Thermal-hydraulics of helium cooled First Wall channels and scoping investigations on performance improvement by application of ribs and mixing devices

Arbeiter, Frederik; Bachmann, Christian; Ilić, Milica; Schwab, Florian; Sieglin, B.; Wenninger, R.

doi:10.1016/j.fusengdes.2016.01.008

Cited by 25 publications

(18 citation statements)

References 12 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This may prove to be an appropriate level for a uniform, normal scenario load; but peaked loads due to magnetic field ripple, plasma transients, wall dimensional intolerance, etc, could be an order of magnitude higher. Baseline FW concepts are based on helium and water cooling of EUROFER channels [10][11][12][13][14], which are reported to have heat flux limits of about 1 MW/m 2 and 1.5 MW/m 2 , respectively. Importantly, these limits are based on engineering analyses however they neither account for irradiated material properties nor the presence of the tungsten armour.…”

Section: Fw Conceptsmentioning

confidence: 99%

“…The FW topology and cooling channel technology [12,13] are currently an active design task and a function of the architecture as per Table 1. As in the divertor, the proposed FW armour material is tungsten, although it is expected that the thickness can be less; nominally 2mm is assumed to be sufficient although this will vary with position around the wall.…”

Section: Fw Pfcsmentioning

confidence: 99%

See 1 more Smart Citation

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

Barrett

Ellwood

Pérez

et al. 2016

Fusion Engineering and Design

View full text Add to dashboard Cite

The European DEMO power reactor is currently under conceptual design within the EUROfusion Consortium. One of the most critical activities is the engineering of the plasma-facing components (PFCs) covering the plasma chamber wall, which must operate reliably in an extreme environment of neutron irradiation and surface heat and particle flux, while also allowing sufficient neutron transmission to the tritium breeding blankets. A systems approach using advanced numerical analysis is vital to realising viable solutions for these first wall and divertor PFCs. Here, we present the system requirements and describe bespoke thermo-mechanical and thermo-hydraulic assessment procedures which have been used as tools for design. The current first wall and divertor designs are overviewed along with supporting analyses. The PFC solutions employed will necessarily vary around the wall, depending on local conditions, and must be designed in an integrated manner by analysis and physical testing.

show abstract

Section: Fw Conceptsmentioning

confidence: 99%

Section: Fw Pfcsmentioning

confidence: 99%

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

Barrett

Ellwood

Pérez

et al. 2016

Fusion Engineering and Design

View full text Add to dashboard Cite

show abstract

“…The main reasons behind this choice are exactly in its declarative nature, which allows to develop the model of new objects by simply writing the model equations, and in the extensive experience on it, e.g. for the modelling of the superconducting magnets cooling system [3], developed during the last years at the Energy Department of Politecnico di Torino. Moreover, several libraries for the modelling of energy-related systems are freely available in Modelica.…”

Section: Modelling Approach and Equationsmentioning

confidence: 99%

“…To compute the Fanning friction factor for the side parts of the channels, the Blasius correlation [20, p. 490] was used. In the front part the channel is assumed to be ribbed on its plasma-facing wall to improve the heat transfer ( Figure 18); the Fanning friction factor correlation = 0.1122 ⋅ −0.1854 (9) has been fitted by regression based on the data in [3,21]. Figure 18: CAD drawing of the ribbed front wall channel [22].…”

Section: Boundary Conditionsmentioning

confidence: 99%

See 1 more Smart Citation

Dynamic thermal-hydraulic modelling of the EU DEMO HCPB breeding blanket cooling loops

Froio

Bachmann²,

Cismondi³

et al. 2016

Progress in Nuclear Energy

View full text Add to dashboard Cite

A global, system-level thermal-hydraulic model of the EU DEMO tokamak fusion reactor is currently under development and implementation in a suitable software at Politecnico di Torino, including the relevant heat transfer and fluid dynamics phenomena, which affect the performance of the different cooling circuits and components and their integration in a consistent design. The model is based on an object-oriented approach using the Modelica language, which easily allows to preserve the high modularity required at this stage of the design. The first module of the global model will simulate the blanket cooling system and will be able to investigate different coolant options and different cooling schemes, to be adapted to the different blanket systems currently under development in the Breeding Blanket (BB) project. The paper presents the Helium-Cooled Pebble Bed (HCPB) module of the EU DEMO blanket cooling loops system model. The model is used to compare different schemes for the cooling of the different components of the HCPB BB, and to suggest improvements aimed at optimizing the pumping power required by the cooling system. The model is then used to analyse a pulsed scenario, characteristic of the EU DEMO operation.

show abstract

Characterization of the cooling channels of First Wall Mock-up dedicated to the HCPB TBM qualification

Abou-Sena

Boccaccini

Ghidersa

et al. 2017

Fusion Engineering and Design

View full text Add to dashboard Cite

The First Wall (FW) of the EU Helium Cooled Pebble Bed (HCPB) Test Blanket Module (TBM) faces the fusion plasma and experiences high heat fluxes; therefore its cooling channels design is a key R&D task for qualifying the HCPB TBM for the fusion reactors ITER and DEMO. Within the manufacturing and qualification activities performed in KIT for the HCPB TBM, a First Wall Mock-up (FWM) was designed and manufactured. The objective of this study is to characterize the hydrodynamic behaviour of the FWM cooling channels by investigating the coolant pressure loss for each channel. The FWM has a shape of rectangular prism (710 mm × 405 mm × 45 mm) and 10 U-shaped cooling channels which have a square cross section (15 mm × 15 mm) with rounded corners of 4 mm radius. The FWM was integrated into an experimental gas loop that has the relevant instrumentation and piping system for measuring and controlling the gas (e.g. compressed air of 6 bar abs.) flow parameters. This paper presents the experimental results of measuring the pressure loss across the FWM cooling channels and discusses its main causes. In addition, the experimental results are compared with theoretical values obtained from relevant models and formula available in the literature. The results of this study will support the qualification of the HCPB TBM mock-ups which will be tested at fusion-relevant heat flux and helium cooling in the Helium Loop Karlsruhe (HELOKA) facility.

show abstract

Thermal-hydraulics of helium cooled First Wall channels and scoping investigations on performance improvement by application of ribs and mixing devices

Cited by 25 publications

References 12 publications

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

Dynamic thermal-hydraulic modelling of the EU DEMO HCPB breeding blanket cooling loops

Characterization of the cooling channels of First Wall Mock-up dedicated to the HCPB TBM qualification

Contact Info

Product

Resources

About