EDN: DOLPLS
Authors & Affiliations
Varfolomeeva V.A., Ivanov I.E., Andrianova O.N., Bychkov S.A., Grushin N.A.
All-Russian Research Institute for Nuclear Power Plants Operation, Moscow, Russia
Varfolomeeva V.A. – Engineer 1st Category. Contacts: 25, Ferganskaya st., Moscow, Russia, 109507. Tel.: +7 (499) 796-91-26; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Ivanov I.E. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Andrianova O.N. – Chief Expert, Cand. Sci. (Techn.).
Bychkov S.A. – Chief Expert.
Grushin N.A. – Lead Engineer.
Abstract
MNT-CUDA, developed at VNIIAES JSC, is a high-precision engineering code for solving the neutron transport equation using the multi-group Monte Carlo method. Leveraging the parallel processing capabilities of graphic processing units (GPUs), MNT-CUDA significantly reduces calculation time compared to traditional CPU-based precision Monte Carlo codes. Furthermore, its detailed representation of system geometry and neutron transport processes enables higher accuracy compared to engineering codes relying on approximations. MNT-CUDA offers several ways to obtain neutron cross-sections, including MCU output files (65 groups), ACE format files (299 groups), and the CONSYST-RF program with the BNAB-RF library (299 groups), implemented as a dedicated module. Utilizing CONSYST-RF requires a priori estimation of the delta-scattering concentration to accurately account for heterogeneity effects. This paper presents a brief description of a novel methodology for determining this concentration. Alternatively, when using ACE format files generated by CONSYST-RF, heterogeneity effects are addressed using the integrated GETER module with automated delta-scattering concentration calculation and the implementation of fictional material shielding zones with automatically calculated dilution cross-sections. The paper benchmarks MNT-CUDA’s calculation results on various periodic lattices, including light water reactor (VVER type) cells and core configurations from the BFS facility. Discrepancies between group calculations using different cross-section sources are analyzed and compared with both high-fidelity calculations of precise codes and experimental data.
Keywords
MNT-CUDA program, GPU, Monte Carlo method, CONSYST-RF, MCU, resonance self-shielding, dilution cross-section, heterogeneity effects adjustment, neutron cross-sections, engineering calculations
Article Text (PDF, in Russian)
References
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UDC 621.039
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 2, 2:4
