Conference Papers

Showing 1 - 10 of 145 Conference Paper Results
2020
UKAEA-CCFE-CP(20)124
14th International Symposium on Fusion Nuclear Technology (ISFNT-14) Budapest,Hungary, 22-27 September 2019

During ITER operations the water coolant flowing through components such as the first wall, blanket modules, divertor cassettes and vacuum vessel will become activated by high energy neutrons. Two key neutron-induced reactions will occur with oxygen in the water producing the radioactive isotopes, N-16 and N-17, which have relatively short half-liv…

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The published version of this paper is currently under embargo and will be available on 17/06/2022
2020
UKAEA-CCFE-CP(20)123
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), South Korea, 24 - 29 January 2021

Preprint
2020
UKAEA-CCFE-CP(20)120
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018

The divertor component is subject to some of the most extreme loading conditions in a fusion environment and the safety design window is relatively narrow. Variation in mechanical properties of the same material throughout a component is common place in practice and can be caused by both local effects of processing and joining, and local variations…

Preprint
2020
UKAEA-CCFE-CP(20)121
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), South Korea, 24 - 29 January 2021

While current tokamak experiments are beginning to utilise real-time feedback control systems to manage the plasma exhaust, future tokamaks still require validation of theoretical models used to predict the threshold impurity concentration required to facilitate stationary divertor operation. This work exploits new spectroscopic measurements of the…

Preprint
2020
UKAEA-CCFE-CP(20)122
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), South Korea, 24 - 29 January 2021

A thorough physics and engineering analysis of alternative divertor configurations is carried out by examining benefits and problems by comparing the baseline single null solution with a Snowflake, an X- and a Super-X divertor. It is observed that alternative configurations can provide margin and resilience against large power fluctuations, bu…

Preprint
2020
UKAEA-CCFE-CP(20)106
14th International Symposium on Fusion Nuclear Technology (ISFNT-14) Budapest,Hungary, 22-27 September 2019

The measurement of the fusion neutron yield provides a direct relationship with fusion power and is hence an important measure of experimental performance. In pulsed neutron emission scenarios, such as those experienced in dense plasma focus devices, inertial confinement fusion and even in short-pulse to…

Preprint Published
2020
UKAEA-CCFE-CP(20)107
International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering, Portland , USA, 25-29 August 2019

Preprint Published
2020
UKAEA-CCFE-CP(20)109
23rd Topical Conference on Radiofrequency Power in Plasmas, Hefei, China, 14-17 May 2019

Understanding the impact of the synergistic effects on fast ion distribution function (DF) is essential for maximising the fusion rates in magnetic confinement fusion plasma. Because fusion reactions such as D-D, D-3He, D-T etc. have different energy dependencies, tailoring the energies of the fast ions to predetermined values optimal for fusion ge…

Preprint
2020
UKAEA-CCFE-CP(20)111
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018

The Mega Amp Spherical Tokamak (MAST) is currently being extensively upgraded to provide a system that will be able to add to the knowledge base for ITER as well as testing innovative reactor systems such as the Super-X divertor. MAST-U will have increased coil system and power supply capability. Therefore, to ensure operation of MAST-U within safe…

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2020
UKAEA-CCFE-CP(20)112
17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven, The Netherlands, 20-24 May 2019

Understanding of fuel retention and release processes from plasma facing components (PFCs) of ITER like wall materials is important from fundamental and technological aspects [1]. Detailed information about fuel retention and release characteristics in plasma facing components from JET will allow gl…

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The published version of this paper is currently under embargo and will be available on 26/02/2021