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UKAEA-CCFE-CP(20)822018
The containment vessel of the Joint European Torus is a huge, complicated assembly with a myriad of components, all of which are important for plasma operation. As a research device, JET has been operated over many years and has been extensively rebuilt. During each maintenance shutdown, inspections and measurements of the Vacuum Vessel are carri…
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UKAEA-CCFE-CP(20)832018
The authors exposed a radiatively cooled, lithium-filled tantalum heat pipe (HP) to a hydrogen plasma in DIFFER’s linear plasma source Magnum PSI continuously for ~2 hours. The beam made a saddle-shaped footprint along the side of the inclined ~195-mm-long HP. During several steps with constant overall heat load, we tilted the HP to vary the peak…
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UKAEA-CCFE-CP(20)792018
The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…
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UKAEA-CCFE-CP(20)802018
The European DEMO design will potentially use single phase water cooling in various components that require protection against corrosion damage. Coolant conditions will be similar to fission PWRs but with additional considerations arising from the materials of choice (Eurofer, CuCrZr), 14 MeV neutron irradiation, the presence of tritium, and strong…
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UKAEA-CCFE-CP(20)812018
The Alfvén Eigenmode Active Diagnostic system (AEAD) has undergone a major upgrade and redesign to provide a state of the art excitation and real-time detection system for JET. The new system consists of individual 4kW amplifiers for each of the six antennas, allowing for increased current, separate excitation and real time control of relative …
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UKAEA-CCFE-CP(20)782018
We report on the selection, implementation and successful demonstration of a new automated laser control system for JET’s Far Infrared Interferometer, a diagnostic essential for machine protection. The new control system allows all laser subsystems and sensors to be interlocked and operated remotely in a precise and preprogramed manner, functiona…
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UKAEA-CCFE-CP(20)772018
Neutral beam injection is one of the primary auxiliary heating systems for tokamak plasmas. Once the neutral beam leaves the neutraliser collisions with background neutral particles in the beamline and tokamak vessel re-ionises part of the neutral beam. These particles can be deflected by the tokamak magnetic field, potentially damaging unshielded …
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UKAEA-CCFE-CP(20)762018
In 1998 Makhankov [1] described the concept of modular exchangeable plasma facing components (PFCs) based on liquid metal heat pipes which are radiatively cooled. Here we present results from recent experiments with a lithium filled tubular heat pipe owned by Sandia National Laboratories. The tantalum envelope (~20mm diameter by ~200mm long) was he…
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UKAEA-CCFE-CP(20)752018
Within the DEMO first wall 3-D shape design activity the first study of the effect of misalignment has started. Such assessments have been conducted in the past for ITER and penalty factor maps have been created; this route could be a feasible approach in the case of DEMO wall design also. This paper details the first set of computational tests tha…
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UKAEA-CCFE-CP(20)742020
Post mortem analysis shows that mid and high atomic number metallic impurities are present in deposits on JET plasma facing components with the highest amount of Ni and W, and therefore the largest sink, being found at the top of the inner divertor. Sources are defined as “continuous” or “specific”, in that “continuous” sources…
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