EDN: GDNTKO
Authors & Affiliations
Sergeev V.V., Kazantsev A.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Sergeev V.V. – Senior Researcher. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-51-13; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Kazantsev A.A. – Leading Researcher, Cand. Sci. (Tech.), Associate Professor.
Abstract
The work considers the design model of the heat removal of the shutdown heat of spent nuclear fuel in the “wet” spent fuel pool due to the evaporation of water and the removal of evaporating steam by ventilated air. This method of heat removal is decisive for a small thermal load of spent fuel pool up to 2 kW per 1 m2 of evaporation surface and stopping forced cooling due to the operation of the heat exchanger of FP. All fuel pools of Bilibino NPP meet this condition. The model is based on the theory of similarity of heat exchange and mass exchange processes and is implemented in analytical form. Analytical comparison was performed with a similar numerical model in the TRAC system thermohydraulic code (TRACE). It is shown that not all system thermohydraulic codes and CFD codes have a complete and closed evaporation model from the liquid-gas interface. For practical use of the developed evaporation model, an integral (LP point) model of the dynamics of thermal operation modes of fuel pool, implemented numerically, is presented. The presented model is characterized by a high speed of calculations, which classifies it as a simulator for driving thermal modes of fuel pools for a period of more than 10 years. Such key figures cannot be obtained using system (industry) codes.
Keywords
spent fuel pool (FP), spent fuel assembly (SFA), Bilibino nuclear power plant (BiNPP), thermohydraulic industry codes, heat exchanger (HE), evaporation from the water surface, atmospheric water steam condensation, similarity theory
Article Text (PDF, in Russian)
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UDC 621.311.25
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 2, 2:21
