Design and Integration of the EU-DEMO Water-Cooled Lead Lithium Breeding Blanket

Author:

Arena Pietro1ORCID,Bongiovì Gaetano2ORCID,Catanzaro Ilenia2ORCID,Ciurluini Cristiano3ORCID,Collaku Aldo4,Del Nevo Alessandro1ORCID,Di Maio Pietro Alessandro2ORCID,D’Onorio Matteo3ORCID,Giannetti Fabio3ORCID,Imbriani Vito5ORCID,Maccari Pietro1ORCID,Melchiorri Lorenzo3,Moro Fabio6ORCID,Mozzillo Rocco7ORCID,Noce Simone8,Savoldi Laura4ORCID,Siriano Simone3ORCID,Tassone Alessandro3ORCID,Utili Marco1ORCID

Affiliation:

1. ENEA, Department of Fusion and Nuclear Safety Technology, C.R. Brasimone, 40032 Camugnano, Italy

2. Department of Engineering, University of Palermo, Viale delle Scienze, Edificio 6, 90128 Palermo, Italy

3. DIAEE Department, Sapienza University of Rome, 00186 Rome, Italy

4. MAHTEP Group, Department of Energy “Galileo Ferraris”, Politecnico of Turin, 10129 Turin, Italy

5. CREATE, Department of Industrial Engineering, University of Naples Federico II, 80125 Naples, Italy

6. ENEA, Department of Fusion and Nuclear Safety Technology, C.R. Frascati, 00044 Frascati, Italy

7. CREATE, Engineering School, Basilicata University, 85100 Potenza, Italy

8. Industrial Engineering Department, University of Rome Tor Vergata, 00133 Rome, Italy

Abstract

The water-cooled lead lithium breeding blanket (WCLL BB) is one of two BB candidate concepts to be chosen as the driver blanket of the EU-DEMO fusion reactor. Research activities carried out in the past decade, under the umbrella of the EUROfusion consortium, have allowed a quite advanced reactor architecture to be achieved. Moreover, significant efforts have been made in order to develop the WCLL BB pre-conceptual design following a holistic approach, identifying interfaces between components and systems while respecting a system engineering approach. This paper reports a description of the current WCLL BB architecture, focusing on the latest modifications in the BB reference layout aimed at evolving the design from its pre-conceptual version into a robust conceptual layout. In particular, the main rationale behind design choices and the BB’s overall performances are highlighted. The present paper also gives an overview of the integration between the BB and the different in-vessel systems interacting with it. In particular, interfaces with the tritium extraction and removal (TER) system and the primary heat transfer system (PHTS) are described. Attention is also paid to auxiliary systems devoted to heat the plasma, such as electron cyclotron heating (ECH). Indeed, the integration of this system in the BB will strongly impact the segment design since it envisages the introduction of significant cut-outs in the BB layout. A preliminary CAD model of the central outboard blanket (COB) segment housing the ECH cut-out has been set up and is reported in this paper. The chosen modeling strategy, adopted loads and boundary conditions, as well as obtained results, are reported in the paper and critically discussed.

Funder

European Union via the Euratom Research and Training Programme

Publisher

MDPI AG

Subject

Energy (miscellaneous),Energy Engineering and Power Technology,Renewable Energy, Sustainability and the Environment,Electrical and Electronic Engineering,Control and Optimization,Engineering (miscellaneous),Building and Construction

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