Published 2019 | Version v1
Report

A strategy to develop power exhaust solutions for tokamaks beyond IT

  • 1. Oak Ridge National Laboratory (United States)

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.

Part of:
Third IAEA Technical Meeting on Divertor Concepts. Report of Abstracts

Additional details

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.