Published November 1, 2016 | Version v1
Journal article

JET experiments with tritium and deuterium–tritium mixtures

  • 1. EUROfusion Consortium, JET, Culham Science Centre, Abingdon OX14 3DB (United Kingdom)
  • 2. European Commission, B-1049 Brussels (Belgium)
  • 3. JET Exploitation Unit, Culham Science Centre, Abingdon OX14 3DB (United Kingdom)
  • 4. Unità Tecnica Fusione - ENEA C. R. Frascati - via E. Fermi 45, Frascati (Roma), 00044, Frascati (Italy)
  • 5. CCFE, Culham Science Centre, Abingdon OX14 3DB, Oxon (United Kingdom)
  • 6. FOM Institute DIFFER, PO Box 1207, NL-3430 BE Nieuwegein (Netherlands)
  • 7. EUROfusion Programme Management Unit, Culham Science Centre, Abingdon OX14 3DB (United Kingdom)
  • 8. CEA, IRFM, F-13108 Saint Paul Lez Durance (France)
  • 9. Max-Planck-Institut für Plasmaphysik, D-85748 Garching (Germany)

Description

Highlights: • JET is preparing for a series of experiments with tritium and deuterium–tritium mixtures. • Physics objectives include integrated demonstration of ITER operating scenarios, isotope and alpha physics. • Technology objectives include neutronics code validation, material studies and safety investigations. • Strong emphasis on gaining experience in operation of a nuclear tokamak and training scientists and engineers for ITER. - Abstract: Extensive preparations are now underway for an experiment in the Joint European Torus (JET) using tritium and deuterium–tritium mixtures. The goals of this experiment are described as well as the progress that has been made in developing plasma operational scenarios and physics reference pulses for use in deuterium–tritium and full tritium plasmas. At present, the high performance plasmas to be tested with tritium are based on either a conventional ELMy H-mode at high plasma current and magnetic field (operation at up to 4 MA and 4 T is being prepared) or the so-called improved H-mode or hybrid regime of operation in which high normalised plasma pressure at somewhat reduced plasma current results in enhanced energy confinement. Both of these regimes are being re-developed in conjunction with JET's ITER-like Wall (ILW) of beryllium and tungsten. The influence of the ILW on plasma operation and performance has been substantial. Considerable progress has been made on optimising performance with the all-metal wall. Indeed, operation at the (normalised) ITER reference confinement and pressure has been re-established in JET albeit not yet at high current. In parallel with the physics development, extensive technical preparations are being made to operate JET with tritium. The state and scope of these preparations is reviewed, including the work being done on the safety case for DT operation and on upgrading machine infrastructure and diagnostics. A specific example of the latter is the planned calibration at 14 MeV of JET neutron diagnostics.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2016.01.051

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2016.01.051;
PII
S0920-3796(16)30052-7;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
109-111
Journal Issue
Part A
Journal Page Range
p. 925-936
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
12. international symposium on fusion nuclear technology
Acronym
ISFNT-12
Dates
14-18 Sep 2015
Place
Jeju Island (Korea, Republic of)

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.