Simulation of Neutronic Characteristics of the HTGR Core during the Fuel Cycle Using the Precision Calculation Code MCU-HTR
In the paper, a methodological approach to the calculation of neutronic characteristics during the burnup of a block-type HTGR core using the MCU-HTR code based on the Monte Carlo method has been presented. A description of the developed full-scale three-dimensional model of the core and the approximations used and also some calculated results have been provided to demonstrate the capability of MCU-HTR to process and visually represent the output data.
Authors
- D. A. Shkarovskiy
- P. A. Fomichenko
- S. E. Sorokin
- G. S. Filippov
- A. N. Lepekhin
- V. Yu. Galickih
- M. I. Gurevich
- A. V. Grol
Institutions
- Kurchatov Institute (RU)
Publication Details
- Journal
- Physics of Atomic Nuclei
- Published
- 2025-12-01
- DOI
- https://doi.org/10.1134/s1063778825080216
- Primary Topic
- Nuclear reactor physics and engineering
- Type
- article
- Field-Weighted Citation Impact
- 0.00