DESIGN SCENARIO AND ANALYSIS FOR PRELIMINARY SPECIFICATION OF STEAM GENERATOR IN THE PELUIT-40

The helical steam generator is connected to an HTGR-type nuclear reactor called PeLUIt-40 for production. Steam used generate electricity and hydrogen. A once-through tube bundle was employed because of its ability endure mechanical stress due thermal expansion, high resistance flow-induced vibrations, better performance compared a straight one. To produce the targeted steam, design analysis needs be conducted. quick evaluation method predict preliminary specifications required Simple thermodynamic calculations combined with empirical heat transfer coefficients covering convective boiling processes at constant pressure were carry out analysis. Two scenarios conducted evaluate choice based on previous RDE-10.