Dort-MCNP Discrepancies for a Simple Testing Model - Proposal of a Calculational Neutron-Gamma Benchmark.

Discrepancies found between DORT and MCNP calculation results for neutron and gamma fluxes in the surveillance and PV regions of a PWR gave the impulse for this work. As nuclear data were suspected to be the reason for these discrepancies a simple 2-zone one-dimensional cylindrical model was defined, allowing to exclude modeling uncertainties and to calculate fluxes in outer zones made of pure materials, as H2O, Fe, Cr, Ni. Compared were the neutron flux integrals over energy regions E<0.414 eV, E >0.0, 0.1, 0.5, 1.0, 3.0 MeV and the gamma flux integrals over energy regions E>0.0, 1.0, 3.0 MeV calculated with DORT-3D-synthesis/BUGLE-96 and MCNP-4B/ENDF/-B-VI at 12-15 radial points in core and outer zones. The reasons of the found discrepancies are not simply to understand. One important difference is the group approximation in DORT/BUGLE and the different treatment of resonance effects. Another is the different treatment of cross sections in the thermal region.
As the used model is supposed to be of general interest for testing codes and data , a detailed specification of the model is given as appendix. It is proposed to be used as benchmark model for coupled neutron-gamma flux calculations, including comparisons with the presented calculation results.