed for burning 232Th fuel (fuel pin 1) and 233U fuel (fuel pin 2) and include mixed minor actinide compositions. Monte Carlo simulations were performed using Serpent Code1.1.19 to compare with CRAM (Chebyshev Rational Approximation Method) and TTA (Transmutation Trajectory Analysis) method in the burnup calculation mode. The total heating power generated in the system was assumed to be 2000 MWth. During the reactor operation period of 600 days, the effective multiplication factor (keff) was between 0.964 and 0.954 and peaking factor is 1.88867

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