Description
All posters from Topics I,II,III will be presented within the Poster Session
One of the crucial aspects in the development and commercialization of D-T fusion is the feeding of Tritium, which requires mass-enriched lithium 6, a minority isotope in nature (about 7%).
Although chemical properties are directly related to the electronic configuration of the atom, the mass difference between the isotope nuclei confer slightly different behavior to molecules and ions...
In the path towards the exploitation of nuclear fusion as a virtually unlimited, reliable, and carbon-free energy source, demonstrating tritium self-sufficiency and achieving competitive net electricity production for the grid are of paramount importance.
As the Eni group fosters the industrialization of magnetic confinement fusion, we are committed to mitigating risks and accelerating the...
One of the largest factors severely limiting the anticipated pace to realize fusion on the grid is the development of a set of basic fusion materials, qualified and validated in expensive irradiation campaigns. Initiated by an international working group, Clean Air Task Force’s “Material Database for Fusion” (MatDB4Fusion) aims to collect all kinds of material properties data which are...
The Water-Cooled Lead Lithium (WCLL) is one of the two candidate breeding blanket (BB) concepts actively developed by the EUROfusion consortium for implementation in the European DEMO fusion reactor. DEMO is intended as a technological demonstrator aiming to substantiate the development of nuclear fusion as an energy source by supplying a power conversion system and operating a self-sufficient...
In-Vessel components in fusion nuclear systems have to withstand a very harsh combination of loads and environmental conditions which leads to designs that are significantly more complex and distinct from those of fission components. The ability to accurately predict component performance in in-vessel conditions, factoring in suitable design margins against critical failure mechanisms, is an...
The Korea Institute of Fusion Energy (KFE), in collaboration with Fusion for Energy (F4E), has been actively engaged in the development of manufacturing technologies for the Helium-Cooled Ceramic Pebble (HCCP) Test Blanket Module (TBM) under the ITER program. A key focus is the fabrication and joining of the Cooling Plate (CP) and Breeder Unit (BU), critical components responsible for removing...
Tritium permeation barriers (TPBs) are essential to limit tritium loss and ensure safety in future fusion reactors. This work presents experimental results on hydrogen isotope permeation through Al₂O₃ coatings deposited by Atomic Layer Deposition (ALD) and by Pulsed Laser Deposition (PLD) on fusion-relevant structural materials, including AISI 316L, Nitronic alloys, and Incoloy 800H. Hydrogen...
Fusion power plants that rely on D-T fuel must achieve tritium self-sufficiency, assessed at concept design stages through an evaluation of the tritium breeding ratio (TBR)—the ratio of tritium produced in the breeding blanket to that consumed in the plasma. In developing a concept it is essential to set a design target TBR, for determining the viability of a given design against a risk...
The Water-Cooled Lithium-Lead (WCLL) is one of the breeding blanket concepts proposed by Europe in view of its DEMO reactor. The multi-physics of the system, multi-material domains, and complex blanket geometry characterize some issues in the development of a tritium transport model. However, the prediction of tritium concentrations and inventories in the blanket and the quantification of the...
Developing a sustainable and large-scale nuclear fusion power plant represents one of the most ambitious technological goals of the 21st century. Among the various postulated solutions, magnetic confinement—particularly through tokamaks—stands out as the most advanced and extensively investigated approach. One of the key issues related to the tokamak operation is the need of a plasma pulsed...
