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UKAEA-CCFE-PR(23)132023
Following the first Deuterium-Tritium Experiment (DTE1) at UKAEA, modifications were investigated to the Joint European Torus’ (JET) gas introduction systems to increase the gas feed capabilities of the JET facility to better support future campaigns. The gas introduction systems comprise the gas introduction and gas distribution system (GI/GD)…
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UKAEA-CCFE-PR(23)122023
The future of nuclear fusion as a viable energy source has two major hurdles to overcome. Firstly, there are the daunting and complex technology and physics issues to be resolved before a power plant capable of breeding its own fuel and producing an excess of electricity can be built. Secondly, fusion must offer a useful and economically competitiv…
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UKAEA-CCFE-PR(23)112023
A prototype infrared video bolometer (IRVB) was succesfully deployed in MAST-U, the first deployment of such a diagnostic in spherical tokamaks. The IRVB was designed to study the radiation around the x-point and has the potential to return emissivity profiles of unprecedented spatial resolution. The system was fully characterised prior installatio…
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UKAEA-CCFE-PR(23)102022
The fusion-born alpha-particle heating in magnetically confined fusion machines is a high priority subject for study. The self-heating of thermonuclear fusion plasma by alpha-particles was observed in recent deuterium-tritium (D-T) experiments on the Joint European Torus (JET). This observation was possible by conducting so-called “af…
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UKAEA-CCFE-PR(23)092023
Following from the paper describing the remote wide angle viewing system compatible with Deuterium-Tritium operations. This is the second article describing a second remote line of sight, this time focusing on the imaging of the divertor region in JET. It explains in detail the optical and engineering designs of constructing an optical relay which …
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UKAEA-CCFE-PR(23)082022
The role of ion-molecule elastic collisions (specifically D+−D2 collisions) in strongly detached divertor conditions has been studied in the MAST-U Super-X configuration using SOLPS-ITER. Two strongly detached steady state solutions, one obtained through a main-ion (D2) fuelling scan and the other through an impurity (N) seeding scan at fixed …
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UKAEA-CCFE-CP(23)012023
The JET 2019–2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power in 2019–2020, and …
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UKAEA-CCFE-PR(23)072023
A Tritium fuel cycle must have the capability to import tritium inventory from transport storage containers to enable initial inventory stockpiling and future refresh of the inventory. The Joint European Torus (JET) Active Gas Handling System (AGHS) previously imported tritium inventory from Amersham Uranium beds (U-beds) via a decanting system hou…
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UKAEA-CCFE-PR(23)062023
The Exhaust Detritiation System (EDS) of the JET Active Gas Handling System (AGHS) removes tritium from exhaust gases and contaminated air prior to discharge to stack. The system was replaced prior to JET’s tritium experimental campaign due to corrosion damage. In this paper, the following topics are presented: System function and de…
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UKAEA-CCFE-PR(23)052023
Predictions of material activity in commercial fusion conditions predominantly rely on computational methods, due to a lack of data on long-term e ects of high-energy neutron irradiation on structural steels. Consequently, this could result in a bias due to uncertainties in nu…
Showing 621 - 630 of 2581 UKAEA Paper Results