Analysis of EU-DEMO WCLL Power Conversion System in Two Relevant Balance of Plant Configurations: Direct Coupling with Auxiliary Boiler and Indirect Coupling

Narcisi, Vincenzo; Ciurluini, Cristiano; Padula, Giovanni; Giannetti, Fabio

doi:10.3390/su14105779

Cited by 5 publications

(3 citation statements)

References 19 publications

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“…The divertor's role is to reduce the heat flux on the first wall and the helium ashes from the plasma's outer layer, avoiding the build-up and dilution of the plasma ion density and preventing the impurities from entering the plasma core. The DEMO divertor system, as described in [17], is composed of two independent systems, as shown in Figure 1a: the DIVertor CASsette (DIV-CAS) and the DIVertor Plasma Face Unit (DIV-PFU). Both systems are composed of two independent loops, each of them serving 8 of 16 sectors, according to the 2019 design of the Divertor PHTS.…”

Section: Eu-demo Divertor Plasma Facing Unitmentioning

confidence: 99%

“…Each divertor PFU PHTS cooling loop is operated at a pressure of 3.8 Mpa, with a total mass flow rate of 5319.3 kg/s [17] distributed over the 24 divertor cassettes. The overall PHTS pipe length in the OF region is 2599 m. The cooling water is distributed at 130 • C and is collected at 136 • C. The total PFU PHTS pressure drop is approximately 1960 kPA.…”

Section: Eu-demo Divertor Plasma Facing Unitmentioning

confidence: 99%

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Water Chemistry Impact on Activated Corrosion Products: An Assessment on Tokamak Reactors

et al. 2023

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Activated Corrosion Product (ACP) formation and deposition pose a critical safety issue for nuclear fusion reactors. The working fluid transports the ACPs towards regions accessible by worker personnel, i.e., the steam generator. The code OSCAR-Fusion has been developed by the CEA (France) to evaluate the ACP generation and transport in closed water-cooled loops for fusion application. This work preliminary assesses the impact of water chemistry on the transport, precipitation, and deposition of corrosion products for the EU-DEMO divertor Plasma Facing Unit Primary Heat Transfer System. Sensitivity analyses and uncertainty quantification are needed due to the multi-physics phenomena involved in ACP formation and transport. The OSCAR-Fusion/RAVEN code coupling developed by the Sapienza University of Rome and ENEA are used. This work presents the perturbation results of different parameters chosen for a closed water-cooled loop considering a continuous scenario of 1888 days. The aim of this work is to preliminarily assess the variation of build-up of ACPs, perturbing the alkalizing agent concentration into the coolant, and the corrosion and release rates of different materials. The assessment of ACP formation deposition and transport is fundamental for source term identification, reduction of radiation exposure assessment, maintenance plan definition, design optimization, and waste management.

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Section: Eu-demo Divertor Plasma Facing Unitmentioning

confidence: 99%

Section: Eu-demo Divertor Plasma Facing Unitmentioning

confidence: 99%

Water Chemistry Impact on Activated Corrosion Products: An Assessment on Tokamak Reactors

et al. 2023

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“…The current EU-DEMO baseline considers a fusion power of 2 GW with a target net power production of 500 MW [16]. Assuming a PCS net electric efficiency of 33.6% [17], the available power for ancillary systems (e.g., the fuel cycle, the heating and current drive systems, the toroidal field coils, and the cryoplant) is less than 200 MW. Therefore, optimization in the power consumption of these systems is desirable, also for the CPS that represents one of the most power consuming system of the fuel cycle.…”

Section: Introductionmentioning

confidence: 99%

Optimized Water Distillation Layout for Detritiation Purpose

Narcisi,

Santucci

2024

Applied Sciences

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Tritium permeation constitutes a key issue for the future EU-DEMO, especially in the Breeding Blanket (BB) where fusion energy must be delivered to the Primary Heat Transport System (PHTS) and where tritium must be bred. Currently, the mitigation strategy of the tritium permeation from BB into primary coolant is based on the adoption of anti-permeation barriers and on the operation of the Coolant Purification System (CPS). This system must ensure a tritium removal rate from the primary coolant equal to the BB permeation rate at a target tritium-specific activity inside the PHTS. In the case of the Water-Cooled Lithium Lead (WCLL) BB, water distillation was selected as the most promising technology for the primary coolant detritiation due to its intrinsic simplicity and safety. Nevertheless, power consumption was recognized as a relevant concern. For this reason, the present work aims at investigating possibilities to reduce power consumption of the water CPS implementing Heat Pump-Assisted Distillation (HPAD) concepts. To do this, a review of the HPADs developed in the chemical industry was carried out, and the best options for the water CPS were identified based on qualitative considerations. Then, a quantitatively assessment of the best solution in terms of power consumption and tritium inventory was performed with the commercial numerical tool Aspen Plus. Finally, the Mechanical Vapor Recompression (MVR) concept was recognized as the most promising solution, ensuring a power saving of around 80% while keeping a limited tritium inventory.

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RELAP5/Mod3.3 thermal-hydraulics characterization of the steam generator mock-up during operational transients in STEAM facility in support of the design of the DEMO WCLL BoP

Vannoni,

Eboli,

Lorusso

et al. 2024

Fusion Engineering and Design

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Analysis of EU-DEMO WCLL Power Conversion System in Two Relevant Balance of Plant Configurations: Direct Coupling with Auxiliary Boiler and Indirect Coupling

Cited by 5 publications

References 19 publications

Water Chemistry Impact on Activated Corrosion Products: An Assessment on Tokamak Reactors

Water Chemistry Impact on Activated Corrosion Products: An Assessment on Tokamak Reactors

Optimized Water Distillation Layout for Detritiation Purpose

RELAP5/Mod3.3 thermal-hydraulics characterization of the steam generator mock-up during operational transients in STEAM facility in support of the design of the DEMO WCLL BoP

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