UKAEA Papers

"Overview of fuel retention and recovery in JET DT operation"

• A. Widdowson
• S. Brezinsek
• T. Dittmar
• D. Douai
• R. Felton
• G. Gervasini
• M. Hook
• I. Jepu
• R. Knipe
• D. Kos
• L. Laguardia
• D. Matveev
• M.-L. Mayoral
• P. Papadopoulos
• A. Peacock
• R. Rayaprolu
• G. Sergienko
• S. Silburn
• P. Staniec
• H. Sun
• A. Tookey
• R. Walker
• H. Weisen
• A. Wilcox
• R. Yi
• Y. Zayachuk
• M. Zlobinski
• Y. Corre
• A. Hakola
• E. Joffrin
• K. Krieger
• E. Tsitrone
• JET Contributors

Tritium inventory build-up is a safety issue for next step devices. JET brings a unique contribution on fuel retention and recovery in a metallic device, as it has operated both in deuterium (D) and deuterium-tritium (DT) plasmas. This paper will provide an overview of results from JET in this fi…

"The composition of ETG turbulence in JET-ILW pedestals"

• B. Chapman-Oplopoiou
• J. Walker
• D.R. Hatch
• T. Görler

We compare the structure of electron temperature gradient (ETG) driven turbulence in the pedestals of two JET ITER-like-wall (ILW) type I ELMy H-mode discharges operating with similar experimental inputs but at different levels of gas fuelling. By artificially removing the toroidal drifts from our GENE gyrokinetic simulations and subsequently an…

"LOCUST-GPU predictions of fast-ion transport and power loads due to ELM-control coils in ITER"

• S. H. Ward
• R. Akers
• S. D. Pinches
• A. Loarte
• R. G. L. Vann
• M. A. Van Zeeland
• L. Li
• Y. Liu
• A. Polevoi

The LOCUST GPU code has been applied to study the fast-ion transport caused by resonant magnetic perturbations in the high-performance Q = 10 ITER baseline scenario. The computational speed of the code is used calculate the impact of the ITER ELM-control-coil system on neutral beam heating efficiency, as well as producing detailed predictions o…

"Reduced models for ETG transport in the tokamak pedestal"

• D. R. Hatch
• C. Michoski
• D. Kuang
• B.Chapman-Oplopoiou
• M. Curie
• M. Halfmoon
• E.Hassan
• M. Kotschenreuther
• S. M. Mahajan
• G. Merlo
• M.J. Pueschel
• J. Walker
• C. D. Stephens

This paper reports on the development of reduced models for electron temperature gradient (ETG) driven transport in the pedestal. Model development is enabled by a set of 61 nonlinear gyrokinetic simulations with input parameters taken from the pedestals in a broad range of experimental scenarios. The simulation data has been consolidated in a new …

"The role of slab-ETG modes in JET-ILW pedestals with varying levels of power and fuelling"

• B. Chapman
• D.R. Hatch
• A.R. Field
• L. Frassinetti
• J.C. Hillesheim
• L. Horvath
• C.F. Maggi
• J. F. Parisi
• C.M. Roach
• S.Saarelma
• J. Walker
• JET contributors

We present the results of GENE gyrokinetic calculations based on a series of JET-ILW type I ELMy H-mode discharges operating with similar experimental inputsbut at different levels of power and gas fuelling. We show that turbulence due to slab electron-temperature-gradient modes (sETGs) produces a significant amount of heat flux in four JET-ILW …

"Verification and validation of the high-performance Lorentz-Orbit Code for Use in Stellarators and Tokamaks (LOCUST)"

• S. H. Ward
• R. Akers
• A. Jacobsen
• P. Ollus
• S. D. Pinches
• E. Tholerus
• R. G. L. Vann
• M. A. Van Zeeland

A novel high-performance computing algorithm, developed in response to the next generation of computational challenges associated with burning plasma regimes in ITER-scale tokamak devices, has been tested and is described herein. LOCUST-GPU 2 The Lorentz-Orbit Code for Use in Stellarators and Tokamaks (LOCUST) is designed for computationally scal…

"Validation and sensitivity of CFETR design using EU systems codes"

• J. Morris
• M. Y. Ye
• S. Mao

The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…

"The cusp compression of colliding plasma blobs"

• TK Allen
• K Doble
• TJL Jones
• RM Payne
• IJ Spalding

"The energy spectra of the neutrons from zeta"

• RA Coombe
• BA Ward

"The MAST Upgrade Plasma Control System"

• G. J. McArdle
• L. Pangione
• M. Kochan

MAST has undergone a substantial upgrade [1], featuring among other things several new poloidal field coils mostly distributed around the new closed-throat divertor structure and an enlarged centre column. The considerable changes have required the plasma control software to be substantially re-written. The MAST digital plasma control system […