Neutronics assessment of EU DEMO alternative divertor configurations
Creators
- 1. Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, OX14 3DB, Oxford (United Kingdom)
- 2. ENEA, Department of Fusion and Nuclear Safety Technology, I-00044 Frascati Rome (Italy)
- 3. Institute of Plasma Physics and Laser Microfusion, ul. Hery 23, 01-497 Warsaw (Poland)
Description
Highlights: • First neutronics assessment of alternative divertor configurations in DEMO. • Shielding proposals to reduce TF coil heat loads and neutron streaming. • DPA, helium production and to assess material damage and lifetimes of components. • MCNP model constructed for SN, SX and XD divertor configurations. • Tritium breeding ratio (TBR) calculated for SN, SX and XD divertor configurations. As a demonstration fusion power plant, EU DEMO has to prove the maturity of fusion technology and its viability for electricity production. The central requirements for DEMO rest on its capability to generate significant net electric power to the grid (300 MW to 500 MW) safely and consistently. Plant availability and lifetime will approach that of a commercial fusion power plant. Operating at such regimes presents many complex challenges, of which one is plasma exhaust. To mitigate the risk that the implementation in preceding experimental devices, namely ITER, does not extrapolate to the requirement of DEMO, alternative solutions must be sought. The investigation of alternative divertor configurations was born out of this motive, seeking to resolve a 'critical' challenge for the realisation of DEMO. In this paper, we study the neutronics performance of three concepts: Single Null (SN), Super-X (SX) and X-divertor (XD). This is the first time a preliminary analysis of alternative configurations to the SN baseline has been performed. The shielding proposals and design recommendations presented herein should be integrated with other engineering and physics constraints in future iterations of the chosen divertor concept.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2021.112663Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2021.112663;
- PII
- S0920379621004397;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 169
- Journal Page Range
- vp.
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54004388
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S74: ATOMIC AND MOLECULAR PHYSICS;
- Descriptors DEI
- ATOMIC DISPLACEMENTS; BREEDING RATIO; DESIGN; DIVERTORS; ELECTRICITY; HEATING LOAD; ITER TOKAMAK; NEUTRON TRANSPORT; NEUTRONS; PLASMA; SHIELDING; THERMONUCLEAR POWER PLANTS; TRITIUM
- Descriptors DEC
- BARYONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; CONVERSION RATIO; DIMENSIONLESS NUMBERS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NEUTRAL-PARTICLE TRANSPORT; NUCLEI; NUCLEONS; ODD-EVEN NUCLEI; PHYSICAL RADIATION EFFECTS; POWER PLANTS; RADIATION EFFECTS; RADIATION TRANSPORT; RADIOISOTOPES; THERMAL POWER PLANTS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2021 Published by Elsevier B.V.