Published November 2017 | Version v1
Journal article

An innovative approach for DEMO core fuelling by inboard injection of high-speed pellets

  • 1. ENEA C.R. Frascati, 00044 Frascati, Rome (Italy)
  • 2. Karlsruhe Institute of Technology, 76021 Karlsruhe (Germany)
  • 3. Max Planck Institute for Plasma Physics, 85748 Garching (Germany)
  • 4. CEA-IRFM, 13108 Saint-Paul-lez-Durance (France)

Description

Highlights: • Effective core fueling in DEMO requires launching pellets from the High Field Side. • Injection speeds not less than 1 km/s will be necessary, even from the HFS. • Guiding tracks with a bend radius ≥6 m are envisaged to deliver intact pellets. • Injection of high-speed pellets from the HFS along free-flight paths, is proposed. • Outboard high-speed injection is still being considered, instead, for JT-60SA. - Abstract: Core fuelling of DEMO tokamak fusion reactor is under investigation within the EUROfusion Work Package "Tritium, Fuelling and Vacuum". An extensive analysis of fuelling requirements and technologies, suggests that pellet injection still represents, to date, the most realistic option. Modelling of both pellet penetration and fuel deposition profiles for different injection locations, assuming a specific plasma reference scenario and the ITER reference pellet mass (6 × 1021 atoms), indicates that: 1) Low Field Side (LFS) injection is inadequate; 2) Vertical injection may be effective only provided that pellets are injected at ∼ 10 km/s from a radial position ≤∼8 m; 3) effective core fuelling can be achieved launching pellets from the High Field Side (HFS) at ∼1 km/s. HFS injection was therefore selected as the reference scheme, though scenarios featuring less steep density and temperature gradients at the plasma edge could induce to reconsider vertical injection at speeds in the range of 4–5 km/s. To deliver intact pellets at 1 km/s from the HFS, the use of guide tubes with a bend radius ≥6 m is envisaged. The results of above simulations rely on the hypothesis that pellets are delivered at the plasma edge with the desired mass and speed. However, mass erosion and fracturing of pellets inside the guide tube (severely limiting the transfer speed), as well as pressure build up and speed losses at relevant injection rates, might hamper the use of curved guide tubes. An additional innovative approach, aimed at identifying inboard straight "free flight" injection paths, to inject pellets from the HFS at significantly higher speeds, is proposed and discussed as a backup solution. Outboard high-speed injection is still being considered, instead, for JT-60SA.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2017.03.067

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2017.03.067;
PII
S0920-3796(17)30289-2;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
124
Journal Page Range
p. 846-849
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
29. symposium on fusion technology
Acronym
SOFT-29
Dates
5-9 Sep 2016
Place
Prague (Czech Republic)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
49088879
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
GUIDE TUBES; HYPERFINE STRUCTURE; ITER TOKAMAK; MASS; MATHEMATICAL SOLUTIONS; PELLET INJECTION; PLASMA; TEMPERATURE GRADIENTS
Descriptors DEC
CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TUBES

Optional Information

Copyright
Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.