Conference Papers

Showing 151 - 160 of 260 Conference Paper Results
2018
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 identit…

Preprint Published
2018
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 Published
2018
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 …

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

Preprint Published
2018
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
2019
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 Published
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…

Preprint Published
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…

Preprint Published
2018
UKAEA-CCFE-CP(20)86
NAFEMS World Congress 2019, Quebec City, Canada, 17-20 June 2019

Nuclear fusion is the process that heats the stars by the collision of atomic nuclei which fuse together to form heavier elements and release energy. The generation of energy using this process has several advantages: no carbon emissions, abundant fuel supplies, efficiency, reliability and operationally safe. One way to achieve the necessary con…

Preprint Published
2019
UKAEA-CCFE-CP(20)84
17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven, The Netherlands, 20-24 May 2019

JET has now completed three operating periods, ILW1, ILW2 and ILW3, giving an opportunity to make comparisons between tiles exposed for single operating periods and also comparisons of tiles exposed for all three periods, ILW1-3 (2011-2016). In this contribution, a comprehensive overview of fuel retention and material erosion/deposition patterns…

Preprint Published