Conference Papers

Showing 1 - 6 of 6 Conference Paper Results
2020
UKAEA-CCFE-CP(20)104
27th IAEA Fusion Energy Conference, Ahmedabad, India, 22-27 October 2018

During the pre-conceptual design phase of fusion devices such as the European demonstration fusion power plant (DEMO), systems codes provide a fast evaluation of optimal design points and highlight high impact areas. However, determining or evaluating a design point at such an early stage comes with uncertainties in many of the design parameters…

Preprint Published
2020
UKAEA-CCFE-CP(20)89
28th IEEE Symposium on Fusion Engineering, Jacksonville, Florida, USA, 2 – 6 June 2019

The EUROfusion Roadmap for fusion research was recently updated and describes a clear set of missions and associated goals on the route to commercial fusion electricity. Beyond ITER, the main target of the programme is the development of DEMO, a fusion technology demonstrator which will produce substantial net electrical output, breed its own fu…

Preprint Published
2020
UKAEA-CCFE-CP(20)79
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018

The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…

Preprint Published
2020
UKAEA-CCFE-CP(19)37
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019

As conceptual design options for a demonstration fusion power plant (DEMO) are explored it is important to understand the design space for possible non-ITER like design options. The power exhaust is a key design driver for a fusion power plant, and puts strong constraints on the size of the machine. One candidate for a alternative design is a do…

Preprint
2019
UKAEA-CCFE-CP(19)54
28th IEEE Symposium on Fusion Engineering, Jacksonville, Florida, USA, 2 – 6 June 2019

Protecting the divertor in a nuclear fusion power plant is a key criteria for operation. Detailed divertor and scrape-off-layer (SOL) modelling is computationally intensive and unsuitable for a systems code. For the use of such models in systems codes they need to be simplified and made computationally fast, while still capturing the most important…

Preprint Published
2019
UKAEA-CCFE-CP(19)44
12th IAEA Technical Meeting on Control, Data Acquisition and Remote Participation for Fusion Research, Daejeon, Republic of Korea, 13-17 May 2019

MAST has undergone a substantial upgrade [1], featuring among other things several new poloidal field coils mostly distributed around the new closed-throat divertor structure and an enlarged centre column. The considerable changes have required the plasma control software to be substantially re-written. The MAST digital plasma control system […

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