J. Simpson D. Moulton C. Giroud F. Casson M. Groth A. Chankin L. Horvath D. S. Gahle F. Kochl
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…
Preprint PublishedK Flinders R Bamber H Lewtas D Hancock D Homfray J Kamalu T Barrett
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…
Preprint PublishedR.A. Tinguely P.G. Puglia N. Fil S. Dowson M. Porkolab A. Dvornova A. Fasoli M. Fitzgerald G.T.A. Huysmans M. Maslov S. Sharapov D. Testa JET Contributors
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 …
Preprint PublishedR. F. Knights J. Benayas K. Sabin S. Ng A. Wohlers T. Tijssen D. Demange S. Willms D. Brennan
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…
Preprint PublishedT.L. Martin A.D. Warren D. Kumar A. Siberry R. Springell R. Holmes R. Clark L. Platts R. Burrows C. Harrington M. Gorley E. Surrey S. Rowthu P. Grundler S. Ritter
The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reac…
Preprint PublishedE. Organ S. Ha J. Holt G. Keech J. Keep C. Shaw A. Wilde
A study into the viability of a double null concept for DEMO has been undertaken as part of the work to address Key Design Integration Issues (KDIIs) within the DEMO powerplant. The objective of this study was to evaluate the feasibility of a double null architecture, featuring split blanket segments to enable a wider range of maintenance options…
PreprintJohn Waterhouse
The JET control and data acquisition system (CODAS) is an integrated system that provides all the pulse based and continuous data acquisition, real time and slow control and control room interfaces for JET. It has a long history, dating back to the beginning of JET in 1980. It utilises both commercially available hardware along with many in-house m…
Preprint PublishedK D Lawson I H Coffey F Rimini I Ksiazek
Divertor Monitoring Pulses (DiMPle) have been run in JET from the C35 campaign onwards. They provide an opportunity to study the impurity contamination of the plasma when it is limited by different surfaces within the machine, as well as the longer term behaviour of the impurities. In these discharges the plasma is first limited on the outer wall, …
Preprint PublishedRobert Skilton Guy Burroughes Matt Goodliffe
Future experimental scientific facilities, energy generation assets, and nuclear decommissioning facilities will require increasing levels of remote maintenance, which must be facilitated by robotic systems. Moreover, these long-lived (30+ years) maintenance systems will, themselves need to maintained and upgraded in order to deal with lifespan …
PreprintH.E. Coules S. O. Nneji J. A. James S. Kabra J. N. Hu Y. Wang
Mechanical constitutive models of metals undergoing deformation in three dimensions can be challenging to validate without loss of generality. For example, creep-induced stress relaxation in stainless steels has previously been studied using axisymmetric notched-bar tests which control the triaxiality of the initial stress state. However, such expe…
Preprint Published