EDN: SIGBNA
Authors & Affiliations
Gembitsky N.D.1, 2, Dolganov K.S.1
1 Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia
2 Moscow Institute of Physics and Technology (National Research University), Dolgoprudny, Russia
a
Gembitsky N.D.1, 2 – Technician, 6th Year Student. Contacts: 52, Bolshaya Tulskaya St., Moscow, Russia, 115191. Tel.: +7 (925) 534-80-55; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Dolganov K.S.1 – Head of Laboratory, Cand. Sci. (Tech.).
Abstract
An integral computer code for numerical analysis of hydrogen safety issues at the Russian tokamaks is currently under development in Nuclear Safety Institute of the Russian Academy of Sciences.
For simulation of prototypical processes at tokamaks, the physical models of the SOCRAT integral code intended for severe accidents analyses at VVER nuclear reactors are used.
The ITER is considered as a reference project for Russian tokamaks. Previous analytical research has demonstrated the possibility of explosive air-hydrogen mixtures formation in the ITER plant, as a consequence of accidents with loss of coolant (LOCA) from the cooling systems of divertor or first wall.
In order to analyze the applicability of SOCRAT thermal-hydraulic models to simulation of processes at tokamaks during this kind of accidents, the cross-verification of results is used. The publicly available calculation results obtained with MELCOR and ATHENA codes are used as reference data.
The nodalization scheme of the early ITER design is considered in the article, together with the results of its qualification in the steady-state nominal conditions of ITER operation, and the transient simulation results for the accident with a double-ended rupture of the diverter cooling circuit.
A possibility to use thermal-hydraulic models of SOCRAT as a part of integral code for hydrogen safety analysis at tokamaks is shown by a comparative analysis of simulation results with reference data.
Keywords
ITER, hydrogen, safety, tokamak, LOCA, SOCRAT, divertor, loss of coolant, accident simulation, thermal-hydraulic processess
Article Text (PDF, in Russian)
References
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UDC 621.039.68
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 2, 2:20
