A new strategy to simulate a random geometry in a pebble-bed core with the Monte Carlo code MCNP

Publication year: 2011
Source: Annals of Nuclear Energy, In Press, Corrected Proof, Available online 14 June 2011

Hong-Chul, Kim , Song Hyun, Kim , Jong Kyung, Kim

MCNP™ is one of the most widely used codes and is suitable for the validation of a new computer code for pebble-bed core analysis which will be developed in the future. In a pebble-bed core not only the fuel and moderator pebbles are randomly packed, but also the fuel-to-moderator pebble ratio is irregular. It is quite difficult to directly apply these features in MCNP™ simulations. A new method, that can efficiently simulate the characteristics of the pebble-bed core by using the MCNP™ code, was developed in this study. The key idea of the method is that the material composing the…

 Highlights: ► We developed a new method to model efficiently a pebble-type core with the MCNP code. ► This method is validated using some benchmark problems. ► This method can be applied to model the various configurations of pebble-bed cores. ► Greater variety of analyses for the pebble-bed core can be possible using the method.