-
UKAEA-CCFE-PR(20)1242018
NBI-heated L-mode plasmas have been obtained in JET with the Be/W ITER-like wall (JET-ILW) in H and D, with matched profiles of the dimensionless plasma parameters in the plasma core confinement region and same Ti/Te and Zeff. The achieved isotope identity indicates that the confinement scale invariance principle is satisfied in the core confine…
-
UKAEA-CCFE-PR(20)1272019
The self-consistent core-pedestal prediction model of a combination of EPED1 type pedestal prediction and a simple stiff core transport model is able to predict type I ELMy pedestals of a large database JET-ILW (ITER-like wall) at the similar accuracy as is obtained when the experimental global plasma b is used as input. The neutral penetration …
-
UKAEA-CCFE-CP(20)1092020
Understanding the impact of the synergistic effects on fast ion distribution function (DF) is essential for maximising the fusion rates in magnetic confinement fusion plasma. Because fusion reactions such as D-D, D-3He, D-T etc. have different energy dependencies, tailoring the energies of the fast ions to predetermined values optimal for fusion…
-
UKAEA-CCFE-CP(20)1112020
The Mega Amp Spherical Tokamak (MAST) is currently being extensively upgraded to provide a system that will be able to add to the knowledge base for ITER as well as testing innovative reactor systems such as the Super-X divertor. MAST-U will have increased coil system and power supply capability. Therefore, to ensure operation of MAST-U within safe…
-
UKAEA-CCFE-CP(20)1122020
Understanding of fuel retention and release processes from plasma facing components (PFCs) of ITER like wall materials is important from fundamental and technological aspects [1]. Detailed information about fuel retention and release characteristics in plasma facing components from JET will allow…
-
UKAEA-RACE-CP(20)042020
The extreme environmental conditions inside future nuclear fusion power plants will mean that maintenance activities must be performed without human access. Current teleoperation paradigms do not enable sufficiently fast maintenance cycles, and automation is seen as a potential solution. Transitioning to an automated maintenance scheme will requ…
-
UKAEA-CCFE-CP(20)1132020
EDGE2D-EIRENE simulations show that for a H-mode JET discharge (92168) the dominant atomic neutral deuterium source at the separatrix originates from the inner divertor target. Within JETTO-EIRENE neutral sources are placed at the X-point and outer midplane (OMP). For fixed electron and ion temperature, transport and neutral temperature it is obser…
-
UKAEA-CCFE-CP(20)1142020
High heat flux testing is a vital part of engineering component validation for fusion technology. Typically, it is an expensive process that is both time and resource intensive. The Heat by Induction to Verify Extremes (HIVE) facility is designed to improve the practicalities of this form of component testing. It provides a faster turnaround for…
-
UKAEA-CCFE-PR(20)1312020
This paper presents a dedicated study of plasma-antenna (PA) coupling with the Alfvén Eigenmode Active Diagnostic (AEAD) in JET. Stable AEs and their resonant frequencies f, damping rates < 0, and toroidal mode numbers n are measured for various PA separations and limiter versus X-point magnetic cofigurations. Two stable AEs are observed to be …
-
UKAEA-CCFE-CP(20)1162020
The ITER Tokamak Exhaust Processing (TEP) system relies on palladium membrane reactors (PMRs) for tritium recovery. The PMR consists of a palladium/silver membrane permeator filled with a catalyst, that can be used to recover hydrogen species (most importantly tritium) from methane and water impurities present in fusion reactor exhaust emissions…
Showing 811 - 820 of 2527 UKAEA Paper Results