Showing 231 - 240 of 260 Conference Paper Results
2019
UKAEA-RACE-CP(19)01
IEEE/RSJ International Conference on Intelligent Robots and Systems, Macau, China, 3 - 8 November 2019
Daniel Butters Emil T. Jonasson Robert Stuart-Smith Vijay M. Pawar
Remote inspection of a complex environment is a difficult, time consuming task for human operators to perform. The need to manually avoid obstacles whilst considering other performance factors i.e. time taken, joint effort and information gained represents significant challenges to continuous operation. This paper proposes an autonomous robotic so…
Preprint Published2019
UKAEA-CCFE-CP(19)12
22nd Topical Conference on High Temperature Plasma Diagnostics (HTPD), San Diego, USA, 16-19 April 2018
J.F. Rivero-Rodriguez M. Garcia-Muñoz R. Martin J. Galdon-Quiroga J. Ayllon-Guerola R. J. Akers J. Buchanan D. Croft D. Garcia-Vallejo J. Gonzalez-Martin D. Harvey K.G. McClements M. Rodriguez-Ramos L. Sanchis-Sanchez the MAST Upgrade Team
The design and unique feature of the first MAST-U fast-ion loss detector (FILD) [M. Garcia-Muñoz, Rev. Sci. Instrum 80, 053503 (2009)] is presented here. The MAST-U FILD head is mounted on an axially and angularly actuated mechanism that makes…
Preprint Published2019
UKAEA-CCFE-CP(19)28
27th IAEA Fusion Energy Conference, Ahmedabad, India, 22-27 October 2018
N. Vianello D. Carralero C. K. Tsui V. Naulin M. Agostini J. Boedo B. Labit C. Theiler D. Aguiam S. Allan M. Bernert S. Costea I. Cziegler H. De Oliveira J. Galdon-Quiroga G. Grenfell A. Hakola C. Ionita H. Isliker A. Karpushov J. Kovacic B. Lipschultz R. Mauriozio K. McClements F. Militello J. Olsen J. J. Rasmussen T. Ravensbergen H. Reimerdes B. Schneider R. Schrittwieser M. Spolaore K. Verhaegh J. Vicente N. Walkden W. Zhang E. Wolfrum the ASDEX Upgrade Team the TCV team the EUROfusion MST1 Team
A detailed cross-device investigation on the role of filamentary dynamics in high density regimes has been performed within the EUROfusion framework comparing ASDEX-Upgrade (AUG) and TCV tokamaks. Both devices have run density ramp experiments at different levels of plasma current, keeping toroidal field or q95 constant in order to disentangle the …
Preprint Published2019
UKAEA-CCFE-CP(19)27
27th IAEA Fusion Energy Conference, Ahmedabad, India, 22-27 October 2018
F. Koechl S.D. Pinches F.J. Casson G. Corrigan Y. Gribov D. Harting A.A. Kavin R.R. Khayrutdinov S.-H. Kim P.J. Knight S.V. Konovalov A. Loarte V.E. Lukash S. Medvedev A.R. Polevoi
The ability to describe the essential physics and technology elements needed to robustly simulate the operation of ITER is critical to being able to model the plasma scenarios that will run in ITER. In this paper, the Integrated Modelling & Analysis Suite (IMAS) is used to simulate the 15 MA DT baseline scenario operation, including a descripti…
Preprint Published2019
UKAEA-CCFE-CP(19)26
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018
Iain Farquhar James Davies Oliver Crofts Tony Loving
One of the major challenge in the commercialisation of fusion is maintaining the powerplant reactor in a sufficiently short period of time to achieve commercial levels of plant availability. To inform the development of an appropriate remote maintenance strategy for EU DEMO, a simplified, parametric model, called the Maintenance Duration Estimator …
Preprint Published2019
UKAEA-CCFE-CP(19)25
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018
Mike Fursdon Jeong-Ha You Muyuan Li
The preferred design of the ITER divertor target component is the monoblock, comprising a tungsten armour block through which passes a CuCrZr cooling pipe which is joined to the tungsten via a copper interlayer. This construction currently looks to be one of the favoured designs for DEMO. Ideally this structure can be assessed for structural integr…
Preprint Published2019
UKAEA-CCFE-CP(19)24
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018
S. I. Muldrew H. Lux V. Menon R. Srinivasan
Systems codes assess the viability of fusion reactor designs by using simplified models for the entire reactor system that allow for the exploration of large areas of parameter space. However, every design will have an associated uncertainty that arises from the accuracy of the models used, the assumptions made and the values of input parameters ad…
Preprint Published2019
UKAEA-CCFE-CP(19)23
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018
A. Krimmer I. Balboa N. J. Conway M. De Bock S. Friese F. Le Guern N. C. Hawkes D. Kampf Y. Krasikov P. Mertens M. Mittwollen K. Mlynczak J. Oellerich G. Szarvas B. Weinhorst C. Linsmeier
The Charge eXchange Recombination Spectroscopy diagnostic system on the ITER plasma core (CXRS core) will provide spatially resolved measurements of plasma parameters. The optical front-end is located in upper port 3 and the light of 460 nm to 665 nm is routed to spectrometers housed in the tritium building. This paper describes the layout of the o…
Preprint Published2019
UKAEA-CCFE-CP(19)22
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018
Vaughan Thompson Russell Eaton Rene Raffray Konstantin Egorov
Remote maintenance in fusion machines such as JET and ITER relies on sliding interfaces such as bolted joints. Experience in JET, where removal torques much higher than installation values with uncoated bolts is commonplace, led to the installation of experimental bolted assemblies in 2015: the first of its kind in JET. These assemblies included so…
Preprint Published2019
UKAEA-CCFE-CP(19)21
23rd International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI), Princeton, NJ, USA, 17-22 June 2018