Abstract
Validation and evaluation of the recently released ADVANTG code is presented in the paper. ADVANTG is a hybrid transport code, which combines a deterministic neutron transport code Denovo with MCNP, a well-known Monte Carlo (MC) transport code. ADVANTG was tested on an ICSBEP labyrinth benchmark where neutron fluxes were measured and calculated in a three-section concrete labyrinth for a 252Cf neutron source. The speed-up factors or the increases in relative efficiency of up to 1400 compared to analog MCNP simulations were achieved using the ADVANTG-generated variance reduction parameters. ADVANTG accelerated the calculations in terms of the CPU time and the calculated values were in good agreement with the experimental values. Additionally, it was shown that no bias was introduced by the ADVANTG code, as the mean values obtained by the ADVANTG accelerated calculation are within statistical uncertainties of the analog calculation. The presented work has shown that ADVANTG is a useful tool for use in solving neutron transport problems in geometries featuring labyrinth.
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