Long-term fusion strategy in Europe

Lackner, K.; Andreani, Roberto; Campbell, D.J.; Gasparotto, M.; Maisonnier, D.; Pick, M.

doi:10.1016/s0022-3115(02)00970-4

Cited by 44 publications

(34 citation statements)

References 9 publications

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“…Therefore, two devices for H, D, He or Ar plasma generation are planned for TechnoFusión: one is a linear plasma device, meant to reproduce the above-mentioned stationary conditions, and the other is a quasi-stationary plasma accelerator (QSPA) to simulate the transients. 1 k, proton kinetic energy.…”

Section: Plasma-wall Interactionsmentioning

confidence: 99%

“…A present approach to fusion power [1,2] is to simultaneously construct and operate ITER (the International Thermonuclear Experimental Reactor) and IFMIF (the Irradiation Fusion Materials Facility) in order to provide information for an early decision on DEMO (the DEMOnstration power plant), the device [3] that will bridge the gap between ITER and the first-of-a-kind fusion power plant (FPP). There are discrepancies on the objectives of DEMO, being one of the main objectives to qualify components and processes in reactor relevant conditions for the first FPP.…”

Section: Introductionmentioning

confidence: 99%

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TechnoFusión, a relevant facility for fusion technologies: The remote handling area

Ibarra

Perlado

Aracil

et al. 2010

Fusion Engineering and Design

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Abstract:The future commercial production of electricity based on thermonuclear fusion requires the development of a number of research projects in addition to ITER, mostly related to the development of long-term technologies needed for future fusion reactors. Among the priority areas identified in the framework of international fusion research programmes, it is projected to build a specific research centre for fusion technologies in Spain. The so-called National Centre for Fusion Technologies, TechnoFusión, will be equipped with a large number of top facilities for the fusion technological development. The research activities will be focused primarily on several areas, including the implementation of advanced man-ufacturing technologies, the evaluation of radiation effects on low activation structural and functional materials, the in-beam and out-beam characterization of materials, the development of robotics and automated systems for remote handling, studies of liquid metal technologies and computer simulation. Currently no similar facilities to TechnoFusión exist, so it will provide more realistic tests than those available in other facilities up today, helping in the fast track to DEMO and IFMIF. The present document summarizes a review of the different facilities to be included in TechnoFusión, with special emphasis on those proposed for remote handling (RH) applications. The paper will review the technical specifications concerning the RH facility, the analysis of the mock-up components and tests to be performed, and the relevance of the RH lab capabilities, particularly the required equipment under irradiation conditions.

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Section: Plasma-wall Interactionsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

TechnoFusión, a relevant facility for fusion technologies: The remote handling area

Ibarra

Perlado

Aracil

et al. 2010

Fusion Engineering and Design

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show abstract

“…This could, in principle, however, be turned into an advantage for the study of the regimes with very high heat flux in the scrape-off layer, required by fusion reactor designs 6 . The reactor relevance of divertor physics and technology is determined by very different similarity considerations 7,8 The above 3 landscapes (Figs.1-3) illustrate that a direct simulation of the ITER or DEMO parameter regime will not be possible in devices existing or under construction, in particular due to the incompatibility of the Greenwald density and the collisionality requirements.…”

Section: Dimensionless Engineering Variablesmentioning

confidence: 99%

Dimensionless Engineering Variables for Measuring the ITER and Reactor Relevance of Tokamak Experiments

Lackner

2008

Fusion Science and Technology

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a 5/4 and P heat . a 3/4 are proposed as dimensionless engineering parameters to measure the reactor relevance of existing and planned confinement devices. These quantities -together with a density parameter that can be written as n . a 3/4 /B t -have to be conserved in plasma physics identity experiments on different size devices to respect the so-called Kadomtsev similarity constraints, and offer a coordinate system to map the approach to the reactor regime. Theoretical and semi-empirical models can be used in this coordinate space to produce isocontours for different dimensionless physics quantities, like the usual parameters ρ * ,ν * ,β, but also for the intensity of collisional coupling, the excess of heating power over the L-H transition threshold, and the ratio of current redistribution to energy confinement time to visualize the distance to the regime of a fusion reactor.

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“…This strategy is common to that of EU. 49,50) For the qualification of materials up to the full lifetime of DEMO and Power Plant Reactors, irradiation testing with IFMIF (International Fusion Materials Irradiation Test Facility, a 14 MeV neutron source) is recognized to be essential.…”

Section: Strategy Of Vanadium Alloy Development For Fusion Blanketmentioning

confidence: 99%

Vanadium Alloys for Fusion Blanket Applications

Muroga

2005

Mater. Trans.

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Vanadium alloys are attractive candidate structural materials for breeding blanket of fusion reactors because of their low activation properties and high temperature strength. Studies on various blanket designs are being carried out using vanadium alloys as structural materials and liquid lithium or molten salt Flibe as breeding and coolant materials. Recently significant progress in fabrication technology has been made for vanadium alloys through a program of producing large ingots of high purity V-4Cr-4Ti (NIFS-HEATs). Fundamental understandings on the effects of interstitial impurities (C, N, O) on mechanical properties, radiation effects on microstructure and mechanical properties, corrosion and compatibility in various environments were enhanced. New promising candidates were identified for the MHD insulator coating. Among the remaining critical issues are the effects of transmutant helium on mechanical properties and development of long life MHD coating. Development of vanadium alloys will be carried out in coordination with IFMIF and ITER-TBM schedules as essential tools for verification of their performance in fusion blanket environments.

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Long-term fusion strategy in Europe

Cited by 44 publications

References 9 publications

TechnoFusión, a relevant facility for fusion technologies: The remote handling area

TechnoFusión, a relevant facility for fusion technologies: The remote handling area

Dimensionless Engineering Variables for Measuring the ITER and Reactor Relevance of Tokamak Experiments

Vanadium Alloys for Fusion Blanket Applications

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