Neutronics Simulations for DEMO Diagnostics

Author:

Luís Raul1ORCID,Nietiadi Yohanes1ORCID,Quercia Antonio2ORCID,Vale Alberto1ORCID,Belo Jorge1ORCID,Silva António1ORCID,Gonçalves Bruno1ORCID,Malaquias Artur1ORCID,Gusarov Andrei3ORCID,Caruggi Federico4,Perelli Cippo Enrico4,Chernyshova Maryna5,Bienkowska Barbara5,Biel Wolfgang6

Affiliation:

1. Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisbon, Portugal

2. DIETI/Consorzio CREATE, Università Federico II, Via Claudio 21, 80125 Napoli, Italy

3. SCK CEN Belgian Nuclear Research Center, 2400 Mol, Belgium

4. Institute for Plasma Science and Technology, National Research Council, 20125 Milan, Italy

5. Institute of Plasma Physics and Laser Microfusion, Hery 23, 01-497 Warsaw, Poland

6. Institute of Energy and Climate Research, Forschungszentrum Jülich GmbH, 52428 Jülich, Germany

Abstract

One of the main challenges in the development of a plasma diagnostic and control system for DEMO is the need to cope with unprecedented radiation levels in a tokamak during long operation periods. A list of diagnostics required for plasma control has been developed during the pre-conceptual design phase. Different approaches are proposed for the integration of these diagnostics in DEMO: in equatorial and upper ports, in the divertor cassette, on the inner and outer surfaces of the vacuum vessel and in diagnostic slim cassettes, a modular approach developed for diagnostics requiring access to the plasma from several poloidal positions. According to each integration approach, diagnostics will be exposed to different radiation levels, with a considerable impact on their design. This paper provides a broad overview of the radiation environment that diagnostics in DEMO are expected to face. Using the water-cooled lithium lead blanket configuration as a reference, neutronics simulations were performed for pre-conceptual designs of in-vessel, ex-vessel and equatorial port diagnostics representative of each integration approach. Flux and nuclear load calculations are provided for several sub-systems, along with estimations of radiation streaming to the ex-vessel for alternative design configurations. The results can be used as a reference by diagnostic designers.

Funder

European Union via the Euratom Research and Training Programme

Fundação para a Ciência e Tecnologia

APPLAuSE Doctoral Program

Polish Ministry of Science and Higher Education

Publisher

MDPI AG

Subject

Electrical and Electronic Engineering,Biochemistry,Instrumentation,Atomic and Molecular Physics, and Optics,Analytical Chemistry

Reference62 articles.

1. Pereslavtsev, P., and Leichtle, D. (2023, May 02). DEMO Nuclear Analysis Handbook (NAH). Available online: http://idm.euro-fusion.org/?uid=2NXXCM.

2. The European roadmap towards fusion electricity;Phil. Trans. R. Soc. A,2019

3. High Heat Flux Performance Assessment of ITER Enhanced Heat Flux First Wall Technology after Neutron Irradiation;Hirai;Fusion Eng. Des.,2023

4. Technology Readiness Assessment of Materials for DEMO In-Vessel Applications;Richardson;J. Nucl. Mater.,2021

5. Diagnostics for Plasma Control—From ITER to DEMO;Biel;Fusion Eng. Des.,2019

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