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


TOMBAKOĞLU M., Celik C.

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

Abstract

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.