Application of Monte Carlo Method for Burnup Dependent Full Core Neutronic Analysis of PBMR


24th International Conference on Nuclear Energy for New Europe (NENE), Portoroz, Slovenia, 14 - 17 September 2015 identifier

  • Publication Type: Conference Paper / Full Text
  • Volume:
  • City: Portoroz
  • Country: Slovenia
  • Hacettepe University Affiliated: Yes


In this study, computational results of burnup dependent full core neutronic analysis of Pebble Bed Modular Reactor (PBMR) are presented. The calculations were performed by the MCNP-4b and BURN-HUNEM codes. BURN-HUNEM code was developed and utilized to perform depletion calculations using the cross section data generated by MCNP-4b to include double heterogeneity effect on neutronic parameters. The results for equilibrium cycle core composition and burnup were presented for once-through-then-out (OTTO) and Mehrfach-DUrchLauf (MEDUL) i.e., multi-pass, fuel cycle strategies.