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Fusion energy: Progress, partnerships, and the path to deployment
Over the past decade, fusion energy has moved decisively from scientific aspiration toward a credible pathway to a new energy technology. Thanks to long-term federal support, we have significantly advanced our fundamental understanding of plasma physics—the behavior of the superheated gases at the heart of fusion devices. This knowledge will enable the creation and control of fusion fuel under conditions required for future power plants. Our progress is exemplified by breakthroughs at the National Ignition Facility and the Joint European Torus.
A C Bell, J L Hemmerich, R Lässer, N Bainbridge, G Bishop, D Brennan, C Caldwell-Nichols, J Campbell, A Dearden, B Grieveson, G Jones, J Lupo, J Mart, A Perevezentsev, N Skinner, R Stagg, K Walker, R Warren, J Yorkshades
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1301-1306
Design, Operation, and Maintenance of Tritium System | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30590
Articles are hosted by Taylor and Francis Online.
The Joint European Torus (JET) carried out the first preliminary experiment with a deuterium-tritium plasma in 1991. This utilised an on-site inventory of 0.25g. The future experimental programme for the JET machine includes two discrete phases using plasmas fuelled by deuterium and tritium. The first of these, in mid-1996, will generate around 2 × 1020 neutrons and require a site inventory of a few grams of tritium. The second is proposed to take place in 1999 if an extension to the JET project from 1996 is granted. This will require a few tens of grams of tritium and will generate up to 5 × 1021 neutrons. The JET Active Gas Handling System has been constructed to enable tritium to be recovered from the plasma exhaust and stored for re-injection. The design also minimises tritium discharges to the environment. It is currently being commissioned to meet the above programme and has been modified to take into account a new requirement for operation over extended periods during maintenance and D-D operation with tritium contaminated plasma exhaust. Commissioning of the Active Gas Handling System consists of inactive, trace tritium (∼40TBq) and full tritium (<3g) phases. The experience and main results of inactive commissioning are presented and the status of tritium commissioning is reviewed.
