Conference Papers

Showing 11 - 20 of 124 Conference Paper Results
2020
UKAEA-CCFE-CP(20)90
28th IEEE Symposium on Fusion Engineering, Jacksonville, Florida, USA, 2 – 6 June 2019

Investment in past fusion experiments has been motivated largely by the study of tokamak physics, and has been vital to provide a sound physics basis for design of a power reactor. However, meeting the challenge of realising fusion energy production will require considerable and increasing investment in facilities for testing and development of fus…

Preprint Published
2020
UKAEA-CCFE-CP(20)91
14th International Reflectometry Workshop, Swiss Plasma Center of the Ecole Polytechnique Fédérale de Lausanne, Switzerland, 22-24 May 2019

The experimental validation of turbulence models is a critical part of developing a predictive understanding of plasma transport. Models based on the non-linear gyrokinetic equations are currently the most well understood and experimentally validated models of turbulence available. However, models of reduced complexity are required in order to mak…

Preprint Published
2020
UKAEA-CCFE-CP(20)92
45th European Physical Society Conference on Plasma Physics (EPS), Prague, 2-6 July 2018

Dimensionless identity experiments test the invariance of plasma physics to changes in the dimensional plasma parameters, e.g. ne and Te, when the dimensionless parameters are conserved [1] [2]. However, conditions at the plasma boundary, such as influx of neutral particles, may introduce additional physics. An isotope identity experiment was ca…

Preprint
2020
UKAEA-CCFE-CP(20)93
45th European Physical Society Conference on Plasma Physics (EPS), Prague, 2-6 July 2018

In 2009-2011 so-called ITER-like wall was installed on JET tokamak, with beryllium limiters and tungsten divertor. Change of the plasma facing materials from carbon to metallic had a significant effect on plasma operations and confinement. Achieving steady plasma performance has become more challenging due to impurity accumulation [1], which has pu…

Preprint
2020
UKAEA-CCFE-CP(20)94
45th European Physical Society Conference on Plasma Physics (EPS), Prague, 2-6 July 2018

Edge localised modes (ELMs) are magneto-hydrodynamic (MHD) instabilities that drive filamentary plasma eruptions in high confinement tokamak discharges [1]. Gaining an improved understanding of ELMs is important [2]; in future fusion reactors such as ITER, ELM heat fluxes will need to be limited to ensure durability of divertor materials [3]. A new…

Preprint Published
2020
UKAEA-CCFE-CP(20)95
45th European Physical Society Conference on Plasma Physics (EPS), Prague, 2-6 July 2018

Preprint
2020
UKAEA-CCFE-CP(20)88
27th IAEA Fusion Energy Conference, Ahmedabad, India, 22-27 October 2018

The ASDEX Upgrade (AUG) programme is geared towards developing the physics basis for ITER and (EU)-DEMO and is jointly executed with the EUROfusion Medium Size Tokamak task force. Integrated scenario development to prepare future device operation, detailed physics studies to improve predictability of fusion devices and testing of fusion relevant t…

Preprint Published
2020
UKAEA-CCFE-CP(20)87
PHYSOR 2020, University of Cambridge, United Kingdom, 29 March - 2 April 2020 - CANCELLED

Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, such as shielding, material lifetime and remote maintenance requirements/scheduling. Neutronics studies are performed using radiation transport codes such as MCNP, TRIP…

Preprint
2020
UKAEA-CCFE-CP(20)85
14th International Symposium on Fusion Nuclear Technology (ISFNT-14) Budapest,Hungary, 22-27 September 2019

The anticipated heat flux limit of the European DEMO first wall is ~1MW/m2. During transient and off normal events, the heat load deposited on the wall would be much larger than that the steady state heat load and exceed the first wall limit, therefore the breeding blanket first wall needs to be protected in such events. This involves de…

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The published version of this paper is currently under embargo and will be available on 24/04/2022
2020
UKAEA-RACE-CP(20)02
14th International Symposium on Fusion Nuclear Technology (ISFNT-14) Budapest,Hungary, 22-27 September 2019

As part of the development work performed under the ITER Robotic Test Facility (IRTF) the development and substantiation of the maintenance strategy for the Vacuum Vessel Pressure Suppression System (VVPSS) must be investigated. The VVPSS is a key safety aspect of the vacuum vessel of ITER. It ensures after a coolant leak, and subsequent pressure e…

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The published version of this paper is currently under embargo and will be available on 11/01/2022