Experimental investigations of thermal-hydraulic processes arising during operation of the passive safety systems used i
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CLEAR POWER STATIONS
Experimental Investigations of Thermal–Hydraulic Processes Arising during Operation of the Passive Safety Systems Used in New Projects of Nuclear Power Plants Equipped with VVER Reactors A. V. Morozov, O. V. Remizov, and D. S. Kalyakin State Scientific Center of the Russian Federation–the Leipunskii Institute for Physics and Power Engineering, pl. Bondarenko 1, Obninsk, Kaluzhskaya oblast, 249033 Russia email: [email protected] Abstract—The results obtained from experimental investigations into thermalhydraulic processes that take place during operation of the passive safety systems used in newgeneration reactor plants constructed on the basis of VVER technology are presented. The experiments were carried out on the model rigs available at the Leipunskii Institute for Physics and Power Engineering. The processes through which interaction occurs between the opposite flows of saturated steam and cold water moving in the vertical steam line of the addi tional system for passively flooding the core from the secondstage hydro accumulators are studied. The spe cific features pertinent to undeveloped boiling of liquid on a single horizontal tube heated by steam and steam–gas mixture that is typical for of the condensing operating mode of a VVER reactor steam generator are investigated. Keywords: VVER, passive systems, vertical blankedoff tube, horizontal tube, condensation, boiling DOI: 10.1134/S0040601514050061
The prospects for future development of nuclear power engineering are connected to a significant extent with the strategies of combined use of VVER type thermalneutron reactors with an open nuclear fuel cycle (NFC) and BNtype fastneutron reactors with a closed NFC [1–3]. In Russia, enterprises of the Rosatom State Atomic Energy Corporation have developed the socalled standard AES2006 project of a nuclear power station (NPP) equipped with a VVER1200 reactor plant (RP). The second stage of the Novovoronezh NPP serves as the site for constructing the pilot power units in the AES2006 series. In addition, the main solu tions for safety assurance are implemented in the Kudankulam NPP project in India, the first power unit of which has already been put in operation. The main specific feature of this project is that it uses addi tional passive safety systems in combination with tra ditional active systems. The list of passive safety sys tems used in the AES2006 project with a VVER1200 reactor plant (Fig. 1) includes the additional passive core flooding system [also known as the system of 2nd stage hydro accumulators (HA2)] and the passive residual heat removal system (PHRS). The HA2 system is intended for passively supply ing boric acid solution into the reactor core in order to remove decay heat under station blackout conditions (including loss of the dieselgenerators) and leaks from the RP primary coolant circuit [4]. The addi
tional passive core flooding system consists of four groups of hydro accumulators (by two 120 m3 reser voirs in each group) with boric
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