Abstract
Extensive modeling and analytical work has been carried out considering the Helium-Cooled Pebble Bed Breeding Blanket (HCPB BB) Balance Of Plant (BOP) configuration of the Demonstration Power Plant (DEMO) using the Apros system code, developed by VTT Technical Research Centre of Finland Ltd. and Fortum. The integral plant model of the HCPB BB plant has been improved with respect to the blanket and steam generator models. Based on HCPB-BL2017 v1 data, reported in 2019, the blanket has been remodeled by separate Apros process components, dedicated to average inboard and outboard segments, where the power deposition scheme of the breeding units took into account the output of high-fidelity neutronic analyses. A new helical coil steam generator model has been developed for primary–secondary system coupling using CAD data provided by EUROfusion partner University of Palermo. Transient analyses have been performed with Apros on the plant configuration that utilizes a molten salt technology-based small Energy Storage System (ESS).
Highlights
The Demonstration Power Plant (DEMO) Balance Of Plant (BOP) integral thermalhydraulic models have been developed by VTT Technical Research Centre of Finland
Such activities have been facilitated by the BOP work package of the EUROfusion Consortium [1], elaborating on two blanket concepts, namely the Helium-Cooled Pebble Bed (HCPB) and the Water-Cooled Lithium–Lead (WCLL)
In the case of direct coupling, the Primary Heat Transfer System (PHTS) is directly connected to the Power Conversion System (PCS) via steam generators, whereas in the indirect layout, the primary–secondary systems’ interface is represented by an Intermediate Heat Transfer System (IHTS), equipped with an Energy Storage System (ESS) [4]
Summary
The Demonstration Power Plant (DEMO) Balance Of Plant (BOP) integral thermalhydraulic models have been developed by VTT Technical Research Centre of Finland. The direct coupling approach has two models, a pure direct version with an AUXiliary Boiler (AUXB) and another, incorporating a small ESS. The former variant served only as a benchmark case, with the ultimate goal of studying the pulsed operation regime of the power plant using a gas-fired boiler. The plasma current in the reactor chamber is driven by the discharge of the central solenoid until the plasma current reaches its opposite peak current This implies that the tokamak has to operate in pulsed mode where a pulse period (∼7200 s) is followed by a dwell phase (∼600 s) when only the decay heat is produced (∼1–3% Pnom ).
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