1,721,065 research outputs found
From Design to Procurement of Tokamak Mechanical Structures
No full textNuclear fusion facilities, as tokamaks, are very complex devices, due to the harsh environmental conditions required to maintain the plasma advance confinement scenarios and the deuterium-tritium fusion reaction (huge temperatures, nuclear radiation, extreme electromagnetic loads). Therefore, several specific concerns shall be considered during the design process of a tokamak, and appropriate solutions shall be designed and provided. These concerns are treated in this paper and some of their possible solutions are explained. This is done following the flow of good practice design process, focusing on each stage from the material selection to the component procurement
Simulation of the beamline thermal measurements to derive particle beam parameters in the ITER neutral beam test facility
No full textInvestigation of corrosion-erosion phenomena in the primary cooling system of SPIDER
Full text linkSPIDER dedicated cooling plant has to remove up to 10 MW thermal power from in-vessel components and auxiliary systems. The circuit is characterized by three main heat transfer systems: primary, secondary and tertiary systems. The primary system is made of four circuits, with only three operating so far, these are called PC01, PC02 and PC03. These three circuits respectively cool SPIDER power supplies and the beam source components using ultrapure water. During 2019 SPIDER experimental campaigns, it was observed that electrical resistivity of water degraded considerably and more quickly (∼25 MΩ cm h−1 in PC01) than estimated by design. To overcome this issue, water had to be restored very frequently to maintain the desired characteristics and avoid possible detrimental leakage currents throughout the circuit. The reason for this severe water degradation has to be better understood before issues such as abrupt failures may arise. This work presents a preliminary analysis of the two main circuits (PC01 and PC02) where an estimation of water degradation induced by general corrosion of stainless steels and copper components was made. This preliminary estimation showed that PC01 could be more prone to general corrosion than PC02; however, the rate of water conductivity increase was 5.3 times smaller than that observed during experiments in 2019 and 2020
Overall survival in BRCA-associated ovarian cancer case-control study of an Italian series
No full text
Effects of seismic isolation on the dynamic behaviour of the DTT torus complex during earthquake events
No full textPreliminary Thermo-Mechanical Design of the Once through Steam Generator and Molten Salt Intermediate Heat Exchanger for EU DEMO
No full textThe European DEMOnstration power plant (DEMO) is considered to be the nearest-term fusion reactor capable of producing several hundred MWs of net electricity, operating with a closed tritium fuel-cycle (achieving the tritium self-sufficiency), and qualifing technological solutions for a fusion power plant with different breeding blanket (BB) concepts that are under investigation. The BB is a key component for the development of the DEMO plant design and, in particular, of those systems having the responsibility to remove the plasma-generated thermal power and its conversion in the electrical energy. This study deals with the preliminary thermo-mechanical design of the heat exchangers and steam generator components. The design criteria and the main design analyses were discussed to achieve a simple but robust design. The proposed preliminary thermo-mechanical designs, both for heat exchangers and for steam generators, are considered feasible
- …
