Compared with lead, lead and bismuth eutectic (LBE) has a lower melting temperature (124.5℃) and an atmospheric boiling temperature (1670℃). LBE cooled fast reactor is attracting attention due to its advantages in safety. A thermal hydraulic analysis model is developed for a Lead and Bismuth Eutectic cooled fast reactor helical coiled type steam generator， which is used for predicting thermal hydraulic parameters distribution. Based on two fluid model, the mathematical heat transfer model includes six regions: single water and vapor, subcooled boiling, saturated boiling, transition boiling and film boiling. In order to describe the heat and mass transfer between phases, the interphase model is presented. finite volume method, the control equations are solved via coupling the interaction force between liquid and gas phases. The steam generator is simplified with single tube concept and all the flow variables are evaluated at each point of the grid in which the domain is discretized. Full load condition and some postulated scenarios, such as flow rate and enthalpy step changed in secondary side, are calculated in this study. The results show that when there is a ±10% step change in the boundary parameters, steam flow oscillated and outlet temperature changes rapidly. Then, the model is both correct and reliable and can be used to evaluate LBE heat transfer and resistance relationships.


Modeling of Thermal Hydraulic Characteristics for a LBE-Cooled Fast Reactor Helical Coiled Type Steam Generator

Division / Sponsors: 
Power Division & Nuclear Engineering Division (NED)

Power Conference
Paper Proceedings: https://asmedigitalcollection.asme.org/POWER/POWER2020/volume/83747

International Conference on Nuclear Engineering
Paper Proceedings: https://asmedigitalcollection.asme.org/ICONE/ICONE2020/volume/83761

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