Validation of deterministic and Monte Carlo codes for neutronics calculation of the IRT-type research reactor

International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016

Shchurovskaya, M.V.^1 ; Alferov, V.P.^1 ; Geraskin, N.I.^1 ; Radaev, A.I.^1

National Research Nuclear University, MEPhI (Moscow Engineering Physics Institute), 31 Kashirskoe shosse, Moscow

115409, Russia^1

关键词: Code comparisons;    Continuous energy Monte Carlo code;    Diffusion based;    High enriched uraniums;    Low-enriched uranium;    Monte Carlo codes;    Neutronics;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/781/1/012025/pdf
DOI  :  10.1088/1742-6596/781/1/012025

来源: IOP

【 摘 要 】

The results of the validation of a research reactor calculation using Monte Carlo and deterministic codes against experimental data and based on code-to-code comparison are presented. The continuous energy Monte Carlo code MCU-PTR and the nodal diffusion-based deterministic code TIGRIS were used for full 3-D calculation of the IRT MEPhI research reactor. The validation included the investigations for the reactor with existing high enriched uranium (HEU, 90 w/o) fuel and low enriched uranium (LEU, 19.7 w/o, U-9%Mo) fuel.