-
UKAEA-CCFE-CP(24)132024
An overview of the modelling approaches, validation methods and recent main results of analysis and modelling activities related to the plasma-wall interaction in JET-ILW experiments, including the recent H/D/T campaigns is presented in the paper. Code applications to JET-ILW experiments improve general erosion/migration/retention prediction cap…
-
UKAEA-CCFE-PR(24)2472023
The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challeng…
-
UKAEA-CCFE-PR(23)1702023
Neutral Beam Injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed DeuteriumTritium Experimental campaign (DTE2) on the JET device. High NBI power was required for high fusion yield and alpha particle studies and to …
-
UKAEA-CCFE-PR(23)102022
The fusion-born alpha-particle heating in magnetically confined fusion machines is a high priority subject for study. The self-heating of thermonuclear fusion plasma by alpha-particles was observed in recent deuterium-tritium (D-T) experiments on the Joint European Torus (JET). This observation was possible by conducting so-called “af…
-
UKAEA-CCFE-PR(22)312022
Unusually high power loads on the Beryllium limiter caused by Neutral Beam re-ionisation, and much cooler divertor target surfaces were observed during the recent JET tritium campaign. As both phenomena are driven by scrape-off layer (SOL) physics, the SOL features of 72 tritium H-mode discharges and their deuterium references have been studied. …
-
UKAEA-CCFE-CP(21)122021
This contribution outlines a strategy for assessing tritium (T) inventory in plasma facing components (PFC) during JET T operations. It is based on retention as a fraction of fuel injected in-vessel, currently reported as 0.24% for 2011-2012 operating period, in conjunction with the planned T pulse schedule providing fueling of 4 g T injected per d…
Showing 1 - 6 of 6 UKAEA Paper Results
Page 1 of 1