UKAEA Papers

Showing 241 - 250 of 1892 UKAEA Paper Results
2018
UKAEA-CCFE-CP(20)86

Nuclear fusion is the process that heats the stars by the collision of atomic nuclei which fuse together to form heavier elements and release energy. The generation of energy using this process has several advantages: no carbon emissions, abundant fuel supplies, efficiency, reliability and operationally safe. One way to achieve the necessary con…

Preprint Published
2019
UKAEA-CCFE-CP(20)84

JET has now completed three operating periods, ILW1, ILW2 and ILW3, giving an opportunity to make comparisons between tiles exposed for single operating periods and also comparisons of tiles exposed for all three periods, ILW1-3 (2011-2016). In this contribution, a comprehensive overview of fuel retention and material erosion/deposition patterns…

Preprint Published
2018
UKAEA-CCFE-CP(20)82

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…

Preprint Published
2018
UKAEA-CCFE-CP(20)83

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…

Preprint Published
2018
UKAEA-CCFE-CP(20)79

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…

Preprint Published
2018
UKAEA-CCFE-CP(20)80

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…

Preprint Published
2018
UKAEA-CCFE-CP(20)81

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 …

Preprint Published
2018
UKAEA-CCFE-CP(20)78

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…

Preprint Published
2018
UKAEA-CCFE-CP(20)77

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 …

Preprint Published
2018
UKAEA-CCFE-CP(20)76

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…

Preprint Published