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Showing 1 - 10 of 86 UKAEA Paper Results

UKAEA-STEP-PR(24)142024

"The Spherical Tokamak for Energy Production: Theme Issue Introduction"
This theme issue collects together papers summarising the conceptual design of the Spherical Tokamak for Energy Production (STEP). In 2019, the UK government funded the first design stages of a prototype fusion powerplant based on a compact toroidal geometry, called STEP. The primary technical aims of STEP are to produce net energy, to be self-s…
- Purchase
UKAEA-STEP-PR(24)082024

"Determining Aqueous Deuterium Detection Limits via Infrared Spectroscopy to Understand its Capabilities for Real-Time Monitoring of Tritiated Water"
- A. Cooper
- T. Stokes
- M. Irwin
- E. Dixon
- A. Wilson
- G. Cefali
Tritiated water will be present in many demonstrator class fusion devices in a wide array of locations and concentrations. Accurate and fast measurement will be a key requirement to ensure suitable process monitoring, safety assurance and tritium tracking is in place. This work quantifies the deuterium detection limits achievable using a bench…
- Published
UKAEA-CCFE-PR(24)2162023

"Observation of new pedestal regime for MAST Upgrade H-mode plasmas"
The first pedestal stability analysis on the new MAST Upgrade (MASTU) spherical tokamak H-mode plasma is presented. Our results indicate that MAST-U pedestals are close to the low toroidal mode number (n) peeling branch of the peelingballooning instability, in contrast with MAST H-mode pedestals which were deeply in the high-n ballooning branch. Th…
- Preprint
- Published
UKAEA-CCFE-PR(23)1802023

"L-H transition studies in recent Tritium and Deuterium-Tritium campaigns at JET"
- E.R. Solano
- G. Birkenmeier
- C. Silva
- E. Delabie
- J.C. Hillesheim
- A. Baciero
- I. Balboa
- M. Baruzzo
- A. Boboc
- M. Brix
- C. Bourdelle
- I.S. Carvalho
- P. Carvalho
- C.D. Challis
- M. Chernyshova
- A. Chomiczewska
- R. Coelho
- T. Craciunescu
- E. de la Cal
- E. de la Luna
- R. Dumont
- P. Dumortier
- M. Fontana
- J.M. Fontdecaba
- L. Frassinetti
- D. Gallart
- J. Garcia
- C. Giroud
- W. Gromelski
- R.B. Henriques
- J. Hall
- A. Ho
- L. Horvath
- P. Jacquet
- I. Jepu
- E. Joffrin
- A. Kappatou
- P.J. Lomas
- D.L. Keeling
- D.B. King
- E. Kowalska-Strzęciwilk
- M. Lennholm
- E. Lerche
- E. Litherland-Smith
- V.G. Kiptily
- K.K. Kirov
- A. Loarte
- B. Lomanowski
- C.F. Maggi
- J. Mailloux
- M.J. Mantsinen
- M. Maslov
- A.G. Meigs
- I. Monakhov
- R.B. Morales
- A.H. Nielsen
- D. Nina
- C. Noble
- E. Pawelec
- M. Poradzinski
- G. Pucella
- P. Puglia
- D. Réfy
- J.J. Rasmussen
- E. Righi-Steele
- F.G. Rimini
- T. Robinson
- M. Sertoli
- S.A. Silburn
- P. Sirén
- Ž. Štancar
- H.J. Sun
- G. Szepesi
- D. Taylor
- B. Thomas
- E. Tholerus
- G. Verdoolaege
- P. Vincenzi
- B. Viola
- N. Vianello
- T. Wilson
- Preprint
- Published
UKAEA-CCFE-PR(23)1702023

"Tritium Neutral Beam Injection on JET: Calibration and Plasma Measurements"
- D.B. King
- R. Sharma
- C.D. Challis
- A. Bleasdal
- E.G. Delabie
- D. Douai
- D. Keeling
- E. Lerche
- M.Lennholm
- J. Mailloux
- G. Matthews
- M. Nicassio
- Z. Stancar
- T. Wilson
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 …
- Preprint
- Published
UKAEA-CCFE-PR(23)1672023

