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UKAEA-CCFE-PR(24)2372021
Control of the detachment front between the target and the X-point is necessary for minimizing the effect of detachment on the core plasma (core radiation and loss of confinement) and maximizing the divertor functions (reduction of target heat load and sputtering, He pumping). However, such control has been difficult in experiments. The SOLPS-IT…
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UKAEA-CCFE-CP(23)342021
The characteristically intense neutron source generated in deuterium-tritium (DT) fusion power presents notable challenges for materials comprising the structure of the device which are exposed to them. These include radiation damage effects leading to degradation of structural properties with impact on maintenance and replacement frequency, but…
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UKAEA-STEP-CP(23)032021
The application of dc magnetic field to a 2G high temperature superconducting (HTS) tape can reduce the critical current Ic of the tape, without driving the material normal. This property can be used in the development of HTS switching elements through so-called Jc(B) switching. The design of a dc magnetic field switch is reported, in both singl…
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UKAEA-STEP-CP(23)022021
High temperature superconducting magnets offer a novel pathway to magnetic confinement fusion energy generation. Reactor-scale fusion devices require tens of kA of current to generate large toroidal fields for magnetic confinement. Operating HTS magnets at kA-current levels is difficult due to unavoidable joint resistances that require active dr…
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UKAEA-CCFE-CP(23)302021
Many of the essential data analysis procedures for a tokamak experiment rely on the knowledge of the magnetic field structure obtained from MHD force balance. On JET, the code that is responsible for computing the magnetic equilibrium is called EFIT++. Interpretation of JET data has been challenging due to inconsistencies between diagnostic meas…
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UKAEA-CCFE-PR(23)972021
The aim of this paper is to numerically study the influences of the impurities on the high power hybrid discharges in the JET ILW configuration in the DD and DT scenarios. Numerical simulations with the COREDIV code of hybrid discharges with 32MW auxiliary heating, 2.2MA plasma current and 2.8T toroidal magnetic field in the ITER-like wall (ILW)…
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UKAEA-CCFE-PR(23)962021
The Debye sheath is shown to vanish completely in magnetised plasmas for a sufficiently small angle between the magnetic field and the wall that depends on the current to the wall. When the Debye sheath vanishes, there is still a potential drop between the wall and the plasma across the magnetic presheath. The magnetic field angle corresponding …
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UKAEA-CCFE-CP(23)232021
This paper describes a case study in seeking to encourage widespread adoption of Systems Engineering at the UK Atomic Energy Authority. Until recently, the quest for fusion energy has primarily been in the scientific research domain, but with a shift in focus to delivering commercially viable fusion power plants, there is a clear need for SE to …
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UKAEA-CCFE-CP(23)202021
Disruption prediction and avoidance is critical for ITER and reactor-scale tokamaks to maintain steady plasma operation and to avoid damage to device components. The present status and results from the disruption event characterization and forecasting (DECAF) research effort are shown. The DECAF paradigm is primarily physics-based and provides q…
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UKAEA-CCFE-CP(23)182021
As the EUROfusion EU-DEMO design programme approaches the transition between the pre-conceptual and conceptual design phase the systems code PROCESS has been improved to incorporate more detailed plasma physics, engineering and analysis modules. Unlike many systems codes PROCESS combines the physics modelling with both technology and costs analysis…
Showing 41 - 50 of 500 UKAEA Paper Results