Experimental investigation of a new method for advanced fast reactor shutdown cooling

• Published in: Thermal engineering Vol. 64; no. 7; pp. 496 - 503
• Main Authors: Pakholkov, V. V., Kandaurov, A. A., Potseluev, A. I., Rogozhkin, S. A., Sergeev, D. A., Troitskaya, Yu. I., Shepelev, S. F.
• Format: Journal Article
• Language: English
• Published: Moscow Pleiades Publishing 2017; Springer Nature B.V
• Subjects: Computer simulation; Cooling; Cooling systems; Decay rate; Displacement; Engineering; Engineering Thermodynamics; Fast nuclear reactors; Gravitation; Heat and Mass Transfer; Nuclear fuels; Nuclear Power Stations; Particle image velocimetry; Pumps; Shutdowns; Simulators; Stratification; Subassemblies; Test procedures; Velocity measurement; Water circulation; modeling; check valve; TISEY test facility; natural circulation; emergency heat removal system; advanced fast reactor; Particle Image Velocimetry
• ISSN: 0040-6015; 1555-6301
• DOI: 10.1134/S0040601517070059

We consider a new method for fast reactor shutdown cooling using a decay heat removal system (DHRS) with a check valve. In this method, a coolant from the decay heat exchanger (DHX) immersed into the reactor upper plenum is supplied to the high-pressure plenum and, then, inside the fuel subassemblies (SAs). A check valve installed at the DHX outlet opens by the force of gravity after primary pumps (PP-1) are shut down. Experimental studies of the new and alternative methods of shutdown cooling were performed at the TISEY test facility at OKBM. The velocity fields in the upper plenum of the reactor model were obtained using the optical particle image velocimetry developed at the Institute of Applied Physics (Russian Academy of Sciences). The study considers the process of development of natural circulation in the reactor and the DHRS models and the corresponding evolution of the temperature and velocity fields. A considerable influence of the valve position in the displacer of the primary pump on the natural circulation of water in the reactor through the DHX was discovered (in some modes, circulation reversal through the DHX was obtained). Alternative DHRS designs without a shell at the DHX outlet with open and closed check valve are also studied. For an open check valve, in spite of the absence of a shell, part of the flow is supplied through the DHX pipeline and then inside the SA simulators. When simulating power modes of the reactor operation, temperature stratification of the liquid was observed, which increased in the cooling mode via the DHRS. These data qualitatively agree with the results of tests at BN-600 and BN-800 reactors.