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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Reinhard Uhlemann, Jef Ongena
Fusion Science and Technology | Volume 35 | Number 1 | January 1999 | Pages 42-53
Technical Paper | doi.org/10.13182/FST99-A76
Articles are hosted by Taylor and Francis Online.
The neutral beam injectors of the tokamak experiment TEXTOR produce neutral particle beams in the megawatt range at 55 keV and up to a 10-s pulse length of the light atoms hydrogen, deuterium, 3He, and 4He for heating the fusion plasma of TEXTOR. The two injectors are equipped with one 5-MW ion source (plug-in neutral injector) each. The injected power of ~1.5 MW of each injector can be varied from 0 to 100% by opening the main beam target vertical aperture in steps of ~2 cm to the full opening of 50 cm. The symmetric truncation of the neutral beam profile at a target position 4.5 m from the ion source leads to no major deformation of the profile downstream at the entrance into the torus plasma at a 6-m distance from the ion source. Whereas usually the particle energy, i.e., acceleration voltage, and beam current or, alternatively, the gas pressure in the neutralizer at fixed energy must be varied to change the injected power, these beam parameters can be kept constant with the reported method to study the effect of different injected neutral beam powers on the fusion plasma. The transmitted power to the torus is detected by the calorimetrically measured remaining power on the beam target. The resulting transmitted neutral beam power as a function of the target aperture is in good agreement with the expected integral of the thus-truncated Gaussianlike beam profile, i.e., the error function. The scaling of the resulting injected neutral beam power, beam profiles, vertical full-width-at-half-maximum, and central power density with variation of the beam target aperture are in good agreement with the beamline simulation code PADET.
