Dynamic modelling of balance of plant systems for a pulsed DEMO power plant

Harrington, C.

doi:10.1016/j.fusengdes.2015.03.029

Cited by 9 publications

(4 citation statements)

References 2 publications

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“…Solutions involving an energy storage system (ESS) to mitigate any issues have been proposed [73]; however, the financial impact could be significant and without a firm understanding of the inherent cycling challenges, it is not possible to justify such a system. [74] simulate the time-variant behaviour of the heat transfer and BoP systems for DEMO, without an ESS, to gain insight into the major technical challenges of pulsed operation and possible mitigation strategies. An operating regime is defined for water such that the primary coolant flows continuously throughout the dwell period while the secondary steam flow is reduced.…”

Section: Primary Heat Transfer System and Balance Of Plantmentioning

confidence: 99%

European DEMO design strategy and consequences for materials

Federici¹,

et al. 2017

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Demonstrating the production of net electricity and operating with a closed fuel-cycle remain unarguably the crucial steps towards the exploitation of fusion power. These are the aims of a demonstration fusion reactor (DEMO) proposed to be built after ITER. This paper briefly describes the DEMO design options that are being considered in Europe for the current conceptual design studies as part of the Roadmap to Fusion Electricity Horizon 2020. These are not intended to represent fixed and exclusive design choices but rather 'proxies' of possible plant design options to be used to identify generic design/material issues that need to be resolved in future fusion reactor systems. The materials nuclear design requirements and the effects of radiation damage are briefly analysed with emphasis on a pulsed 'low extrapolation' system, which is being used for the initial design integration studies, based as far as possible on mature technologies and reliable regimes of operation (to be extrapolated from the ITER experience), and on the use of materials suitable for the expected level of neutron fluence. The main technical issues arising from the plasma and nuclear loads and the effects of radiation damage particularly on the structural and heat sink materials of the vessel and in-vessel components are critically discussed. The need to establish realistic target performance and a development schedule for near-term electricity production tends to favour more conservative technology choices. The readiness of the technical (physics and technology) assumptions that are being made is expected to be an important factor for the selection of the technical features of the device.

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Section: Primary Heat Transfer System and Balance Of Plantmentioning

confidence: 99%

European DEMO design strategy and consequences for materials

Federici¹,

et al. 2017

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“…Since the latter would probably require large amounts of auxiliary installed power and operate in 'advanced' regimes, the pulsed machine looks at the moment as the most standard and cost-effective solution. Each discharge of the pulsed DEMO (called DEMO1 henceforth), would be characterized by ramp-up, H-mode flattop, and ramp-down, plus dwell time [6]. The H-mode phase would be characterized by substantial α heating, moderate auxiliary power (∼50 MW, mostly for MHD/burn control), and substantial core/SOL radiation to mitigate the heat loads on the wall and divertor materials [7].…”

Section: Introductionmentioning

confidence: 99%

Selected transport studies of a tokamak-based DEMO fusion reactor

2016

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As a next-step in the tokamak-based fusion programme, the DEMO fusion reactor is foreseen to produce relevant output electricity, in the order of ∼500 MW delivered to the network. The scenarios that are being presently investigated consist of a pulsed device, called DEMO1, and a steady-state device, called DEMO2. In this work, which is focused on the pulsed device DEMO1, scenarios are studied from the point of view of core transport, to assess plasma performance and limitations due to core microinstabilities. The role of radiated power, aspect ratio, and height of temperature pedestal are assessed as they impact both core energy and particle transport. Open issues in this framework are also discussed.

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“…The lower temperature of 300 °C was chosen because during the dwell period, the temperature of a brazed joint should be close Fig. 5 Scheme of the investigated brazed joints to the coolant and during the dwell period the coolant will continue to flow [44]. Every 20 cycles, an appearance of the specimen was examined by macro examination at sevenfold magnification with binocular microscope.…”

Section: Methodsmentioning

confidence: 99%

Self-passivating smart tungsten alloys for DEMO: a progress in joining and upscale for a first wall mockup

et al. 2021

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Self-passivating, so-called smart alloys are under development for a future fusion power plant. These alloys containing tungsten, chromium and yttrium must possess an acceptable plasma performance during a regular plasma operation of a power plant and demonstrate the suppression of non-desirable oxidation of tungsten in case of an accident. The up-scaling of the bulk smart alloys to the reactor-relevant sizes has begun and the first samples with a diameter of 50 mm and thickness of 5 mm became available. The samples feature high relative density of above 99% and good homogeneity. With production of bulk samples, the research program on joining the smart alloy to the structural material was initiated. In a present study, the novel titanium–zirconium–beryllium braze was applied successfully to join the smart alloy to the Rusfer-reduced-activation steel. The braze has survived at least a hundred of cyclic thermal excursions in the range of 300–600 °C without mechanical destruction.

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Dynamic modelling of balance of plant systems for a pulsed DEMO power plant

Cited by 9 publications

References 2 publications

European DEMO design strategy and consequences for materials

European DEMO design strategy and consequences for materials

Selected transport studies of a tokamak-based DEMO fusion reactor

Self-passivating smart tungsten alloys for DEMO: a progress in joining and upscale for a first wall mockup

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