Conceptual study of ferromagnetic pebbles for heat exhaust in fusion reactors with short power decay length
Creators
- 1. Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung - Plasmaphysik, 52425 Jülich (Germany)
- 2. Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung - Werkstoffstruktur und -eigenschaften, 52425 Jülich (Germany)
Description
Highlights: • Ferromagnetic pebbles are investigated as high heat flux plasma-facing components in fusion devices. • Steel grade 1.4510 is chosen as a candidate material due to the Fe-Cr composition and the availability of material data. • Optimum pebble diameter and exposure time for given q|| are obtained from numerical transient thermal simulations. • Inward acceleration of the ferromagnetic pebbles due to magnetic gradients in a tokamak is used to exchange the pebbles. • For narrow λq profiles very high heat fluxes > 500 MW/m2 are accessible in the operation space of ferromagnetic pebbles. • Ferromagnetic pebbles are compatible with tokamak operation and current divertor designs - Abstract: Ferromagnetic pebbles are investigated as high heat flux (q∥) plasma facing components in fusion devices with short power decay length (λq) on a conceptual level. The ability of a pebble concept to cope with high heat fluxes is retained and extended by the acceleration of ferromagnetic pebbles in magnetic fields. An alloying concept suited for fusion application is outlined and the compatibility of ferromagnetic pebbles with plasma operation is discussed. Steel grade 1.4510 is chosen as a well characterized candidate material to perform an analysis of the heating process. Scaling relationships as a function of q∥ for maximum and optimal pebble diameter, allowed exposure time, and removal time safety margin are obtained numerically for spherical pebble geometry. The acceleration of ferromagnetic pebbles in a tokamak resulting from magnetic gradients is studied and operation parameters for an ITER-based reactor are outlined. Counter-intuitively, it is found that ferromagnetic pebbles perform better for narrow λq profiles, making them an attractive heat exhaust concept for next step devices and thus an option to be investigated in detail. The key results of this study are that very high heat fluxes are accessible in the operation space of ferromagnetic pebbles, that ferromagnetic pebbles are compatible with tokamak operation and current divertor designs, that the heat removal capability of ferromagnetic pebbles increases as λq decreases and, finally, that for fusion relevant values of q∥ pebble diameters below 100 μm are required.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nme.2015.01.001Additional details
Identifiers
- DOI
- 10.1016/j.nme.2015.01.001;
- PII
- S2352179114200056;
Publishing Information
- Journal Title
- Nuclear Materials and Energy
- Journal Volume
- 2
- Journal Page Range
- p. 12-19
- ISSN
- 2352-1791
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50070371
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- DECAY; FERROMAGNETIC MATERIALS; FIRST WALL; HEAT FLUX; ITER TOKAMAK; MAGNETIC FIELDS; MAGNETS
- Descriptors DEC
- CLOSED PLASMA DEVICES; EQUIPMENT; MAGNETIC MATERIALS; MATERIALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.