EDN: SYUNXO
Authors & Affiliations
Lepehin A.N., Savinovskii A.S., Sorokin S.E., Shkokov M.G., Malkin S.A., Ushatikov A.S.
Afrikantov Experimental Design Bureau for Mechanical Engineering, Nizhny Novgorod, Russia
Lepehin A.N. – Head of Department, Cand. Sci. (Tech.).
Malkin S.A. – Lead Design Engineer, Cand. Sci. (Tech.).
Ushatikov A.S. – Design Engineer.
Sorokin S.E. – Head of Group.
Shkokov M.G. – Lead Design Engineer.
Savinovskii A.S. – Lead Design Engineer. Contacts: 15, proezd Burnakovskii, Nizhnyi Novgorod, Russia, 603074. Tel.: +7(831) 243-99-99, ext. 59-97, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Abstract
The article presents the description and verification results of algorithms for reconstitution of axial power fields and the thermahydraulic parameters calculating of the reactor for the isotope production. The algorithms are designed for axial power fields control in the core, as well as the subsequent calculation of the temperatures of cladding of the fuel elements in real time scale. The article presents the general principles of implementing algorithms, as well as their flow diagrams. The functioning of the algorithm reconstitution of axial power fields is provided by collecting information from neutron-physical monitoring sensors of the in-core monitoring system, data on the position of the operating elements of the control and protection system, as well as information on the loading of core channels with irradiated materials. The functioning of the algorithm for calculating the temperatures of fuel elements claddings and onset of nucleate boiling ratio in real time is provided by collecting information from the coolant temperature sensors from different systems. In particular, such measured parameters are used as coolant temperature at the outlet from core channels, coolant temperature at the inlet and outlet from the reactor, calculated from the parameters of the 1st and 2nd loop reactor power value.
Keywords
vortex boundary layer, turbulent eddies, shear layer, large eddies, pseudoturbulence, homogeneous combustion, stochastic dynamics, vortex model, continuous medium, thermal gas aerodynamics
Article Text (PDF, in Russian)
References
- Research reactors nuclear fuel. NZHK, Novosibirsk: Minatom. Available at: https://www.nccp.ru/press/booklets/ (accessed 13.08.2025).
- Vatulin A.V., Suprun V.B., Kulakov G.V. Development of Fuel for Research Reactors. At Energy, 2016, vol. 119, pp. 304–312. DOI: https://doi.org/10.1007/s10512-016-0064-4.
- Chusov I.A., Sheglov A.S., Kochnov O.Yu. Osobennosti konstruktsiy issledovatel'skikh reaktorov vodo-vodyanogo tipa [Design features of water-water type research reactors]. Izvestiya vuzov. Yadernaya energetika, 2016, no. 3, pp. 116–128.
- Eremeev S.A., Vasin V.M., Podshibyakin A.K. Sovershenstvovanie kontrolya minimal'nogo zapasa do krizisa teplootdachi kak kharakteristiki teplotekhnicheskoy nadezhnosti aktivnoy zony VVER [Improvement of control of DNBR as characteristics of heat engineering reliability of VVER core]. MNTK 2019 “Obespechenie bezopasnosti AES s VVER” [Proc. of the 11th ISTC “Safety assurance of NPP with VVER”]. Podolsk, 2019. Available at: https://www.gidropress.podolsk.ru/publication/materialy-konferentsiy/ (accessed 13.08.2025).
- Skorohodov D.N. Metodika rascheta polya energovydeleniya po pokazaniyam vnutrireaktornykh detektorov v reaktorakh tipa VVER. Dis. kand. tekh. nauk [Methods for calculation of power fields using of in-core detectors in VVER type reactors. Cand. tech. sci. diss.]. Moscow, 2022. 149 p.
- Kalinushkin A.E., Semchenkov Yu.M. Sovremennaya sistema kontrolya upravleniya i diagnostiki reaktorov VVER bol'shoy moshchnosti [Modern control and diagnostics system for high-power VVER reactors]. Dokladi BGUIR, 2015, no. 2(88), pp. 81–85.
- Galanin A.D. Teoriya yadernykh reaktorov na teplovykh neytronakh [Theory of nuclear reactors on thermal neutrons]. Moscow, Atomizdat Publ., 1959. 359 p.
- Veinberg A., Wigner E. The physical theory of neutron chain reactors. Chicago, University of Chicago Press, 1959. 800 p.
- Bell D., Glesston S. Nuclear Reactors Theory. New York, Van Nostrand Reinhold Company, 1970. 637 p.
- Kochurov B.P., Kvarachveli A.Yu., Michailov V.M. Annotatsiya programmy TRIFON [TRIFON code annotation]. Voprosy atomnoy nauki i tekhniki. Seriya: Phizika yadernih reactorov – Problems of Atomic Science and Technology. Series: Physics of nuclear reactors, 2000, no. 1, pp. 73–76.
- Kochurov B.P. Annotatsiya programmy SHERATON [SHERATON code annotation]. Voprosy atomnoy nauki i tekhniki. Seriya: Phizika yadernih reactorov – Problems of Atomic Science and Technology. Series: Physics of nuclear reactors, 2000, no. 1, pp. 76–79.
- Isachenko V.P. Teploperedacha. Uchebnik dlya vuzov [Heat transfer. Textbook for Universities]. Moscow, Energoizdat Publ., 1981. 416 p.
- Miheev M.A. Osnovy teploperedachi [Fundamentals of heat transfer]. Moscow, Energiya Publ., 1973. 320 p.
- Kirillov P.L. Spravochnik po teplogidravlicheskim raschetam (yadernye reaktory, teploobmenniki, parogeneratory) [Reference book of thermal and hydraulic calculations (nuclear reactors, heat exchangers, steam generators)]. Moscow, Energoizdat Publ., 1984. 296 p.
- Idelshik I.E. Spravochnik po gidravlicheskim soprotivleniyam [Hydraulic resistance reference book]. Moscow, Mashinostroenie Publ., 1975. 559 p.
- Statkov V.A., Maruhun N.Yu. Metodika i programma rascheta statsionarnogo temperaturnogo polya v sisteme mnogozonnykh tsilindricheskikh tvelov [Method and program of calculation of stationary temperature field in the system of multizone cylindrical fuel elements]. Izvestiya vuzov. Yadernaya energetika, 2013, no. 1, pp. 54–62.
- Kobzar A.I. Prikladnaya matematicheskaya statistika. Dlya inzhenerov i nauchnykh rabotnikov [Applied mathematical statistics. For engineers and scientists]. Moscow, Fizmathlit Publ., 2006. 816 p.
- Petrunin V.V., Bolshuhin M.A., Lepehin A.N., Savinovskii A.S. Development and verification of the RING 2.0 software for calculating thermal-hydraulic characteristics of fuel assemblies with annular fuel elements. At Energy, 2024, vol. 135, issue 5–6, pp. 323–327. DOI: https://doi.org/10.1007/s10512-024-01119-2.
UDC 621.039.51
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 3, 3:18