Conference Papers

Showing 21 - 30 of 155 Conference Paper Results
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 Published
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 Purchase
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
2020
UKAEA-CCFE-CP(20)116
31st Symposium on Fusion Technology (SOFT), Dubrovnik, Croatia, 20 - 25 September 2020

The ITER Tokamak Exhaust Processing (TEP) system relies on palladium membrane reactors (PMRs) for tritium recovery. The PMR consists of a palladium/silver membrane permeator filled with a catalyst, that can be used to recover hydrogen species (most importantly tritium) from methane and water impurities present in fusion reactor exhaust emissions…

Preprint
2020
UKAEA-CCFE-CP(20)117
19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Boston, MA, USA,18-22 August 2019

The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reac…

Preprint