Authors & Affiliations
Belousov V.I.1, Davidenko V.D.1, Dyachkov I.I.1, Elkin N.N.1, Zborovsky V.G.1,2, Ioannisian M.V.1, Likhansky V.V.1,2, Malkov M.R.1, Khoruzhy O.V.1,2, Chernetsky M.G.1
1 National Research Centre “Kurchatov Institute”, Moscow, Russia
2 Р.N. Lebedev Physical Institute of the Russian Academy of Sciences, Moscow, Russia
Belousov V.I. – Head of Laboratory, Cand.
Sci. (Phys.-Math.). Contacts: 1, Academic Kurchatov pl., Moscow, 123182, Russia.
Tel.: +7 (499) 196-98-20; e-mail:
Davidenko V.D. – Head of the Department, Dr. Sci. (Tech.).
Dyachkov I.I. – Junior Researcher.
Ioannisian M.V. – Head of the Laboratory, Cand. Sci. (Phys.-Math.).
Malkov M.R. – Senior Researcher, Cand. Sci. (Phys.-Math.).
Chernetsky M.G. – Engineer.
Elkin N.N. – Leading Researcher, Dr. Sci. (Phys.-Math.).
Zborovsky V.G. – Leading Researcher, Dr. Sci. (Phys.-Math.).
Likhansky V.V. – Head of the Department, Dr. Sci. (Phys.-Math.).
Khoruzhy O.V. – Leading Researcher, Dr. Sci. (Phys.-Math.).
Abstract
The technique of coupled neutronic and thermohydraulic calculation for the PWR-SCP reactor (supercritical pressure) is considered. As a part of this work the linking was created and applied in the dynamic programming languages Python and Lua between the KIR [1]–[4] module for calculating neutron physics using the Monte Carlo method [5]–[6] and the TK-SCP [7] thermohydraulic module. The neutronic part was based on a precision calculation performed by the Monte Carlo method allowed to avoid the deterministic approximation methods errors in the results of calculations. The statement of the problem as well as the nature and the result of the work revealed a number of advantages of this approach to solving problems associated with thermohydraulic calculations: the performance of parallel neutronic and sequential thermohydraulic calculations doesn't affect to the overall speed of performing the coupled calculation; calculation codes are developed in parallel helped saves a time and resources; error tracking is done apart.
It should be noted that the PWR-SCP reactor has several features leading to additional difficulties arising in the simulation process. One of them is the transformation of a water coolant into a water-water mixture closed to steam in density but it's having own unique properties with a special temperature regime. The KIR-TG software package using the Monte Carlo method was developed specifically to solve problems associated with the calculation of PWR-SCP type reactors and it allows to generate data exchange between the KIR neutronic code and the TK-SCP thermohydraulic program. The uniqueness of the complex lies in the fact that the imitation of neutronic processes happens taking into account the distributed temperature of the materials. The paper provides a brief description of the methodology, programs and results of simulating the test problems.
Keywords
coupled calculations, neutronic calculation, thermohydraulic calculation, supercritical pressure, Monte Carlo method, water coolant, water-water mixture, density, software package, distributed temperatures of materials
Article Text (PDF, in Russian)
UDC 621.039.5, 550.34.013
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 1, 1:3