Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems

On the use of the SPH method in nodal diffusion analyses of SFR cores

“…The reference core is modeled with DYN3D (Grundmann et al, 2000(Grundmann et al, , 2005 and PARCS (Downar et al, 2010) multi-group nodal diffusion codes using SPH-corrected few-group XS generated by Serpent. The current results are compared with the previous Serpent-DYN3D and Serpent-PARCS solutions obtained without applying the SPH correction (Nikitin et al, 2015). The nodal diffusion results obtained with and without SPH correction are verified against the reference full-core Serpent MC solution.…”

“…The general approach to the few-group XS generation is similar to that adopted in our previous study (Nikitin et al, 2015). Therefore only a brief description of the XS generation methodology is given.…”

“…A large 3600MWth SFR U-Pu mixed oxide (MOX) core specified by the SFR Benchmark Task Force of OECD/NEA (Blanchet et al, 2011) that the selected reference core is fully identical to that used in our previous study (Nikitin et al, 2015).…”

“…Several recent studies investigated the capability of Monte Carlo (MC) code Serpent (Leppänen et al, 2015) to produce few-group homogenized cross sections (XS) for the 3D nodal diffusion analyses of Sodium cooled Fast Reactor (SFR) cores (Fridman and Shwageraus, 2013;Rachamin et al, 2013;Nikitin et al, 2015). In these studies the few-group XS generation methodology was established and tested on various simplified 2D and more realistic 3D SFR core configurations.…”

SARCS cross section library generator: Part two: Fast and quasi transients evaluations

“…Although accurate, MCNPX requires substantial time to perform burnup calculations for a typical LWR. Several deterministic codes have implemented burnup calculations, however deficiency of thermal-hydraulic (TH) feedbacks requires external coupling with TH codes (Nikitin et al, 2015). The capabilities of PARCS in eigenvalues and critical boron level searches, as well as control rods movement modeling makes it an important tool for analyzing short-term (KINETIC) and longterm (DEPLETION) transients of light water nuclear reactor.…”