Impact of blanket material and configuration on the size of a tokamak fusion reactor

On the basis of the Korean fusion roadmap, conceptual design of the DEMO and R&D on the breeding blanket are ongoing. This article addresses the impact of blanket material and configuration on the tritium breeding, shielding characteristics, and resulting size of a tokamak fusion reactor. The re...

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Main Author: Bong Guen Hong
Format: Article
Language:English
Published: Elsevier 2021-03-01
Series:Nuclear Materials and Energy
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S235217912030154X
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spelling doaj-6a1f389ebfdf45d2bff9021f91d6bea02021-03-13T04:24:08ZengElsevierNuclear Materials and Energy2352-17912021-03-0126100892Impact of blanket material and configuration on the size of a tokamak fusion reactorBong Guen Hong0Quantum System Engineering, Jeonbuk National University, Jeonju 54896, Republic of KoreaOn the basis of the Korean fusion roadmap, conceptual design of the DEMO and R&D on the breeding blanket are ongoing. This article addresses the impact of blanket material and configuration on the tritium breeding, shielding characteristics, and resulting size of a tokamak fusion reactor. The reactor parameters were determined via coupled tokamak systems analysis, which incorporated the effect of various materials and configurations of the blanket self-consistently with the plasma performance and the tokamak engineering constraints. In the homogeneous configuration, the minimum major radius was smaller and the TBR (tritium breeding ratio) was larger than in the vertical configuration due to an increase in slow neutron flux. In the vertical configuration, placing a neutron multiplier in front of the blanket resulted in an increase in TBR due to increased slow neutron flux. The HCSB concept among solid blanket concepts allows for a smaller reactor size which satisfies the tritium self-sufficiency and shielding requirements because of the good tritium breeding capability of the solid breeder; the HCLL concept among liquid blanket concepts does as well, due to the good shielding capability of PbLi. The outcomes of this study provide useful guidelines for the feasibility assessment and selection for the blanket concept of the tokamak fusion reactor.http://www.sciencedirect.com/science/article/pii/S235217912030154XTritium breeding blanketBlanket materialBlanket configurationCoupled systems analysisReactor size
collection DOAJ
language English
format Article
sources DOAJ
author Bong Guen Hong
spellingShingle Bong Guen Hong
Impact of blanket material and configuration on the size of a tokamak fusion reactor
Nuclear Materials and Energy
Tritium breeding blanket
Blanket material
Blanket configuration
Coupled systems analysis
Reactor size
author_facet Bong Guen Hong
author_sort Bong Guen Hong
title Impact of blanket material and configuration on the size of a tokamak fusion reactor
title_short Impact of blanket material and configuration on the size of a tokamak fusion reactor
title_full Impact of blanket material and configuration on the size of a tokamak fusion reactor
title_fullStr Impact of blanket material and configuration on the size of a tokamak fusion reactor
title_full_unstemmed Impact of blanket material and configuration on the size of a tokamak fusion reactor
title_sort impact of blanket material and configuration on the size of a tokamak fusion reactor
publisher Elsevier
series Nuclear Materials and Energy
issn 2352-1791
publishDate 2021-03-01
description On the basis of the Korean fusion roadmap, conceptual design of the DEMO and R&D on the breeding blanket are ongoing. This article addresses the impact of blanket material and configuration on the tritium breeding, shielding characteristics, and resulting size of a tokamak fusion reactor. The reactor parameters were determined via coupled tokamak systems analysis, which incorporated the effect of various materials and configurations of the blanket self-consistently with the plasma performance and the tokamak engineering constraints. In the homogeneous configuration, the minimum major radius was smaller and the TBR (tritium breeding ratio) was larger than in the vertical configuration due to an increase in slow neutron flux. In the vertical configuration, placing a neutron multiplier in front of the blanket resulted in an increase in TBR due to increased slow neutron flux. The HCSB concept among solid blanket concepts allows for a smaller reactor size which satisfies the tritium self-sufficiency and shielding requirements because of the good tritium breeding capability of the solid breeder; the HCLL concept among liquid blanket concepts does as well, due to the good shielding capability of PbLi. The outcomes of this study provide useful guidelines for the feasibility assessment and selection for the blanket concept of the tokamak fusion reactor.
topic Tritium breeding blanket
Blanket material
Blanket configuration
Coupled systems analysis
Reactor size
url http://www.sciencedirect.com/science/article/pii/S235217912030154X
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