A strategy to develop power exhaust solutions for tokamaks beyond IT
Description
Predictions for the scrape-off layer (SOL) in future fusion devices based on empirical scalings imply extremely large parallel heat flux, q|| ~10 GW/m2, which is exacerbated for high-field concepts that may enable a Compact Pilot Plant (CPP) as recommended by a recent US strategic planning assessment. Here we discuss the framework of a proposed ~10 year program to more firmly establish the basis for power handling in tokamaks by extending the paradigm of solid (likely high-Z) walls using noble gas seeding to increase impurity radiation. This is intended to take relatively mature science and technologies relevant to power exhaust and particle control (PFCs, pumping) and demonstrate the combined physics and engineering basis for a divertor solution for a tokamak-based CPP. The aims of this program are to a) establish the predictive basis for projecting heat flux and the conditions for its mitigation; b) develop core confinement scenarios that minimize exhaust requirements on the divertor; c) test the interaction between radiative divertor and high-pressure pedestals at-scale; and d) explore the potential of alternative divertor geometries as risk mitigation should the conventional geometry employed in ITER prove to be insufficient for CPP requirements.
Additional details
Identifiers
Publishing Information
- Imprint Title
- Third IAEA Technical Meeting on Divertor Concepts. Report of Abstracts
- Imprint Pagination
- 68 p.
- Journal Page Range
- p. 3-4
- Report number
- INIS-XA--21M2087
Conference
- Title
- 3. IAEA Technical Meeting on Divertor Concepts
- Acronym
- DC 2019
- Dates
- 4-7 Nov 2019
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52124360
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIVERTORS; GEOMETRY; HEAT FLUX; ITER TOKAMAK; MITIGATION; PILOT PLANTS; PLASMA CONFINEMENT; PLASMA IMPURITIES; PLASMA SCRAPE-OFF LAYER; PUMPING; RARE GASES
- Descriptors DEC
- BOUNDARY LAYERS; CLOSED PLASMA DEVICES; CONFINEMENT; ELEMENTS; FLUIDS; FUNCTIONAL MODELS; GASES; IMPURITIES; LAYERS; MATHEMATICS; NONMETALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Contract/Grant/Project number
- Contract DE-AC05-00OR22725
- Notes
- 3 refs.