Compact fusion energy based on the spherical tokamak

Sykes, A.; Costley, A.E.; Windsor, C. G.; Asunta, O.; Brittles, Greg; Buxton, P.F.; Chuyanov, V.A.; Connor, J. W.; Gryaznevich, M.; Huang, Billy; Hugill, J.; Kukushkin, A.S.; Kingham, David R.; Langtry, A.V.; McNamara, Steven; Morgan, J.G.; Noonan, P.; Ross, John; Shevchenko, V. F.; Slade, Robert A.; Smith, George Davey

doi:10.1088/1741-4326/aa8c8d

Cited by 120 publications

(78 citation statements)

References 28 publications

(45 reference statements)

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“…Advanced shielding materials are needed in many nuclear shielding technologies where space is limited including isotope containers, collimators, beam stops, and compact nuclear fission and fusion reactors. Space limitation is a particular concern for compact reactors and the recentlyvalidated spherical tokamak fusion reactor [1], which could offer dramatically reduced costs and faster prototype development compared to conventional reactors [2][3][4]. Shielding these reactors is challenging around the high-temperature superconductors (HTS) within the central column.…”

Section: Introductionmentioning

confidence: 99%

A high temperature W2B–W composite for fusion reactor shielding

Athanasakis-Kaklamanakis

Ivanov²,

Río³

et al. 2020

Journal of Nuclear Materials

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We have developed a new material for neutron shielding applications where space is restricted. W 2 B is an excellent attenuator of neutrons and gamma-rays, due to the combined gamma attenuation of W and neutron absorption of B. However, its low fracture toughness (∼3.5 MPa) and high melting point (2670 • C) prevent the fabrication of large fully-dense monolithic parts with adequate mechanical properties. Here we meet these challenges by combining W 2 B with a minor fraction (43 vol.%) of metallic W. The material was produced by reaction sintering W and BN powders. The mechanical properties under flexural and compressive loading were determined up to 1900 • C. The presence of the ductile metallic W phase enabled a peak flexural strength of ∼950 MPa at 1100 • C, which is a factor of 2-3 higher than typical monolithic transition-metal borides. Its ductile-brittle transition temperature of ∼1000 • C is typical of W-based composites, which is surprising as the W phase was the minor constituent and did not appear to form a fully continuous network. Compression tests showed hardening below ∼1500 • C and significant elongation of the phase domains, which suggest that by forging or rolling, further improvements in ductility may be possible.

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Section: Introductionmentioning

confidence: 99%

A high temperature W2B–W composite for fusion reactor shielding

Athanasakis-Kaklamanakis

Ivanov²,

Río³

et al. 2020

Journal of Nuclear Materials

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“…The extra space made available by increasing the major radius has been divided in the ratio 92% to the shield thickness T shield and 8% to the HTS core radius R cc across the plot. Reproduced from Sykes et al [27], with the permission of the IAEA.…”

Section: Integration: Design Of a Compact St Fusion Modulementioning

confidence: 99%

“…As an example, a scoping study has been undertaken by Sykes et al [27]. The authors took as a reference plasma Q fus = 5, P fus = 200 MW, H(IPB98y2) = 1.9, A = 1.8, κ = 2.64, β N = 4.5, and examined the engineering feasibility in relation to a few key parameters, for example the cryopower needed to maintain the temperature of the HTS magnet in the required range (20-30 K).…”

Section: Integration: Design Of a Compact St Fusion Modulementioning

confidence: 99%

Towards a compact spherical tokamak fusion pilot plant

Costley

2019

Phil. Trans. R. Soc. A.

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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.

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“…The tokamak, such as ITER (as introduced in Section 1), utilizes magnetic coils arranged around a torus-shaped vessel, which generates a toroidal magnetic field to confine the plasma, and uses a secondary poloidal magnetic field to drive the current in the plasma [13]. Other tokamak variants, such as the spherical tokamak design, which has a lower aspect ratio (the ratio of the outer radius to the inner radius of the torus), exhibits different and potentially better plasma performance but with the tradeoff of increased difficulty in engineering design [22].…”

Section: Approaches To Fusion Reactorsmentioning

confidence: 99%

“…A modular power plant configuration also opens up the possibility of load-following capability and co-generation, by switching on a greater number of modules to provide electricity at times of high grid demand and then switching the output for the purposes of process heat applications at times of low grid demand. This concept is possible with some of the approaches being explored by various fusion initiatives, and is suggested in [22] (see Section 6), as well as by an array of concepts employing the use of fission SMRs (Small Modular Reactors), which share many similarities with the modular fusion power plant concept [21,23].…”

Section: Operation Modesmentioning

confidence: 99%

Nuclear Fusion Power Plants

Takeda¹,

Pearson²

2019

Power Plants in the Industry

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Nuclear fusion, the process that powers the sun and the stars, is heralded as the ultimate energy source for the future of mankind. The promise of nuclear fusion to provide clean and safe energy, while having abundant fuel resources continues to drive global research and development. However, the goal of reaching so-called "breakeven" energy conditions, whereby the energy produced from a fusion reaction is greater than the energy put in, is yet to be demonstrated. It is the role of ITER, an international collaborative experimental reactor, to achieve breakeven conditions and to demonstrate technologies that will allow fusion to be realized as a viable energy source. However, with significant delays and cost overruns to ITER, there has been increased interest in the development of other fusion reactor concepts, particularly by private-sector start-ups, all of which are exploring the possibility of an accelerated route to fusion. This chapter gives a comprehensive overview of nuclear fusion science, and provides an account of current approaches and their progress towards the realization of future fusion energy power plants. The range of technical issues, associated technology development challenges and future commercial opportunities are explored, with a focus on magnetic confinement approaches.

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Compact fusion energy based on the spherical tokamak

Cited by 120 publications

References 28 publications

A high temperature W2B–W composite for fusion reactor shielding

A high temperature W2B–W composite for fusion reactor shielding

Towards a compact spherical tokamak fusion pilot plant

Nuclear Fusion Power Plants

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