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
H. Lux M. Morgan M. Siccinio W. Biel G. Federici R. Kembleton A. W. Morris E. Patelli H. Zohm
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 Published2020
UKAEA-CCFE-CP(20)89
28th IEEE Symposium on Fusion Engineering, Jacksonville, Florida, USA, 2 – 6 June 2019
R. Kembleton W. Morris G. Federicia A. J. H. Donné
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 Published2020
UKAEA-CCFE-CP(20)79
30th Symposium on Fusion Technology (SOFT), Giardini Naxos, Messina, Sicily, 16-21 September 2018
J. Morris M. Y. Ye S. Mao
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 Published2020
UKAEA-CCFE-CP(19)37
46th European Physical Society Conference on Plasma Physics (EPS), Milan, 8-12 July 2019
A.J. Pearce R. Kembleton M. Kovari H. Lux J. Morris M. Siccinio
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…
Preprint2019
UKAEA-CCFE-CP(19)54
28th IEEE Symposium on Fusion Engineering, Jacksonville, Florida, USA, 2 – 6 June 2019
J. Morris N. Asakura Y. Homma
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 Published2019
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