EDN: GBLPQT
Authors & Affiliations
Shulga A.M., Yufereva V.A.
N.A. Dollezhal Research & Development Institute of Power Engineering, Moscow, Russia
Shulga A.M. – Engineer. Contacts: 1, bldg. 3, pl. Akademika Dollezhalya, Moscow, Russia, 107140. Tel.: +7 (961) 575-99-01; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Yufereva V.A. – Head of Group.
Abstract
Currently, preparations are underway for the physical start-up of the BREST-OD-300. The BREST-OD-300 is a Generation IV reactor with a fast neutron spectrum. The reactor facility uses lead coolant and mixed nitride uranium-plutonium fuel. A certified code, MCU-BR, with the MDBBR50 library of constants is used for the design calculations of the BREST-OD-300’s neutron and radiation characteristics. The MCU-BR code is designed to solve nonhomogeneous neutron and photon transport equations using analog and non-analog Monte Carlo methods. Monte Carlo method is used in this study for the MCU-BR calculations of the radiation characteristics (neutron flux and activation reaction rates) measured in experiments: at the IR-50 reactor facility, JANUS series at the ASPIS reactor, with a 252Cf source inside a lead sphere. Due to insufficient experimental data, special computational tests have been developed, including a test based on a BREST-OD-300 reactor model. Different methods were used in the calculations to reduce the dispersion, namely: monitoring of counts, truncation by energy. A Figure of Merit (FOM) taking into account the ratio of the calculation time and the statistical error was used as the criterion for estimating the efficiency of using non-analog methods. A method has been proposed based on this criterion for calculations to compare the efficiency of different dispersion reduction methods.
The data obtained will be used to verify and validate the MCU-BR code with the MDBBR50 constant library as applicable to the BREST-OD-300 and BR-1200 reactor facility calculations.
Keywords
BREST-OD-300, JANUS, IR-50, precision calculations, ionizing radiation calculation, calculation methodology, radiation protection, verification, mathematical simulation methods, weighing window, splitting/roulette
Article Text (PDF, in Russian)
References
- MCU-BR s bibliotekoy konstant MDBBR50 [MCU-BR with MDBBR50 constant library]. Certification passport of the software No. 405 dated 08.12.2016.
- Fishman G.S. Monte Carlo: concepts, algorithms and applications. Springer series in operations research. New York: Springer-Verlag, 1996.
- Samarsky А.А., Mihailov A.P. Matematicheskoye modelirovaniye [Mathematical modeling]. Moscow, FIZMATLIT Publ., 2002. 320 p.
- Kalugin М.А. Razvitiye pretsizionnykh i inzhenernykh metodov i programm raschota yadernykh reaktorov s ispol'zovaniyem algoritmov Monte-Karlo. Diss. dokt. tekh. nauk [Development of precision engineering methods and programs for calculating Nuclear Reactors using Monte Carlo algorithms. Diss. Dr. tech. sci.]. Мoscow, 2009. 295 p.
- Briesmeister J.F. MCNP-A general Monte-Carlo N-particle transport code, version 4В. LANL report LA-12625-М. Los Alamos,1997.
- Carter L.L. et al. Monte Carlo Development in Los Alamos. LA-5903-MS. Los Alamos, 1975.
- Estes Guy P., Cashwell Edmond D. MCNP1B Variance Error Estimator. LA-UR-23-26390. Los Alamos, 2023.
- Thomas E. Booth. A Sample Problem for Variance Reduction in MCNP. LA-10363-MS. Los Alamos, 1985.
- Adrian Barbu, Song-Chun Zhu. Monte Carlo Methods. Singapore: Springer Nature, 2020.
- Lux I., Koblinger L. Monte Carlo Particle Transport Methods: Neutron and Photon Calculations. Boca Raton, Florida: CRC Press, 1991.
- Frankel A., Iaccarino G. Efficient control variates for uncertainty quantification of radiation transport. Journal of Quantitative Spectroscopy and Radiative Transfer, 2017, vol. 189, pp. 398–406.
- Dai H., Zhang H., Rasmussen K.J.R., Wang W. Wavelet density-based adaptive importance sampling method. Structural Safety, 2015, vol. 52, pp. 161–169.
- Murata I., Shindo R., Shiozawa Sh. Importance Determination Method for Geometry Splitting with Russian Roulette in Monte Carlo Calculations of Thick and Complicated Core Shielding Structure. Journal of Nuclear Science and Technology, 1995, vol. 32, no. 10, pp. 971–980.
- Shielding Integral Benchmark Archive Database (SINBAD). NEA-1517/101. Organization for Economic Co-operation and Development – Nuclear Energy Agency (OECD-NEA), November 2019.
- International Handbook of Evaluated Criticality Safety Benchmark Experiments. NEA/NSC/DOC(95)03. Organization for Economic Co-operation and Development – Nuclear Energy Agency (OECD-NEA), September 2009.
UDC 621.039.51
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 2, 2:7
