Showing 131 - 140 of 260 Conference Paper Results
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
Liga Avotina Anna Widdowson Ionut Jepu Aleksandra Baron-Wiechec Gunta Kizane JET Contributors
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 Published2020
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
Samuel Jimenez Guy Burroughes
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…
Preprint2020
UKAEA-CCFE-CP(20)113
24th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), South Korea, 24 - 29 January 2021
J. Simpson D. Moulton C. Giroud F. Casson M. Groth A. Chankin L. Horvath D. S. Gahle F. Kochl
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 Published2020
UKAEA-CCFE-CP(20)114
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018
K Flinders R Bamber H Lewtas D Hancock D Homfray J Kamalu T Barrett
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 Published2020
UKAEA-CCFE-CP(20)116
31st Symposium on Fusion Technology (SOFT), Dubrovnik, Croatia, 20 - 25 September 2020
R. F. Knights J. Benayas K. Sabin S. Ng A. Wohlers T. Tijssen D. Demange S. Willms D. Brennan
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 Published2020
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
T.L. Martin A.D. Warren D. Kumar A. Siberry R. Springell R. Holmes R. Clark L. Platts R. Burrows C. Harrington M. Gorley E. Surrey S. Rowthu P. Grundler S. Ritter
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 Published2020
UKAEA-CCFE-CP(20)118
31st Symposium on Fusion Technology (SOFT)
E. Organ S. Ha J. Holt G. Keech J. Keep C. Shaw A. Wilde
A study into the viability of a double null concept for DEMO has been undertaken as part of the work to address Key Design Integration Issues (KDIIs) within the DEMO powerplant. The objective of this study was to evaluate the feasibility of a double null architecture, featuring split blanket segments to enable a wider range of maintenance options…
Preprint2020
UKAEA-CCFE-CP(20)119
12th IAEA Technical Meeting on Control, Data Acquisition and Remote Participation for Fusion Research, Daejeon, Republic of Korea, 13-17 May 2019
John Waterhouse
The JET control and data acquisition system (CODAS) is an integrated system that provides all the pulse based and continuous data acquisition, real time and slow control and control room interfaces for JET. It has a long history, dating back to the beginning of JET in 1980. It utilises both commercially available hardware along with many in-house m…
Preprint Published2020
UKAEA-RACE-CP(20)03
International Conference on Intelligent Robots and Systems (IROS), 25-29 October 2020, Las Vegas, USA
Salua Hamaza André Farinha Hai-Nguyen Nguyen Mirko Kovac
Research into remote sensing tools for environmentalmonitoring is an essential aspect for ensuring a healthy anthriving biosphere under the canopy, but also for preventingforest-related hazards from occurring. The challenges associatedwith forestry robotics are posed by the environment itself, asforests are wide-spread areas with a high density …
Preprint Published2020
UKAEA-CCFE-CP(20)108
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018