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UKAEA-CCFE-PR(25)3792025
A robust disruption mitigation system (DMS) requires accurate characterization of key disruption timescales, one of the most notable being the thermal quench (TQ). Recent modeling of shattered pellet injection (SPI) into ITER plasmas, using JOREK and INDEX, suggests long TQ durations (6–10 ms) and slow cold front propagation due to the large p…
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UKAEA-CCFE-PR(25)3012025
Detailed results are presented from the first experimental study of self-regulation between plasma relative density fluctuations and perpendicular velocity over limit cycle oscillations (LCO) across the edge and near scrape-off layer (SOL) regions of the MAST-U spherical tokamak. The start of the dithering phase is preceded by the localisation of t…
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UKAEA-RACE-PR(25)042025
The Vacuum Vessel Pressure Suppression System Remote Handling Equipment (VVPSS RHE) is being developed for remote maintenance of VVPSS components, including the Rupture Disc Assembly (RDA), Bleed Line Valve Assembly (BLVA), Support Trolley and relief lines within the Neutral Beam (NB) cell. It works in conjunction with the Neutral Beam Remote Ha…
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UKAEA-CCFE-CP(25)252024
The integrated modelling tool JINTRAC [1] was recently updated and now has the unique capability of fully consistent treatment of Deuterium and Tritium in the whole plasma volume. In this work this is utilized with coupled core-SOL-divertor simulations performed for the ITER 15MA/5.3T DT Q=10 scenario. The work is built on previous simulations publ…
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UKAEA-CCFE-PR(24)2142024
In order to test the capability of the full electromagnetic DYON to predict the plasma initiation feasibility of individual discharges and thus the operating space in the device, a dedicated experimental database was built in MAST-U by scanning the prefilled gas pressure $p_0$ and the induced loop voltage $V_{loop}$ (3 failed breakdown discharge…
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UKAEA-CCFE-PR(24)032024
To design a safe termination scenario for a burning ITER plasma is a challenge that requires extensive core plasma and divertor modelling. The presented work consists of coupled core/edge/SOL/divertor simulations, performed with the JINTRAC code, studying the Q=10 flat-top phase and exit phase of the ITER 15MA/5.3T DT scenario. The modelling uti…
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UKAEA-CCFE-PR(25)2682023
In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure no production of neutrons from fusion reactions. With the expected higher L-H power threshold of hy…
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UKAEA-CCFE-PR(24)2472023
The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challeng…
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UKAEA-CCFE-PR(24)2452023
2021 JET experimental campaign has produced high stationary fusion power with 50%D 50%T discharges, operated with the ITER-relevant conditions i.e. operation with the baseline or hybrid scenario in the full metallic wall. It has provided a unique opportunity to assess the DT fusion power prediction capability before ITER DT experiments. This pap…
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UKAEA-CCFE-PR(23)1912023
ITER is of key importance in the European fusion roadmap as it aims to prove the scientific and technological feasibility of fusion as a future energy source. The EUROfusion consortium of labs is contributing to the preparation of ITER scientific exploitation and operation and aspires to exploit ITER outcomes in view of DEMO. The paper provides …
Showing 1 - 10 of 45 UKAEA Paper Results