Conceptual Design of Fusion Experimental Reactor(FER)

Tone, Tatsuzo; Fujisawa, N.; Seki, Yasushi; Iida, H.; Tachikawa, K.; Sugihara, M.; Minato, Akihiko; Nishio, S.; Yamamoto, T.; Kitamura, K.; Ueda, K.; Saito, Seiji; Shimada, Ryuichi; Matsuda, Yuji; Naruse, Yuji; Shimamoto, S.; Tamura, Shinichi; Yoshikawa, M.; Tomabechi, Ken

doi:10.13182/fst83-a22924

Cited by 21 publications

(4 citation statements)

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“…Present day tokamaks are built with up-down symmetric sets of divertor coils that offer a capability of two standard X-point divertors commonly referred to as double null (DN) configurations. Such DN configurations have been envisioned for many tokamak concepts [48][49][50][51] and realized in a number of tokamaks (e.g., [16,52,53]) (see figure 1). The DN divertor provides heat and particle sharing between divertors [54], a possibility of separating power and particle control [55,56], and unique quiescent properties of the inner isolated SOL [57].…”

Section: Concepts Overview Via Historical Perspectivementioning

confidence: 99%

A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

Soukhanovskii

2017

Plasma Phys. Control. Fusion

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The present vision for a plasma-material interface in the tokamak is an axisymmetric poloidal magnetic X-point divertor. Four tasks are accomplished by the standard poloidal X-point divertor: plasma power exhaust; particle control (D/T and He pumping); reduction of impurity production (source); and impurity screening by the divertor scrape-off layer. A low-temperature, low heat flux divertor operating regime called radiative detachment is viewed as the main option that addresses these tasks for present and future tokamaks. Advanced magnetic divertor configuration has the capability to modify divertor parallel and cross-field transport, radiative and dissipative losses, and detachment front stability. Advanced magnetic divertor configurations are divided into four categories based on their salient qualitative features: (1) multiple standard X-point divertors; (2) divertors with higher order nulls; (3) divertors with multiple X-points; and (4) long poloidal leg divertors (and also with multiple X-points). This paper reviews experiments and modeling in the area of radiative detachment in the advanced magnetic divertor configurations.

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Section: Concepts Overview Via Historical Perspectivementioning

confidence: 99%

A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

Soukhanovskii

2017

Plasma Phys. Control. Fusion

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“…It can provide full integrated testing of plasma physics and technology. Devices in this class include INTOR [16], NET [17], and FER [18]. The 1982 INTOR design is used here to represent this general class of facilities.…”

Section: Fusion Test Facilitiesmentioning

confidence: 99%

“…Numerous blanket design studies have been conducted worldwide. Many of these studies have been carried out in the context of conceptual designs for power reactors (see Refs [8,[10][11][12][13][14][15] for examples) or for near term engineering testing facilities such as INTOR [ 16], NET [17], and FER [18]. Recently, the Blanket Comparison and Selection Study (BCSS) [19] in the USA and another study [20,21 ] carried out by a number of organizations in Europe have focused explicitly on comparisons of blanket concepts.…”

Section: Introductionmentioning

confidence: 99%

Technical issues and requirements of experiments and facilities for fusion nuclear technology

et al. 1987

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The technical issues, development problems and required experiments and facilities for fusion nuclear technology have been investigated. The results have been used to develop a technical framework for a test plan that identifies the role, timing, characteristics and costs of major experiments and facilities. A major feature of this framework is the utilization of non-fusion facilities over the next 15 years, followed by testing in fusion devices beyond about the year 2000. Basic, separate effect and multiple interaction experiments in non-fusion facilities will provide property data, explore phenomena and provide input to theory and analytic modelling. Experiments in fusion facilities can proceed in two phases: (1) concept verification and (2) component reliability growth. Integrated testing imposes certain requirements on fusion testing device parameters; these requirements have been quantified. The nuclear subsystems addressed in the study are: (a) blanket and first wall; (b) tritium processing system; (c) plasma interactive components; and (d) radiation shield. The two generic classes of liquid and solid breeder blankets have significant engineering feasibility issues, and new experimental data must be obtained before selection of an attractive design concept. Liquid metal blanket issues are dominated by problems related to momentum, heat and mass transfer, which can be addressed in non-neutron test facilities. Solid breeder blanket issues are, however, dominated by the effects of radiation, including heating, transmutation and damage, which can be reasonably addressed in fission reactors. The tritium processing uncertainties are primarily related to the control and recovery systems, and most can be addressed in existing and planned non-neutron facilities. A dominant feature of plasma interactive components is the strong interrelation to both plasma physics and nuclear technology. Required facilities include thermomechanical test stands and confinement devices with sufficiently long plasma burn. The radiation shield poses no feasibility issues, but improved accuracy of predictions will reduce design conservatism and lower costs.

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“…Lithium oxide is the leading candidate for the blanket material in deuterium-tritium fusion reactors [4]. It is also a lithium fast-ion conductor at high temperatures, and has potential applications in solid-state batteries [5].…”

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The Energetics of Frenkel Defects in Li ₂ O from First Principles

et al. 1992

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Conceptual Design of Fusion Experimental Reactor(FER)

Cited by 21 publications

References 1 publication

A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

Technical issues and requirements of experiments and facilities for fusion nuclear technology

The Energetics of Frenkel Defects in Li ₂ O from First Principles

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Conceptual Design of Fusion Experimental Reactor(FER)

Cited by 21 publications

References 1 publication

A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

Technical issues and requirements of experiments and facilities for fusion nuclear technology

The Energetics of Frenkel Defects in Li 2 O from First Principles

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The Energetics of Frenkel Defects in Li ₂ O from First Principles