From W7-X to a HELIAS fusion power plant: On engineering considerations for next-step stellarator devices

Warmer, F.; Bykov, V.; Drevlak, M.; Häußler, A.; Fischer, U.; Stange, T.; Beidler, C. D.; Wolf, R. C.

doi:10.1016/j.fusengdes.2017.05.034

Cited by 26 publications

(20 citation statements)

References 20 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The current HELIAS concept is a large aspect ratio stellarator consisting of five identical field periods [5,10,11]. From a design point of view, it is thus meaningful that the BB heat transfer system follows this symmetry.…”

Section: Primary Heat Transfer Systemmentioning

confidence: 99%

First considerations on the Balance of Plant for a HELIAS fusion power plant

Warmer

Bubelis

2019

Fusion Engineering and Design

View full text Add to dashboard Cite

A first conceptual design of the Balance of Plant for a HELIAS power plant equipped with a Helium Cooled Pebble Bed (HCPB) Breeder Blanket (BB) is presented in this work. 5 inboard and 10 outboard cooling loops extract the heat from the blanket. Heat exchangers are used to transfer the thermal power from the helium to solar salt, which transports the heat out of the stellarator building and into an industrial 2-tank thermal energy storage system (IHTS/ESS). For electricity generation, the heat from the solar salt is transferred to the feedwater, which is boiled and superheated in the steam generator and then used in the turbine.In absence of a detailed design for the HCPB BB in stellarator geometry and the ex-vessel piping, a sensitivity study was carried out for the pressure drop of the cooling loops which showed that even small changes in the pressure drop have significant impact on the required pumping power.Finally, an exemplary runtime scenario is presented demonstrating the capability of a stellarator fusion power plant equipped with an IHTS/ESS to operate very flexibly (±20%) in an envisaged dynamic future energy system. Considering demand forecasts and the ESS, a stellarator fusion power plant (FPP) seems well equipped to cope with fluctuating grid demands within its technical limitations. If the conceptual idea for the HELIAS BoP as presented in this paper can be confirmed by more detailed technical studies, then a stellarator FPP could potentially contribute to grid stabilization in a future energy system while replacing fossil fuel power plants as a sustainable energy source.

show abstract

Section: Primary Heat Transfer Systemmentioning

confidence: 99%

First considerations on the Balance of Plant for a HELIAS fusion power plant

Warmer

Bubelis

2019

Fusion Engineering and Design

View full text Add to dashboard Cite

show abstract

“…For such purpose, the BB is made by Li compound T breeding material that regenerates T by 6 Li(n, T) and 7 Li(n, n T) reactions. In the case of the Dual Coolant Lithium Lead (DCLL) BB concept the breeder material is PbLi in the eutectic composition: 84.3% Pb and 15.7% Li [9].…”

Section: The Dual Coolant Lithium Lead Bb Concept: Major Features And...mentioning

confidence: 99%

“…Substantial progress has been made in understanding stellarator plasmas and important advancements have been already obtained on the physics aspects, especially thanks to the operation of the Weldenstein 7-X (W7-X) stellarator [5]. This has lead the Eurofusion community to define the HELIAS (HELical-axis Advanced Stellarator) [6] type stellarator development as one of its long term missions (Mission 8 within the European roadmap towards fusion [7]), as an alternative to the main DEMO tokamak line. All the related engineering and technological activities are included in the Work Package Prospectives R&D: Stellarator Power Plant Studies (WPPRD SPPS).…”

Section: Introductionmentioning

confidence: 99%

Neutronic Assessments towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket

Sosa¹,

Palermo²

2023

Preprint

View full text Add to dashboard Cite

The Stellarator Power Plant Studies Prospective R&amp;D Work Package among the Eurofusion Programme was settled to bring the stellarator engineering to maturity, so that stellarators and particularly the HELIAS (HELical-axis Advanced Stellarator) configuration could be a possible alternative to tokamaks. However, its complex geometry makes designing a Breeding Blanket (BB) that fully satisfies the requirements for such an HELIAS configuration a difficult task. Taking advantage of the acquired experience in BB design for DEMO tokamak, CIEMAT is leading the development of a Dual Coolant Lithium Lead (DCLL) BB for a HELIAS configuration. To answer the specific HELIAS challenges new and advanced solutions have been proposed, as the use of fully detached First Wall (FW) based on liquid metal Capillary Porous Systems (CPS). These proposed solutions have been studied in a simplified 1D model that can help to estimate the relative variations in Tritium Breeding Ratio (TBR) and displacement per atom (dpa) to verify their effectiveness to simplify the BB integration, improve the machine availability while keeping the main BB nuclear functions (i.e. tritium breeding, heat extraction and shielding). This preliminary study demonstrates that the use of FW CPS would reduce the radiation damage received by the blanket without compromising its tritium breeding performance.

show abstract

“…The enclosure of this reactor consists of 50 non-level rewinds and 20 lat rewinds. The rewinds create a magnetic ield that encloses a hydrogen plasma with a temperature of more than 100 million degrees [3,4] (Figure 1).…”

Section: Introductionmentioning

confidence: 99%

Magnetohydrodynamic (MHD) stability of wendelstain7-X reactor with reszistive wall (RWMs)

Pazirandeh¹,

Shariati²

2021

Int J Phys Res Appl

View full text Add to dashboard Cite

Plasma stability is the biggest challenge facing the nuclear fusion industry. One of the best methods of stability study is magnetohydrodynamic (MHD) equations, which has two linear and nonlinear states. Usually linear stability analysis is used to describe the MHD state, which is obtained by linearizing nonlinear equations. The reactor under study is the W7-X reactor, which is an optimal example of a stellaratoric system. The question raised in this research is how to create suitable conditions for the formation and formation of plasma and heat transfer produced by the melting reaction. Many efforts have been made in this direction, but still the record holder for plasma state maintenance belongs to the international ITER project and around 1000S. However, IPP researchers at the Max Planck Institute in Germany (maker of the W7-X reactor) predicted that by 2020 they would produce a pulse of 30 minutes. The numerical method is used to investigate the stability of the reactor. In this paper, boundary conditions were expressed in terms of resistance wall. With the help of the mathematical Matlab software, magnetic field values were obtained from experimental reports extracted from the Max Planck Institute for various values of β. From the values obtained, it was concluded that the appropriate field value is β = 5 according to the ideal MagnetoHydroDynamic state and the interval defined by the Max Planck Institute.

show abstract

From W7-X to a HELIAS fusion power plant: On engineering considerations for next-step stellarator devices

Cited by 26 publications

References 20 publications

First considerations on the Balance of Plant for a HELIAS fusion power plant

First considerations on the Balance of Plant for a HELIAS fusion power plant

Neutronic Assessments towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket

Magnetohydrodynamic (MHD) stability of wendelstain7-X reactor with reszistive wall (RWMs)

Contact Info

Product

Resources

About