EDN: JNZDMM
Authors & Affiliations
Burkov I.V., Yekimov A.V., Zhirnov A.P., Ivanyuta A.N., Krivoshein I.N., Larin I.A., Rangayev N.V., Semchenkov A.A.
N.A. Dollezhal Research and Development Institute of Power Engineering, Moscow, Russia
Burkov I.V. – Lead Engineer.
Yekimov A.V. – 2nd Category Engineer.
Zhirnov A.P. – Head of Department.
Ivanyuta A.N. – Team Leader.
Krivoshein I.N. – Head of Laboratory.
Larin I.A. – Chief Specialist.
Rangayev N.V. – Engineer. Contacts: 1, building 3, pl. Academician Dollezhal, Moscow, Russia, 107140. Tel.: +7 (499) 763-03-28; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Semchenkov A.A. – Head of Department, Cand. Sci. (Tech.).
Abstract
Development of a reactor plant (RP) includes multiple stages, one of which is a simulation of steady-state, transient and emergency modes of operation, which is an important stage in justification of the RP safety. Detailed simulation of modes, consideration of feedbacks, and prediction of the reactor behavior require coupled neutronic and thermal-hydraulic (TH) calculations using integral codes (IC).
The developed integral code comprises a neutronic module based on the FACT-M code with a pre-prepared and verified two-group library of microconstants, and a thermal-hydraulic module based on the unidimensional KORSAR code. The neutronic macroconstant library has been verified using the results of calculations based on a full-scale reactor plant model performed with the help of the MCU-NR precision code. Verification was carried out on the main neutronic parameters, such as the effective multiplication factor, the weights of the control and protection system organs, reactivity coefficients, energy release fields, etc. Neutronic and TH models of the reactor core and the reactor primary circuit TH model were developed using the code tools. Calculations of transient modes of the SHELF-M RP operation, carried out using the code, allow one to judge whether feedbacks have been properly adjusted and the data exchange between the neutronic and TH models is correct. Further improvement of the code will require building an automatics module and developing control algorithms and a convenient user interface, as well as extending and updating the neutronic microconstant library for the reactor burnup and poisoning calculations.
Keywords
verification, integral code, safety justification, transients, thermal-hydraulic calculation, neutronic calculation, macroconstant library, effective multiplication factor, diffusion code, improved estimation code
Article Text (PDF, in Russian)
References
- Voropai N.I., Saneev B.G., Ivanova I.Yu., Izhbuludin A.K. Sravnitel'naya effektivnost' ispol'zovaniya atomnykh stantsiy maloy moshchnosti v lokal'nykh energosistemakh na vostoke Rossii [Comparative efficiency of using low-power nuclear power plants in local energy systems in the east of Russia]. Sb. dokl. konferentsii “Atomnye stantsii maloy moshchnosti: novoe napravlenie razvitiya energetiki” [Proc. of the Conference “Low-power nuclear power plants: a new direction for energy development”]. Moscow, Akadem-Print Publ., 2015. P. 59.
- Pimenov A.O., Kulikov D.G., Vasiliev A.P., Molokanov N.A. Atomnye stantsii maloy moshchnosti na arkticheskikh territoriyakh: voprosy ekonomicheskoy tselesoobraznosti i ekologicheskoy bezopasnosti [Low-power nuclear power plants in the Arctic territories: issues of economic feasibility and environmental safety]. Arktika: ekologiya i ekonomika – Arctic: Ecology and Economics, 2019, no. 2 (34), pp. 120–128. DOI: https://doi.org/10.25283/2223-4594-2019-2-120-128.
- Goltsov A.E., Molokanov N.A. Otsenka konkurentnosposobnosti ASMM na baze RU ShEL''F dlya izolirovannykh territoriy na primere Respubliki Sakha (Yakutiya) [Assessment of the competitiveness of nuclear power plants based on the SHELF reactor plant for isolated territories using the example of the Republic of Sakha (Yakutia)]. V sb. Nauchno-tekhnicheskiy godovoy otchet NIKIET-2019 [Scientific and Technical Annual Report NIKIET-2019]. Moscow, AO «NIKIET» Publ., 2019. Pp. 260–263.
