Recent Advances on the Spherical Tokamak Route to Fusion Power

2014 ◽  
Vol 42 (3) ◽  
pp. 482-488 ◽  
Author(s):  
Alan Sykes ◽  
Mikhail P. Gryaznevich ◽  
David Kingham ◽  
Alan E. Costley ◽  
Jan Hugill ◽  
...  
2016 ◽  
Vol 57 (3) ◽  
pp. 036001 ◽  
Author(s):  
C.G. Windsor ◽  
J.G. Morgan ◽  
P.F. Buxton ◽  
A.E. Costley ◽  
G.D.W. Smith ◽  
...  

Author(s):  
A. E. Costley

The question of size of a tokamak fusion reactor is central to current fusion research especially with the large device, ITER, under construction and even larger DEMO reactors under initial engineering design. In this paper, the question of size is addressed initially from a physics perspective. It is shown that in addition to size, field and plasma shape are important too, and shape can be a significant factor. For a spherical tokamak (ST), the elongated shape leads to significant reductions in major radius and/or field for comparable fusion performance. Further, it is shown that when the density limit is taken into account, the relationship between fusion power and fusion gain is almost independent of size, implying that relatively small, high performance reactors should be possible. In order to realize a small, high performance fusion module based on the ST, feasible solutions to several key technical challenges must be developed. These are identified and possible design solutions outlined. The results of the physics, technical and engineering studies are integrated using the Tokamak Energy system code, and the results of a scoping study are reviewed. The results indicate that a relatively small ST using high temperature superconductor magnets should be feasible and may provide an alternative, possibly faster, ‘small modular’ route to fusion power. This article is part of a discussion meeting issue ‘Fusion energy using tokamaks: can development be accelerated?’.


2004 ◽  
Vol 44 (8) ◽  
pp. 917-929 ◽  
Author(s):  
H.R Wilson ◽  
J.-W Ahn ◽  
R.J Akers ◽  
D Applegate ◽  
R.A Cairns ◽  
...  

2011 ◽  
Vol 57 ◽  
pp. 395-422 ◽  
Author(s):  
John Connor ◽  
Colin Windsor

Derek Robinson was a leading UK plasma physicist of his generation. After an early success in measuring the electron temperature in the ZETA plasma through the Thomson scattering of laser light, he became a key member of the team from Culham Laboratory sent to Moscow in 1968 to verify the high temperatures claimed by the Russians for their T3 tokamak. On returning to Culham his research activities continued to broaden and he became an acknowledged expert on a range of fusion devices. His management responsibilities grew in parallel and eventually he became Director of Culham. With his strong support, Culham explored the novel spherical tokamak devices START and MAST, and he promoted this concept as an alternative route to the conventional tokamak for developing fusion power. His energetic leadership and his mastery of theory, experiment and fusion politics brought fusion power nearer to reality. His vision of the ‘way forward’ for the international fusion programme remains with us after his life was so sadly cut short by the unexpected development of lung cancer in a non-smoker.


2022 ◽  
Author(s):  
Colin Windsor ◽  
Jack Astbury ◽  
Guy Morgan ◽  
Christopher L. Wilson ◽  
Sam Humphry-Baker

Abstract The FISPACT-II code is used to compute the levels of activation and transmutation of tungsten borides for shielding the central High Temperature Superconductor (HTS) core of a spherical tokamak fusion power plant during operations at 200 MW fusion power for 30 years and after shutting down for 10 years. The materials considered were W2B, WB, W2B5 and WB4 along with a sintered borocarbide B0.329C0.074Cr0.024Fe0.274W0.299, monolithic W and WC. Calculations were made within shields composed of each material, for five reactor major radii from 1400 to 2200 mm, and for six 10B isotope concentrations and at five positions across the shield. The isotopic production and decay in each shield is detailed. The activation of boride materials is lower than for either W or WC and is lowest of all for W2B5. While isotopes from tungsten largely decay within 3 years of shut-down, those from boron have a much longer decay life. An acceptable 70% of the absorbing 10B isotope will remain after 30 years of operations behind the first wall for a 1400 mm radius tokamak. Gaseous production is problematic in boride shields, where 4He in particular is produced in quantities 3 orders of magnitude higher than in W or WC shields. The FISPACT-II displacements per atom (dpa) tend to increase with boron content, although they decrease with increased 10B isotopic content. The dpa ranges of boride shields tend to lie between those of W and WC. Overall, the results confirm that the favourable fusion reaction shielding properties of W2B5 are not seriously challenged by its irradiation and transmutation properties, although helium gas production could be a challenge to its thermal and mechanical properties.


Author(s):  
A Sykes ◽  
M. P. Gryaznevich ◽  
D. Kingham ◽  
A. E. Costley ◽  
J. Hugill ◽  
...  

1998 ◽  
Vol 33 (1) ◽  
pp. 1-21 ◽  
Author(s):  
Ronald D. Stambaugh ◽  
Vincent S. Chan ◽  
Robert L. Miller ◽  
Michael J. Schaffer

2021 ◽  
Author(s):  
Colin Windsor ◽  
Jack Astbury ◽  
James Davidson ◽  
Charles McFadzean ◽  
Guy Morgan ◽  
...  

2012 ◽  
Vol 132 (7) ◽  
pp. 526-529
Author(s):  
Kozo Yamazaki ◽  
Tetsutarou Oishi ◽  
Kanae Ban ◽  
Takuya Kondo ◽  
Hideki Arimoto ◽  
...  

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