Showing 151 - 159 of 159 Conference Paper Results
2019
UKAEA-CCFE-CP(19)08
22nd Topical Conference on High Temperature Plasma Diagnostics (HTPD), San Diego, USA, 16-19 April 2018
N. C. Hawkes E. Delabie S. Menmuir C. Giroud A. Meigs N. Conway T. M. Biewer D. L. Hillis
Charge-exchange spectroscopy on JET has become particularly challenging with the introduction of the ITER-like wall. The impurity spectra are weaker and contaminated by many tungsten lines. We have therefore upgraded the instrumentation to allow the simultaneous measurement of impurity and fuel-ion charge exchange by splitting the light between two…
Preprint Published2019
UKAEA-CCFE-CP(19)07
ICVRAM - ISUMA UNCERTAINTIES, Florianoplis, Brazil, 8-11 April 2018
Dominic C Calleja Wayne Arter Marco De-Angelis Edoardo Patelli
Nuclear fusion, the process by which the Sun generates energy, is proposed as one solution to secure the future of global energy supply. If successful it will provide an unlimited source of clean energy. Probably the most promising approach to harnessing fusion for energy production is that of the Tokamak device, a magnetic confinement device of to…
Published2019
UKAEA-CCFE-CP(19)06
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018
Maria Lorena Richiusa Daniel Iglesias Guy F. Matthews Michael Porton Vaughan K. Thompson Zsolt Vizvary
The next D-T campaign will push JET ITER-like Wall (IWL) to high divertor power and energy levels. During the 2016 campaign, the Strike Point (SP) sweeping permitted relevant H-mode scenarios without exceeding the temperature limits imposed by JET Operation Instructions (JOIs). In the subsequent shutdown, six outer divertor tungsten-coated 2D carbo…
Preprint Published2019
UKAEA-CCFE-CP(19)05
Waste Management Symposia (WMS), Phoenix, USA, 18-22 March 2018
Guy Burroughes Rob Skilton Jean-Jacque Honore Rob Buckingham
This paper presents the methodology and results of developing and implementing a system-of-systems architecture for controlling many robotic systems within the context of industrial facilities, where the life of the facility will be far longer than the life of the robotics, due to software updates and accelerated digital obsolescence. The use cases…
Preprint Published2019
UKAEA-CCFE-CP(19)04
27th IAEA Fusion Energy Conference, Ahmedabad, India, 22-27 October 2018
M.R. Gilbert T. Eade C. Bachmann U. Fischer N.P. Taylor
Waste-production predictions for the future demonstration fusion power plant (DEMO) are necessary to produce an accurate picture of the likely environmental and economic costs of radioactive waste disposal at end-of-life (EOL). Even during the conceptual stage of DEMO design it is important to perform waste assessment so as to avoid potential surpr…
Preprint Published2019
UKAEA-CCFE-CP(19)03
UK-RAS Network Conference on Robotics and Autonomous Systems: robots working for and among us, Bristol, UK, 12 December 2018
Guy Burroughes
The European Spallation Source (ESS) is a multi-disciplinary research facility which will be the world’s most powerful pulsed neutron source. A critical component of ESS will be a facility for handling radioactive waste and preparing it for safe disposal. Safe disposal of ESS waste requires the dexterous tele-manipulation of large, highly activat…
Preprint Published2019
UKAEA-CCFE-CP(19)02
Waste Management Symposia (WMS), Phoenix, USA, 18-22 March 2018
Barry Preston Guy Burroughes Matt Goodliffe Rob Skilton
Nuclear decommissioning environments are challenging and hazardous, typically involving high temperatures, pressures and extreme radiation. Robotic devices are commonly used to complete tasks within challenging environments, which would otherwise pose a risk to human health, however remotely operating robots without full three-dimensional vision is…
Preprint Published2019
UKAEA-CCFE-CP(19)01
Waste Management Symposia (WMS), Phoenix, USA, 18-22 March 2018
S. Kirk K. Keogh W. Suder T. Tremethick C. Allen I. Farquhar
The maintenance, replacement and decommissioning of future nuclear fusion reactors will require quick and reliable cutting and joining of in-vessel pipework. Initial design studies for nuclear fusion reactors for power generation have estimated cutting and welding could account for up to 60% of the maintenance duration using conventional in-situ pr…
Preprint Published2017
CCFE-PR(17)10
2017 ANS Annual Meeting, San Francisco, USA, 11-15 June 2017