Vitaly Mogulian

Monte Carlo Variance Reduction Research & Code Developing & Nuclear Engineering

BRAND Development

Below, it is briefly described the story of my and my collaborators’ development of the neutron-gamma modules of the BRAND legacy code to altrough partially fill the gap of missed publication activity. This material does not include unsuccessful experience with developments which were not prove effective because such investigations was not completed in most of cases.

BRAND Heritage Note

The project of BRAND (BRothers ANDrosenko) Monte Carlo complex of codes has been initiated by two mathematicians of IPPE (Obninsk, USSR): P.A. and A.A. Androsenko. It is intended for Monte Carlo numerical simulation of quite a wide range of physical processes, such as neutral and charged fixed-source particle transport, thermal conduction, adjoint equation for photon transport, etc. As many other Soviet codes, it was not widely distributed in the community and always used mostly by the maintainers.

Academic Period (2007-2011)

NOT READY

Industrial Period (2011-2021)

NOT READY

References

P.A. Androsenko, V.G. Mogulian. Algorithms of the Monte Carlo method based on combination of local and double-local estimates (in Russian). In proceedings of Conference of Computational Mathematics CVM-2009, 23-25 June, Akademgorodok, Novosibirsk, Russia, 2009.
P.A. Androsenko, V.G. Mogulian. A modification of the Monte Carlo method based on combination the point and double-point estimators (in Russian – Модификация метода Монте-Карло, основанная на комбинации локальной и двойной локальной оценок). MEPhI-2010 scientific session proceedings, 2010
P.A. Androsenko, V.G. Mogulian. Efficient methods of non-analog simulation of scattering as solving of radiation transport by the Monte Carlo method (in Russian). “Neutron physics problems of nuclear power (Neutronica-2010)” seminar, 2010.
V.G. Mogulian. An approach to radiation shielding evaluations using estimators by expected scoring. 2025. doi:10.5281/zenodo.16781416.
V.G. Mogulian and T.V. Utyanskaya. Estimation of allowed spent fuel parameters values range boundaries by usage of the BRAND post-processing module on the TUK-141O instance (in Russian). Slides on the “Neutron physics problems of nuclear power (Neutronica-2016)” conference, Obninsk, Russia, 23-25 November, 2016.