Preprint Article Version 1 Preserved in Portico This version is not peer-reviewed

Analysis of a Two-Phase Flow Based First Wall Cooling System for Water-Cooled Fusion Reactor Blankets

Version 1 : Received: 17 December 2023 / Approved: 17 December 2023 / Online: 18 December 2023 (05:53:46 CET)

How to cite: Garg, V.; Carraretto, I.M.; Colombo, L.P.M. Analysis of a Two-Phase Flow Based First Wall Cooling System for Water-Cooled Fusion Reactor Blankets. Preprints 2023, 2023121245. https://doi.org/10.20944/preprints202312.1245.v1 Garg, V.; Carraretto, I.M.; Colombo, L.P.M. Analysis of a Two-Phase Flow Based First Wall Cooling System for Water-Cooled Fusion Reactor Blankets. Preprints 2023, 2023121245. https://doi.org/10.20944/preprints202312.1245.v1

Abstract

In a Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB), the heat generated by the plasma thermal radiation and nuclear reactions is removed mainly by two components; namely, the First Wall (FW) and the Breeding Zone (BZ). The FW faces the neutrons and charged particles fluxes generated by the fusion reactions and the thermal radiation coming from the plasma. The present work takes into account the FW cooling system inspired by the WCLL BB 2018 design of DEMO 2017 baseline. Unlike the baseline where a Pressurized-Water Reactor (PWR) setup is used for the coolant, various setup between the Boiling Water Reactor (BWR) and the High-Pressure (HP) BWR are studied in the present work operating in the Two-Phase Flow (TPF) regime. The 3D model of the FW in the WCLL BB 2018 design is simplified into a 1D model and a steady state analysis is carried out to optimize the mass flow rate of the water and the number of parallel channels at the BB cells at different poloidal locations of the reactor, which helps not only in reducing the used coolant but also in improving the Tritium Breeding Ratio (TBR). The present work takes into account forced convection in the liquid only region, the subcooled boiling region, and the saturated boiling region using suitable empirical or semi-empirical models from the literature. The results are validated against the existing results in the literature. In the end, related conclusions are made regarding the pros and cons of the studied operating conditions.

Keywords

Water-cooled Lithium-Lead; breeding blanket; first wall; pressurized water reactor; boiling water reactor; steady state; poloidal locations; Tritium Breeding Ratio; subcooled boiling; saturated boiling

Subject

Engineering, Energy and Fuel Technology

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