Overview of the ALPS Program

Brooks, J.N.; Allain, Jean Paul; Bastasz, R.; Doerner, R.; Evans, T.E.; Hassanein, A.; Kaita, R.; Luckhardt, S.; Maingi, R.; Majeski, R.; Morley, Neil B.; Narula, M.; Rognlien, T. D.; Ruzic, D. N.; Stubbers, R.; Ulrickson, M.; Wong, C.P.C.; Whyte, D.G.; Ying, Alice

doi:10.13182/fst05-a763

Cited by 31 publications

(31 citation statements)

References 14 publications

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“…Secondly the fuel retention of liquid metals especially Li and Sn is highly uncertain and needs to be elaborated under controlled conditions. Tin as it doesn't readily form a stable hydrid may be less of an issue [4,38,39]. Thirdly, the heatexhaust of Sn under steady state and transient conditions needs to elaborated.…”

Section: Plasma Exposures and Outlookmentioning

confidence: 99%

“…Liquid metals have long been suggested to partly ameliorate life-time and power-exhaust issues by allowing for a self healing, self replenishing surface with no susceptibility to neutron damage. Several studies were dedicated to this topic [3,4,5,6] as several tokamak facilities have established liquid metal related research. Typically the research focuses on liquid Li due to its low melting point and beneficial behavior on plasma performance [7,8,9,10,11].…”

Section: Introductionmentioning

confidence: 99%

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Liquid metals as alternative solution for the power exhaust of future fusion devices: status and perspective

Coenen

Temmerman

Federici³

et al. 2014

Phys. Scr.

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Abstract. Applying liquid metals as Plasma Facing Components for fusion powerexhaust can potentially ameliorate lifetime issues as well as limitations to the maximum allowed surface heat loads by allowing for a more direct contact with the coolant. The material choice has so far been focused on lithium (Li) as it showed beneficial impact on plasma operation. Here materials such as tin (Sn), gallium (Ga) and aluminum (Al) are discussed as alternatives potentially allowing higher operating temperatures without strong evaporation. Power loads of up to 25MW/m 2 for a Sn/W component can be envisioned based on calculations and modeling. Reaching a higher operating temperature due to material re-deposition will be discussed. Liquids are typically facing stability issues due to j × B forces, potential pressure and MHD driven instabilities. The Capillary Porous System is used for stabilization by a mesh (W,Mo) substrate and replenishment by means of capillary action.

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Section: Plasma Exposures and Outlookmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Liquid metals as alternative solution for the power exhaust of future fusion devices: status and perspective

Coenen

Temmerman

Federici³

et al. 2014

Phys. Scr.

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“…We present here our computations of this effect, to obtain a feel for its magnitude. Fig [8] shows various views relevant to this effect, concluding in a pressure gradient diagram where we see about 80 -90 % variation in pressure gradient near the pressure tap. …”

Section: Role Of Pressure Tapsmentioning

confidence: 92%

“…A comprehensive code development activity at the scale investigated here has not been carried out hitherto, and there is to date, a lack of a well accepted set of benchmark problems in this area. The design of unit problems in multi-physical MHD flows is of contemporary interest, as expressed in various survey articles in the literature (Morley et al 31 , Kirilov et al 25 , Brooks et al 8 , and Molokov et al 28 ).…”

Section: Progress In High Hartmann Number Computations Page 4 Of 59mentioning

confidence: 99%

Physical Model Development and Benchmarking for MHD Flows in Blanket Design

Munipalli¹,

Chandler²,

C.Rowell³

et al. 2008

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An advanced simulation environment to model incompressible MHD flows relevant to blanket conditions in fusion reactors has been developed at HyPerComp in research collaboration with TEXCEL. The goals of this phase-II project are two-fold: The first is the incorporation of crucial physical phenomena such as induced magnetic field modeling, and extending the capabilities beyond fluid flow prediction to model heat transfer with natural convection and mass transfer including tritium transport and permeation. The second is the design of a sequence of benchmark tests to establish code competence for several classes of physical phenomena in isolation as well as in select (termed here as "canonical",) combinations. No previous attempts to develop such a comprehensive MHD modeling capability exist in the literature, and this study represents essentially uncharted territory. During the course of this Phase-II project, a significant breakthrough was achieved in modeling liquid metal flows at high Hartmann numbers. We developed a unique mathematical technique to accurately compute the fluid flow in complex geometries at extremely high Hartmann numbers (10,000 and greater), thus extending the state of the art of liquid metal MHD modeling relevant to fusion reactors at the present time. These developments have been published in noted international journals. A sequence of theoretical and experimental results was used to verify and validate the results obtained. The code was applied to a complete DCLL module simulation study with promising results.DOE Phase-II SBIR Project: "Canonical approach to liquid metal modeling"

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“…The Advanced Limiter-divertor Plasma-facing Systems (ALPS) program in the U.S. 2 considered engineering approaches to the implementation of liquid metal (or liquid salt) PFCs. Liquid metals constitute a viable alternative to the use of solid tungsten PFCs in a reactor.…”

Section: Introductionmentioning

confidence: 99%

Particle Control and Plasma Performance in the Lithium Tokamak Experiment (LTX)

Majeski¹

2013

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Abstract. The Lithium Tokamak eXperiment (LTX) is a small, low aspect ratio tokamak, 1 which is fitted with a stainless steel-clad copper liner, conformal to the last closed flux surface. The liner can be heated to 350 °C. Several gas fueling systems, including supersonic gas injection, and molecular cluster injection have been studied, and produce fueling efficiencies up to 35%.Discharges are strongly affected by wall conditioning. Discharges without lithium wall coatings are limited to plasma currents of order 10 kA, and discharge durations of order 5 msec. With solid lithium coatings discharge currents exceed 70 kA, and discharge durations exceed 30 msec.Heating the lithium wall coating, however, results in a prompt degradation of the discharge, at the melting point of lithium. These results suggest that the simplest approach to implementing liquid lithium walls in a tokamak -thin, evaporated, liquefied coatings of lithium -does not produce an adequately clean surface.2

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Overview of the ALPS Program

Cited by 31 publications

References 14 publications

Liquid metals as alternative solution for the power exhaust of future fusion devices: status and perspective

Liquid metals as alternative solution for the power exhaust of future fusion devices: status and perspective

Physical Model Development and Benchmarking for MHD Flows in Blanket Design

Particle Control and Plasma Performance in the Lithium Tokamak Experiment (LTX)

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