Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety justification

10/23/2015 2015 - #03 Thermal physics and thermal hydraulics

Khafizov R.R. Poplavsky V.M. Rachkov V.I. Sorokin A.P. Ashurko Yu.M. Volkov A.V. Ivanov E.F. Privezentsev V.V.

DOI: https://doi.org/10.26583/npe.2015.3.09

UDC: 621.039.526.034+621.039.546.8:536.26

ULOF accident calculations for sodium fast reactor, carried out using COREMELT code, indicate sodium boiling in the core. The process is accompanied with reactor technological parameters oscillations over a period of several tens of seconds. In this case, it is possible the implementation of sustainable decay heat removal. Since the two-phase model implemented in the code has significant influence on calculations, the model need to be experimentally verified.

Obtained experimental data on coolant flow, pressure, sodium and cladding temperatures and oscillations of parameters for sodium boiling process in a fuel subassembly mockup under natural and forced coolant circulation with sodium plenum and upper axial blanket model.

The results showed possibility of long residual heat removal by means of boiling sodium in case of sodium plenum presence in the experimental model under pins heat fluxes up to 140 kW/m2 in natural circulation conditions and up to 170 kW/m2 in forced circulation.

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fast reactor liquid metal coolant sodium boiling two-phase flow fuel subassembly mockup experimental investigation sodium void reactivity effect