The technology of micro heat pipe cooled reactor: A review

Capability of the RELAP5 code to simulate natural circulation behavior in test facilities

Power and efficiency optimization of open Maisotsenko-Brayton cycle and performance comparison with traditional open regenerated Brayton cycle

Thermodynamic analysis and optimization of a Stirling cycle for lunar surface nuclear power system

Prediction of subcooled flow boiling characteristics using two-fluid Eulerian CFD model

Thermodynamic analysis and optimization of a Closed Regenerative Brayton Cycle for nuclear space power systems

Assessment of RELAP5 matrix solvers for a two-phase natural circulation loop

Heat transfer processes using two-phase boiling flows are often found in the industry, due to the high-efficiency heat removal, with a minimum difference of temperature between the heated surface and fluid. Moreover, the use of computational fluid dynamics to solve safety issues related to nuclear reactors has increased rapidly, but a complete validation is still being carried out. Therefore, this study aims the assessment of different sub-models of the interfacial heat transfer coefficient which is used as a closure relation in the two-fluid multiphase model. As a manner to validate the numerical results, the set of experimental conditions of Bartolomei and Chanturiya (Therm Eng 14:123–128, 1967) were applied to an upwards flow in a circular channel, under high water saturation pressures. The interfacial sub-models were implemented into an axisymmetric simulation domain, using the Eulerian two-fluid approach. Three different saturation pressures and two uniform heat fluxes were considered in the simulation runs. Fixed mass flux and subcooled degree of 900 kg/m2 and 60 K were applied, respectively. A satisfactory agreement was achieved for the estimation of the heated wall temperature, the liquid bulk temperature and the onset of saturated boiling. Different heat transfer closure relations promoted different vapor volume fraction along the channel, indicating the importance of an adequate interfacial heat transfer correlation to predict the flow boiling phenomena.

Francisco A. Braz Filho

Papers

Thermodynamic analysis and optimization of a Closed Regenerative Brayton Cycle for nuclear space power systems

Prediction of subcooled flow boiling characteristics using two-fluid Eulerian CFD model

Assessment of RELAP5 matrix solvers for a two-phase natural circulation loop

Comparison of interfacial heat transfer correlations for high-pressure subcooled boiling flows via CFD two-fluid model

A problem in the COBRA-EN code related to the void fraction calculation