Conference Papers

Showing 11 - 20 of 147 Conference Paper Results
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, but the…

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 tokamak experiments, considerations of the d…

Preprint Published
2018
UKAEA-CCFE-CP(20)107
International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering, Portland , USA, 25-29 August 2019

Validation and verification (V&V) benchmark exercises form an important part of the development and release of the FISPACT-II inventory code and its associated input nuclear data libraries. This paper describes the latest V&V based on the fusion decay heat measurements performed at the Japanese FNS facility. New and novel assessm…

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…

Preprint Published
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 s…

Preprint Published
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…

Preprint Purchase
2020
UKAEA-RACE-CP(20)04
CASE 2019 - International Conference on Automation Science and Engineering, University of British Columbia, Vancouver, BC, Canada, 22- 26 August 2019

The extreme environmental conditions inside future nuclear fusion power plants will mean that maintenance activities must be performed without human access. Current teleoperation paradigms do not enable sufficiently fast maintenance cycles, and automation is seen as a potential solution. Transitioning to an automated maintenance scheme will requ…

Preprint
2020
UKAEA-CCFE-CP(20)113
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), South Korea, 24 - 29 January 2021

EDGE2D-EIRENE simulations show that for a H-mode JET discharge (92168) the dominant atomic neutral deuterium source at the separatrix originates from the inner divertor target. Within JETTO-EIRENE neutral sources are placed at the X-point and outer midplane (OMP). For fixed electron and ion temperature, transport and neutral temperature it is obser…

Preprint
2020
UKAEA-CCFE-CP(20)114
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018

High heat flux testing is a vital part of engineering component validation for fusion technology. Typically, it is an expensive process that is both time and resource intensive. The Heat by Induction to Verify Extremes (HIVE) facility is designed to improve the practicalities of this form of component testing. It provides a faster turnaround for…

Preprint
2020
UKAEA-CCFE-CP(20)115
14th International Symposium on Fusion Nuclear Technology (ISFNT-14) Budapest

Since the 1960’s computer-aided design (CAD) has been at the forefront of engineering. Originally and literally quite a broad term, “CAD” appears to have narrowed in definition, and is nowadays usually used to refer to three-dimensional (3-D) geometric models. Such 3-D CAD models are the currency of modern engineering, enabling a wide variety…

Preprint