Conveners
DEMOs and Next Step Facilities
- James Harrison (United Kingdom Atomic Energy Authority)
- Nobuyuki Asakura (National Institutes for Quantum and Radiological Science and Technology (QST))
DEMOs and Next Step Facilities
- James Harrison (United Kingdom Atomic Energy Authority)
- Nobuyuki Asakura (National Institutes for Quantum and Radiological Science and Technology (QST))
A simple extrapolation of the ITER Q=10 H-mode divertor target heat-load specification assuming mitigated type-I ELMs is not sufficient for the exhaust concept required in EU-DEMO provided the increased power level of Pedge = 300MW entering the edge region. The combination of an anticipated reduced power fall-off length of only a few mm in the SOL at a plasma current Ip=20MA whilst keeping the...
The Wendelstein 7-X (W7-X) is an advanced stellarator device operated in Greifswald, Germany, to provide the proof of principle that the stellarator concept can meet the requirements of a future fusion reactor by demonstrating high-performance, steady-state HELIAS operation. During the experimental programs, starting with the first operation phase OP1.1 (Dec. 2015 - March 2016) up to OP1.2a...
SPARC is a compact, high-field short pulse ICRF heated tokamak ($B_{0}=12.2$ T, $R_{0}=1.85$ m, $\tau_{flattop}=10$ s, $P_{rf}=25$ MW) with a close-fitting tungsten first wall designed to achieve its mission goal of $Q_{fus}>2$ with significant margin. Construction has begun at a new site in Devens, MA and operations are scheduled to begin in mid-2025. Although the baseline design relies on...
Significant advances have been made on the physics design of full tungsten divertor and the edge modeling for Chinese Fusion Engineering Testing Reactor (CFETR). CFETR is proposed by Chinese fusion community to bridge the gap between ITER and DEMO with fusion power up to GW level [1]. One of the key challenges is that the divertor solution for CFETR must meet requirements beyond that of ITER...
The STEP programme aims to demonstrate viability of a GW-scale spherical tokamak reactor, with parameters around: geometric axis 3.6m, aspect ratio 1.8, elongation 2.9, plasma current 20MA, on-axis magnetic field 3.2T, core radiated power 350MW, with steady state power crossing the separatrix 150MW. Here we give a physics overview of the studies driving forward the STEP divertor concept...
SONIC divertor code enables simultaneous calculations of seeding impurity (Ar) and fusion product (He ash) transport. He exhaust has been investigated in JA DEMO, where exhaust power ($P_{out}$ = 250 MW), ion flux ($\Gamma_{out}^{D}$ = $\rm 1x10^{22} s^{-1}$) and He ion flux ($\Gamma_{out}^{He}$ =$\rm 5.3x10^{20} s^{-1}$, corresponding to 1.5 GW fusion power) were given at the core-edge...
The new high field superconducting divertor tokamak test facility (DTT) [1] presently under construction is devoted to specifically study power exhaust solutions in regimes as close as possible to those foreseen in DEMO fusion reactor in terms of power crossing the separatrix, $P_{sep}/R$, and heat flux decay length, $\lambda_q$. The first DTT divertor will use the ITER-like technology based...
Safe plasma exhaust with high core performance is one of the remaining challenges on the development path towards a fusion reactor. Alternatives to conventional single-null divertors are assessed as risk mitigation. While multiple null divertors face severe technological challenges, long-legged divertors emerge as a promising option [1] where combination with tight baffling may further...
