HEAT TRANSFER OF SUPERCRITICAL PRESSURE WATER IN FUEL ASSEMBLIES IN UNSTEADY REGIME


  • A.A. Avramenko Institute of Engineering Thermophysics of the National Academy of Sciences of Ukraine, 03057, Kiev, vul. Zhelyabova 2a, Ukraine
  • M.M. Kovetskaya Institute of Engineering Thermophysics of the National Academy of Sciences of Ukraine, 03057, Kiev, vul. Zhelyabova 2a, Ukraine
  • Yu.Yu. Kovetskaya Institute of Engineering Thermophysics of the National Academy of Sciences of Ukraine, 03057, Kiev, vul. Zhelyabova 2a, Ukraine
  • A.V. Kravchuk Institute of Engineering Thermophysics of the National Academy of Sciences of Ukraine, 03057, Kiev, vul. Zhelyabova 2a, Ukraine
  • L.V. L.V. Institute of Engineering Thermophysics of the National Academy of Sciences of Ukraine, 03057, Kiev, vul. Zhelyabova 2a, Ukraine
Keywords: nuclear reactor, heat transfer, heat emitting assembly, supercritical pressure of coolant

Abstract

Numerical simulation of heat of supercritical pressure water flow in seven kernels fuel assembly is carried out. The effect of the thermal power and the coolant flow rate on the conditions of occurrence and development of degraded heat transfer modes is analyzed.

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Published
2016-09-20
How to Cite
Avramenko, A., Kovetskaya, M., Kovetskaya, Y., Kravchuk, A., & L.V., L. (2016). HEAT TRANSFER OF SUPERCRITICAL PRESSURE WATER IN FUEL ASSEMBLIES IN UNSTEADY REGIME. Thermophysics and Thermal Power Engineering, 38(5), 59-68. https://doi.org/https://doi.org/10.31472/ihe.5.2016.06