Conceptual design study of a superconducting spherical tokamak reactor with a self-consistent system analysis code

Hong, Bong Guen; Hwang, Y.S.; Kang, Junsu; Lee, D.W.; Joo, Han Gyu; Ono, M.

doi:10.1088/0029-5515/51/11/113013

Cited by 34 publications

(15 citation statements)

References 14 publications

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“…The other class of ST power plants is the SC TF design being pursued in Japan 86,87 and Korea. 88 The size of the power plant is larger (because of the thicker in-board neutron shield) as shown in the curve for D $ 100 cm in Fig. 32.…”

Section: St Demo/power Plantsmentioning

confidence: 99%

“…88 The high-temperature superconducting magnets with high critical current density, if they can be developed for fusion magnet, open up the possibility of a fusion power plant with compact size and small re-circulating power, simultaneously with low aspect ratio. A central ohmic start-up solenoid is envisioned.…”

Section: Korean Sc-st Reactor Studiesmentioning

confidence: 99%

“…Because of this, an ohmic heating solenoid with sufficient start-up capability can be incorporated into the design as mentioned in Sec. II C. [86][87][88] V. TRANSPORT AND TURBULENCE…”

mentioning

confidence: 99%

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Recent progress on spherical torus research

Ono

Kaita

2015

Physics of Plasmas

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The spherical torus or spherical tokamak (ST) is a member of the tokamak family with its aspect ratio (A = R0/a) reduced to A ∼ 1.5, well below the normal tokamak operating range of A ≥ 2.5. As the aspect ratio is reduced, the ideal tokamak beta β (radio of plasma to magnetic pressure) stability limit increases rapidly, approximately as β ∼ 1/A. The plasma current it can sustain for a given edge safety factor q-95 also increases rapidly. Because of the above, as well as the natural elongation κ, which makes its plasma shape appear spherical, the ST configuration can yield exceptionally high tokamak performance in a compact geometry. Due to its compactness and high performance, the ST configuration has various near term applications, including a compact fusion neutron source with low tritium consumption, in addition to its longer term goal of an attractive fusion energy power source. Since the start of the two mega-ampere class ST facilities in 2000, the National Spherical Torus Experiment in the United States and Mega Ampere Spherical Tokamak in UK, active ST research has been conducted worldwide. More than 16 ST research facilities operating during this period have achieved remarkable advances in all fusion science areas, involving fundamental fusion energy science as well as innovation. These results suggest exciting future prospects for ST research both near term and longer term. The present paper reviews the scientific progress made by the worldwide ST research community during this new mega-ampere-ST era.

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Section: St Demo/power Plantsmentioning

confidence: 99%

Section: Korean Sc-st Reactor Studiesmentioning

confidence: 99%

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Recent progress on spherical torus research

Ono

Kaita

2015

Physics of Plasmas

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“…A potential candidate material for next generation nuclear shielding is cemented tungsten carbide (cWC). cWCs have excellent wear and thermal properties along with a high hardness (7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18)(19)(20)(21)(22) GPa at 30 kgf) [2,3] and impressive fracture toughness (8-25 MPa m 1/2 ) [2,4]. The properties of cWCs result from their combination of hard WC particles (0.4-8 µm) and ductile metallic binder phase (hereafter referred to as "binder") processed using powder metallurgy.…”

Section: Introductionmentioning

confidence: 99%

Structure and Properties of High-Hardness Silicide Coatings on Cemented Carbides for High Temperature Applications

Humphry-Baker

Marshall

2018

Coatings

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Cemented tungsten carbides (cWCs) are routinely used in mining and manufacturing but are also candidate materials for compact radiation shielding in fusion power generation. In both applications, there is a need for oxidation to be minimized at operating temperatures. In a recent study, Si-based coatings deposited by pack cementation were demonstrated to improve the oxidation resistance of cWCs by up to a factor of 1000. In this work, these coatings are further characterized, with the focus on growth kinetics, phase composition, and hardness. By combining quantitative X-ray diffraction, electron microscopy, and instrumented micro-indentation, it is shown that the coating layer has a 20% higher hardness than the substrate, which is explained by the presence of a previously-unknown distribution of very hard SiC laths. To interpret the coating stability, a coating growth map is developed. The map shows that the structure is stable under a broad range of processing temperatures and cWC compositions, demonstrating the wide-ranging applicability of these coatings.

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“…Due to advantages of high beta, compactness and consequent cost-effectiveness, spherical torus (ST) has been proposed as a potential fusion reactor concept as well as compact neutron sources [1,2]. However, since ST has limited space in a center stack for central solenoid coils, ohmic heating using the central solenoid coils may not be available for plasma start-up.…”

Section: Introductionmentioning

confidence: 99%