The Role of Heater Thermal Response in Reactor Thermal Limits during Oscillatory Two-Phase Flows
| Autor: | A. D. Vasil’ev, N. W. Brown, M. W. Wendel, Arthur E. Ruggles |
|---|---|
| Rok vydání: | 1997 |
| Předmět: |
Materials science
010308 nuclear & particles physics Critical heat flux Thermal resistance Flow (psychology) 0211 other engineering and technologies Thermodynamics 02 engineering and technology Mechanics 01 natural sciences Physics::Fluid Dynamics Natural circulation Nuclear Energy and Engineering 0103 physical sciences Thermal Heat transfer 021108 energy Two-phase flow Nucleate boiling |
| Zdroj: | Nuclear Science and Engineering. 125:75-83 |
| ISSN: | 1943-748X 0029-5639 |
| DOI: | 10.13182/nse97-a24255 |
| Popis: | Analytical and numerical investigations of critical heat flux (CHF) and reactor thermal limits are conducted for oscillatory two-phase flows often associated with natural circulation conditions. The CHF and associated thermal limits depend on the amplitude of the flow oscillations, the period of the flow oscillations, and the thermal properties and dimensions of the heater. The value of the thermal limit can be much lower in unsteady flow situations than would be expected using time average flow conditions. The properties of the heater strongly influence the thermal limit value in unsteady flow situations, which is very important to the design of experiments to evaluate thermal limits for reactor fuel systems. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
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