"Drift kinetic theory of neoclassical tearing modes in tokamak plasmas: polarisation current and its effect on magnetic island threshold physics"
- A V Dudkovskaia
- J W Connor
- D Dickinson
- P Hill
- K Imada
- S Leigh
- H R Wilson
A nonlinear 4-dimensional drift island theory derived in (Imada et al 2019 Nucl. Fusion 59 046016 and references therein) provides qualitative predictions of the plasma response to a stationary neoclassical tearing mode (NTM) magnetic island in a low beta, large aspect ratio tokamak plasma. (Dudkovskaia et al 2021 Plasma Phys. Control. Fusion 63 05…
- Published
UKAEA-STEP-CP(24)022022

"Microwave current drive for STEP and MAST Upgrade"
The UK’s Spherical Tokamak for Energy Production (STEP) reactor design program has recently taken the decision to use exclusively microwave-based heating and current drive (HCD) actuators for its reactor concepts. This is based on a detailed assessment considering all viable HCD concepts, covering the grid to plasma efficiency (), physics applica…
- Published
UKAEA-CCFE-PR(23)1882022

"Mitigation of disruption electro-magnetic load with SPI on JET"
- S.N.Gerasimov
- L.R.Baylor
- A.Boboc
- I.S.Carvalho
- P.Carvalho
- I.H.Coffey
- D.Craven
- J.Flanagan
- A.Huber
- V.Huber
- S.Jachmich
- I.Jepu
- E.Joffrin
- D.Kos
- S.I.Krasheninnikov
- U.Kruezi
- M.Lehnen
- P.J.Lomas
- A.Manzanares
- M.Maslov
- A.Peacock
- P.Puglia
- S.Silburn
- F.G.Rimini
- R.D.Smirnov
- D.Shiraki
- C.Stuart
- H.Sun
- J.Wilson
- L.E.Zakharov
- JET Contributors
In 2019, the JET-ILW was equipped with a Shattered Pellet Injector (SPI) system with a wide capability to allow studies on the efficacy of shattered pellets in reducing the electro-magnetic and the thermal loads during disruptions and the avoidance/suppression of the formation of runaway electrons. The fully commissioned system became operationa…
- Preprint
UKAEA-STEP-CP(23)072022

"The Physics of the Preferred Plasma Scenario for STEP"
- Hendrik Meyer
- the STEP Plasma Control Heating & Current Drive Team
With steady progress on ITER project and the design of DEMO, the international community is now entering an era in which fusion power on the grid could become a reality within the next 20 – 30 years. In this environment the UK has started the ambitious Spherical Tokamak for Energy Production (STEP) programme, aiming to develop a compact protot…
- Preprint
UKAEA-STEP-CP(23)052022

"Electron Bernstein Wave (EBW) current drive profiles and efficiency for STEP"
The UK’s Spherical Tokamak for Energy Production (STEP) reactor design program is now exclusively investigating concepts using microwave-based heating and current drive (HCD) systems. Electron Bernstein Wave (EBW) HCD is a relatively immature technology compared to Electron Cyclotron (EC) HCD but is of interest due to the promise of high current…
- Preprint

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UKAEA Papers

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"The Spherical Tokamak for Energy Production: Theme Issue Introduction"

"Determining Aqueous Deuterium Detection Limits via Infrared Spectroscopy to Understand its Capabilities for Real-Time Monitoring of Tritiated Water"

"Observation of new pedestal regime for MAST Upgrade H-mode plasmas"

"L-H transition studies in recent Tritium and Deuterium-Tritium campaigns at JET"

"Tritium Neutral Beam Injection on JET: Calibration and Plasma Measurements"

"Drift kinetic theory of neoclassical tearing modes in tokamak plasmas: polarisation current and its effect on magnetic island threshold physics"

"Microwave current drive for STEP and MAST Upgrade"

"Mitigation of disruption electro-magnetic load with SPI on JET"

"The Physics of the Preferred Plasma Scenario for STEP"

"Electron Bernstein Wave (EBW) current drive profiles and efficiency for STEP"

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