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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.
A. Nicolai, P. Börner
Fusion Science and Technology | Volume 12 | Number 1 | July 1987 | Pages 119-136
Technical Paper | Blanket Engineering | doi.org/10.13182/FST87-A25056
Articles are hosted by Taylor and Francis Online.
The main objective of this numerical study is to investigate how to minimize the tritium content in the first wall of a tokamak reactor. Mainly pulsed tokamak operation with 100-s cycle durations, 75-s duty times, and outgassing phases with durations τg between 500 and 3000 s is envisaged. These outgassing phases are started after every Np cycle (20 < Np < 70). For modeling, a multicode is applied that describes the surface and volume processes determining the tritium inventory in and the permeation through the first wall, the neutral gas background due to the recycling of the plasma, and the transport processes governing the parameters of a three-species burning plasma. The calculations show that control of the wall temperature Tw, determined by the heat transfer to the coolant and the radiation loading by the plasma, is decisive for the tritium buildup. Cooling is achieved by pressurized water or helium at a pressure pHe = 30 bar. The coolant channels are assumed to be composed of a corrugated steel sheet and the first wall, both connected in a panel-type construction. The main results are as follows: 1. In long outgassing phases (τg = 3000 s, Np = 70) at elevated temperatures (Tw = 300° C), the tritium content (˜20 g) after 1400 pulses is ˜2.5 times lower than in continuous irradiation with time-averaged intensity. 2. Shorter but more frequent outgassing phases, e.g., τg = 500 s, Np = 20, are less efficient. 3. Good outgassing efficiency at elevated temperatures is obtained at the expense of an enhanced tritium permeation to the outside. 4. An oxide layer, acting as an ideal diffusion barrier at the outside of the vessel, prevents permeation but effects a tritium content 30% higher than in case 1.
