A5012259462- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Nuclear and radioactivity studies
- Nuclear Materials and Properties
- EU Law and Policy Analysis
- Climate Change Policy and Economics
- Life Cycle Costing Analysis
- International Science and Diplomacy
- Global Energy and Sustainability Research
- Environmental Impact and Sustainability
- Plasma Diagnostics and Applications
- Cold Fusion and Nuclear Reactions
- European Monetary and Fiscal Policies
- Radioactive contamination and transfer
Culham Centre for Fusion Energy
2016-2023
Philip Morris International (Germany)
2020
Culham Science Centre
2016-2019
Hillingdon Hospital
2016
This paper describes the progress of DEMO Design Activities in Europe and particularly work done to address critical design integration issues that affect machine configuration performance, plant concept layout selection system technologies. Work continues be primarily focused on a pulsed baseline reactor concept, but number alternative configurations (e.g., double-null divertor snowflake as well ‘flexi’ operates initially an inductively driven regime, with possibility upgraded long-pulse or...
This paper describes the status of pre-conceptual design activities in Europe to advance technical basis a DEMOnstration Fusion Power Plant (DEMO) come operation around middle this century with main aims demonstrating production few hundred MWs net electricity, feasibility closed-tritium fuel cycle, and maintenance systems capable achieving adequate plant availability. is expected benefit as much possible from ITER experience, terms design, licensing, construction. Emphasis on an integrated...
Abstract A large scale program to develop a conceptual design for demonstration fusion power plant (DEMO) has been initiated in Europe. Central elements are the baseline points, which developed by system codes. The assessment of credibility these points is often hampered missing information. main physics and technology content central European codes have published (Kovari et al 2014 Fusion Eng. Des . 89 3054–69, 2016 104 9–20, Reux 2015 Nucl. 55 073011). In addition, this publication...
This paper is part of a series publications concerning the development European DEMO during Pre-Concept Design Phase (2014-2020), and also describing strategy for next phase. In particular, it deals with physics basis plasma scenarios employed definition various baselines released so far, assumptions adopted where necessary. course Phase, some these have been progressively replaced results dedicated modelling activities or code developments in general, which are summarized here. The...
Plasma exhaust has been identified as a major challenge towards the realisation of magnetic confinement fusion. To mitigate risk that single null divertor (SND) with high radiation fraction in scrape-of-layer (SOL) adopted for ITER will not extrapolate to DEMO reactor, EUROfusion consortium is assessing potential benefits and engineering challenges alternative configurations. Alternative configurations could be readily design include X (XD), Super-X (SXD), Snowflake (SFD) double (DND). The...
The European DEMO, i.e. the demonstration fusion power plant designed in framework of Roadmap to Fusion Electricity by EUROfusion Consortium, is approaching end pre-conceptual design phase, be accomplished with a Gate Review 2020, which all DEMO subsystems will reviewed panels independent experts. latest 2018 baseline has major and minor radius 9.1 m 2.9 m, plasma current 17.9 MA, toroidal field on axis 5.2 T, peak toroidal-field (TF) conductor 12.0 T. 900 ton heavy TF coil prepared four...
In the present work, role of plasma facing components protection in driving EU-DEMO design will be reviewed, focusing on steady-state and, especially, transients. This work encompasses both first wall (FW) as well divertor. fact, while ITER divertor heat removal technology has been adopted, FW concept shown past years to inadequate for EU-DEMO. is due higher foreseen irradiation damage level, which requires structural materials (like Eurofer) able withstand more than 5 dpa neutron damage....
This paper discusses the criteria to be used in preliminary design phases of EU-DEMO reactor ensure performance divertor without compromising stability core plasma or fusion power generation. work refers a lower single null conventional using actively cooled solid metal plasma-facing components and with extrinsic seeding for heat flux dissipation, which is solution currently being adopted EU-DEMO. The analysis does not consider role edge localised modes, also neglects major off-normal events...
A physics and engineering analysis of alternative divertor configurations is carried out by examining benefits problems comparing the baseline single null solution with a Snowflake, an X- Super-X divertor. It observed that can provide margin resilience against large power fluctuations, but their has intrinsic difficulties, especially in balance between structural solidity accessibility components when specific poloidal field coil positioning poses further constraints. hybrid proposed as...
Once the high-level requirements for a fusion power plant are set, expected performance of systems, including plasma, must be defined and then available design space can explored in order to converge on final overall operating point, setting major parameters such as number toroidal field (TF) coils, tokamak radius, flows etc. Such explorations conducted using systems codes which contain simplified models attempt capture interactions between them balance trade-offs enforce consistency. This...
Under the ambitious EUROfusion mission of "bringing stellarator line to technological maturity", development a Dual Coolant Lithium–Lead (DCLL) Breeding Blanket (BB) for Helical-Axis Advanced Stellarator (HELIAS) started. The BB is crucial systems achieve tritium self-sufficiency in fusion power plants. DCLL has potentialities answer challenges posed by complex HELIAS configuration, having liquid breeder and decoupled first wall (FW) breeding zone circuits. Both characteristics are being...
The divertor design and configuration define the power exhaust capabilities of DEMO, act as a major driver. They set number requirements on tokamak layout, including port sizes, poloidal field coil positions, size toroidal coils. It also requires corresponding plasma-facing components (PFCs) remote handling scheme to be able handle cassettes associated in-vessel requires. There is risk that baseline ITER-like single-null (SN) cannot meet PFC technology limits regarding while achieving target...
• In order to assess the commercial prospects of nuclear fusion as an energy source, consideration must be given both its technological capabilities and market environment in which it finds itself. structure thinking about this, EUROfusion takes three potential future power plant options define what features they have, therefore gaps between a current DEMOnstration concept commercialisable option. Approaching issue this way highlights role that such play beyond simply demonstrating...
The stellarator concept is a promising candidate for steady-state fusion power plant, but currently lacking behind the tokamak developments. In order to bring maturity, new EUROfusion Task has been established within Work Package Prospective Research & Development (WP-PRD) called Stellarator Power Plant Studies (SPPS). This task addresses stellarator-specific engineering aspects relevant on way reactor. paper reports strategy of this and provides an overview over ongoing activities as well...
As well as the mainstream activities aimed at delivering DEMO to meet high-level targets and timetable outlined elsewhere, there is a parallel stream of research investigating developing technology provide alternative risk-mitigating options for and/or fusion power plant, targeting delivery commercially viable energy. This programme termed Prospective Research Development (PRD). The focus on into promising technologies that do not form part main due their current readiness level or higher...
The heating & current drive (H&CD) systems in a DEMOnstration fusion power plant are one of the major energy consumers. Due to its high demand electrical H&CD efficiency optimization is an important goal DEMO development. for DEMO, based on physics scenarios different plasma phases, needed initiation phases (incl. breakdown), ramp-up, H-mode, burn control, controlled ramp-down, MHD control and other functions. Plasma will need significant installed power, though not continuously used....
The EUROfusion roadmap for fusion research was recently updated, and it describes a clear set of missions associated goals on the route to commercial electricity. Beyond ITER, main target program is development DEMO, technology demonstrator which will produce substantial net electrical output, breed its own fuel, demonstrate supporting technologies such as automated remote handling systems aimed high availability. Work DEMO has already proven extremely valuable in identifying design...