A quasi-static model of a helical coiled Once-Through Steam Generator of High Temperature gas-cooled Reactor-Pebble Bed Module (HTR-PM) is developed based on the fundamental conservation of fluid mass, energy and momentum. The steam generator is handled with single tube concept and is divided into three regions as subcooled region, boiling region and superheated region. The equations are solved by Rung-Kutta method. The steady-state simulation results agree well with the design data. Furthermore, the results are compared with the results gotten from THERMIX/BLAST program, and the difference between them is small which shows the model and the methodology are reasonable.
- Nuclear Engineering Division
Simulation of a Once-Through, Helical-Coiled Steam Generator of High Temperature Gas-Cooled Reactor
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Ye, J, Zhou, Y, Chen, X, Ma, Y, Li, F, & Dong, Y. "Simulation of a Once-Through, Helical-Coiled Steam Generator of High Temperature Gas-Cooled Reactor." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 645-650. ASME. https://doi.org/10.1115/ICONE17-75775
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