- Alekseev A.I., Goltsov E.N., Grechko G.I., Eremeev D.V., Pepa V.N. ASMM “Uniterm” – odno iz aktual'nykh napravleniy razvitiya atomnoy energetiki [“Uniterm” is one of the current trends in the development of nuclear energy]. Sb. dokl. konferentsii “Atomnye stantsii maloy moshchnosti: novoe napravlenie razvitiya energetiki” [Proc. of the Conference “Low-power nuclear power plants: a new direction for energy development”]. Moscow, Akadem-Print Publ., 2015. P. 219.
- Goltsov E.N., Kulikov D.G., Pimenov A.O., Rapnitsky V.A. Unifitsirovannaya reaktornaya ustanovka “ShEL''F” dlya atomnykh stantsiy maloy moshchnosti [Unified Reactor Installation “SHELF” for Low-power Nuclear Power Plants]. Sb. dokl. konferentsii “Innovatsionnye proekty i tekhnologii yadernoy energetiki: MNTK NIKIET 2016” [Proc. of the Conference “Innovative Projects and Technologies of Nuclear Power: MNTK NIKIET 2016”]. Moscow, September, 27–30. Moscow, JSC AO “NIKIET” Publ., 2016. Vol. 1, pp. 582–586.
- Andreeva L.A., Gol’tsov E.N., Kaplienko A.V. et al. Actual Developmental Problems of Small Energy Installations: SNPP Based on the SHELF-M Reactor Installation. At Energy, 2021, vol. 129, issue 4, pp. 201–207. DOI: https://doi.org/10.1007/s10512-021-00734-7.
- Programma FACT-M [The FACT-M Program]. Computer Program State Registration Certificate No. 2023667090. Dated August 10, 2023.
- Programmnyy kompleks KORSAR/GP [The KORSAR/GP Software Package]. Software certification passport No. 263. Dated September 23, 2009.
- Takeda T., Komano Y. Extension of Askew's Coarse Mesh Method to Few-Group Problems for Calculating Two-Dimensional Power Distribution in Fast Breeder Reactors. Journal of Nuclear Science and Technology, 1978, 15(7), pp. 523–532. DOI: 10.1080/18811248.1978.9735544.
- Hamming R.W. Numerical Methods for Scientists and Engineers. New York, Mc Graw Hill Book Company, Inc., 1962. 400 p.
- Gubanov V.S. Obobshchennyy metod naimen'shikh kvadratov. Teoriya i primenenie v astrometrii [Generalized Least Squares Method. Theory and Application in Astrometry]. St. Petersburg, Nauka Publ., 1997. 318 p.
- Daryin N.A., Uvakin M.A., Antipov M.V., Nikolaev A.L., Makhin I.V. Razrabotka chislennogo metoda parametrizatsii makrokonstant dlya programmy KORSAR/GP na osnove polinomov [Development of a numerical method for parameterizing macroconstants for the KORSAR/GP program based on polynomials]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 1, pp. 17–30.
- Programmnyy kompleks MCU-NR s bibliotekoy konstant MDBNR61 [MCU-NR Software Package with the MDBNR61 Constant Library]. Software Qualification Certificate No. 638, dated 24.12.2024.
- Alekseev N.I., Bolshagin S.N., Gomin E.A., Gorodkov S.S., Gurevich M.I., Kalugin M.A., Kulakov A.S., Marin S.V., Novoseltsev A.P., Oleinik D.S., Pryanishnikov A.V., Sukhino-Khomenko E.A., Shkarovsky D.A., Yudkevich M.S. Status MCU-5 [MCU-5 status]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2011, no. 4, pp. 5–23.
- Bartenyev O.V. Sovremennyy Fortran. 2-e izd., ispr. [Modern Fortran. 2nd ed. rev.]. Moscow, Dialog-MIFI Publ., 1998. 397 p.
UDC 621.039.553
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 4, 4:3
