Conference Papers

Showing 91 - 100 of 260 Conference Paper Results
2022
UKAEA-CCFE-CP(22)10
24th Topical Conference on High Temperature Plasma Diagnostics (HTPD), Rochester, NY, USA, 15 - 19 May 2022

We use the beam model of Doppler backscattering (DBS), which was previously derived from beam tracing and the reciprocity theorem, to shed light on mismatch attenuation. This attenuation of the backscattered signal occurs when the wavevector of the probe beam’s electric field is not in the plane perpendicular to the magnetic field. Correcting …

Published
2022
UKAEA-CCFE-CP(22)09
2021 IEEE Pulsed Power Conference & Symposium on Fusion Engineering (PPC/SOFE) NPSS, Denver, Colarado, USA, 12-16 December 2021

SPIDER (Source for the Production of Ions of Deuterium Extracted from a Radio frequency plasma) is the full scale prototype for the ITER Heating Neutral Beam (HNB) source. Driven by four driver coil pairs powered by oscillators the SPIDER source plasma exhibits fluctuations in a range of frequencies that have been observed by Langmuir probes and So…

Preprint
2022
UKAEA-CCFE-CP(22)08
31st Symposium on Fusion Technology (SOFT), Dubrovnik, Croatia, 20 - 25 September 2020

The charged particle heat load assessed for the DEMO Single Module Segment First Wall (FW) during current off-normal plasma scenarios underlines that protection is needed for avoiding/reducing damage to the Breeding Blanket FW due to the deposition of a huge amount of energy in a small timescale. Within the “Key Design Integration Issue 1”, an…

Preprint Published
2022
UKAEA-CCFE-CP(22)07
PhDiaFusion 2021, Kraków, Poland, 20th - 24th September, 2021

Neutron spectrum unfolding using activation foils is currently the primary technique planned for measuring the neutron energy spectrum at the first wall of power-generating fusion reactors. Room for improvement in the effectiveness of current foil selection was identified, and a program produced to select foils procedurally in order to maximise the…

Preprint Published
2022
UKAEA-CCFE-CP(22)06
International Conference on Physics of Reactors 2022 (PHYSOR 2022), Pittsburgh, USA, 15–20 May 2022

We present new two applications, AURORA and Achlys, developed using the MOOSE framework for finite element analysis, intended to facilitate engineering analysis for fusion reactors. Respectively these couple neutronics and tritium transport to native MOOSE physics modules including heat conduction and tensor mechanics. We outline steps taken to pe…

Preprint
2022
UKAEA-STEP-CP(22)01
2021 IEEE Pulsed Power Conference & Symposium on Fusion Engineering (PPC/SOFE) NPSS, Denver, Colarado, USA, 12-16 December 2021

With the ITER project entering the second half of the construction phase and various national and international plans for fusion prototype power plants being in early to advanced stages, fusion has entered the delivery era. With the urgency of the climate crisis being at the forefront of government policy agendas it is important to focus on the com…

Preprint Published
2022
UKAEA-CCFE-CP(22)05
28th IAEA Fusion Energy Conference, Nice, France, 10-15th May 2021

A study of a dataset of JET H-mode plasma with the Be/W ITER-like wall (JET-ILW) shows that reaching the edge MHD ballooning limit leads to confinement degradation. However, unlike JET plasmas with a carbon wall (JET-C), the JET-ILW plasmas stay in a marginal dithering phase for a relatively long period, associated with a higher (20%) H-mode den…

Preprint Published
2022
UKAEA-CCFE-CP(22)04
2021 IEEE Pulsed Power Conference & Symposium on Fusion Engineering (PPC/SOFE) NPSS, Denver, Colarado, USA, 12-16 December 2021

The protection strategy adopted for the European DEMOnstration (EU-DEMO) fusion power reactor foresees the use of sacrificial components–referred to as limiters–dealing with plasma-wall contacts. Their aim is to protect the first wall (FW) against the huge amount of plasma energy (up to GigaJoules) released in a few milliseconds during disrupti…

Preprint Published
2022
UKAEA-CCFE-CP(22)03
Virtual Royal Society Conference on H-mode transition and pedestal studies in fusion plasmasa, 17-19 January 2022

Preprint
2020
UKAEA-CCFE-CP(22)02
28th IAEA Fusion Energy Conference, Nice, France, 10-15th May 2021

In the conceptual design of EU-DEMO, damage to plasma facing components under disruption events is planned to be mitigated by specific sacrificial limiter components. A new limiter concept has been proposed using lattice structures fabricated with tungsten powder by additive manufacturing techniques. The major potential benefits of using a latti…

Published