Solution of the neutronic fast reactor benchmark with Serpent-CriMR code system

Smirnov Anton

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-2 Reactor Design, Nuclear Energy Strategy, Nuclear Transmutation

[1K15-17] Analysis Method

Wed. Mar 20, 2019 4:40 PM - 5:30 PM Room K (Common Education Bildg. 2 3F No.33)

Chair:Toshihiro Yamamoto(Kyoto Univ.)

4:55 PM - 5:10 PM

[1K16] Solution of the neutronic fast reactor benchmark with Serpent-CriMR code system

*Smirnov Anton¹, Vladislav Romanenko¹, Pavel Pugachev¹, Georgy Tikhomirov¹, Toru Obara² (1. National Research Nuclear University MEPhI, 2. Tokyo Institute of Technology)

Keywords:Group constant generation, Monte Carlo, Serpent, CriMR, Fast reactor

The Serpent Monte Carlo code was used as a tool for preparing homogenized group constants for the CriMR diffusion code for neutronic analysis of the BN fast reactor core specified in the IAEA neutronic benchmark.