PCA Benchmark Analysis with ADVANTG3.0.1. and MCNP6.1.1b Codes

The Pool Critical Assembly Pressure Vessel (PCA) benchmark is a well known in the reactor shielding community which described Shielding Integral Benchmark Archive and Database (SINBAD). It based on experiments performed at PCA facility Oak Ridge National Laboratory (ORNL) it can be used for qualification of pressure vessel fluence calculational methodology. measured quantities to compared against calculated values are equivalent fission fluxes several experimental access tubes (A1 A8) front, behind, inside pressure-vessel wall simulator. This particularly suitable test capabilities methodology cross-section libraries predict invessel flux gradients because only few approximations necessary overall analysis. was analyzed using modern hybrid stochastic-deterministic with ADVANTG3.0.1 MCNP6.1.1b codes. an automated tool generating variance reduction (VR) parameters Monte Carlo (MC) calculations MCNP5v1.60 code (and higher versions). multigroup, discrete ordinates solver Denovo, approximating forward-adjoint transport construct VR final MC simulation. form weight windows source biasing cards directly unmodified MCNP input. underlining CADIS Denovo initially developed local results, such as point detector or limited region detector. FW-CADIS extension results globally over mesh tallies multiple point/region detectors. Both concept neutron importance function, solution adjoint Boltzmann equation. highenergy threshold reactions from international dosimetry IRDF-2002 IRDFF-2014, distributed by IAEA Nuclear Data Section. obtained show good agreement referenced measurements. Visualization deterministic 3D done VisIt Lawrence Livermore (LLNL).