Browse > Article
http://dx.doi.org/10.1016/j.net.2019.03.013

High heat flux limits of the fusion reactor water-cooled first wall  

Zacha, Pavel (Czech Technical University in Prague)
Entler, Slavomir (Czech Technical University in Prague)
Publication Information
Nuclear Engineering and Technology / v.51, no.5, 2019 , pp. 1251-1260 More about this Journal
Abstract
The water-cooled WCLL blanket is one of the possible candidates for the blanket of the fusion power reactors. The plasma-facing first wall manufactured from the reduced-activation ferritic-martensitic steel Eurofer97 will be cooled with water at a typical pressurized water reactor (PWR) conditions. According to new estimates, the first wall will be exposed to peak heat fluxes up to $7MW/m^2$ while the maximum operated temperature of Eurofer97 is set to $550^{\circ}C$. The performed analysis shows the capability of the designed flat first wall concept to remove heat flux without exceeding the maximum Eurofer97 operating temperature only up to $0.75MW/m^2$. Several heat transfer enhancement methods (turbulator promoters), structural modifications, and variations of parameters were analysed. The effects of particular modifications on the wall temperature were evaluated using thermo-hydraulic three-dimensional numerical simulation. The analysis shows the negligible effect of the turbulators. By the combination of the proposed modifications, the permitted heat flux was increased up to $1.69MW/m^2$ only. The results indicate the necessity of the re-evaluation of the existing first wall concepts.
Keywords
High heat flux; Thermal performance factors; Turbulator promoters; First wall; Cooling; CFD;
Citations & Related Records
연도 인용수 순위
  • Reference
1 F. Romanelli, Fusion Electricity, A Roadmap to the Realization of Fusion Energy, EFDA, EU, 2012.
2 R. Wenninger, et al., The DEMO wall load challenge, Nucl. Fusion 57 (2017), 046002 (11pp).   DOI
3 G. Federici, et al., European DEMO design strategy and consequences for materials, Nucl. Fusion 57 (2017), 092002 (26pp).   DOI
4 C. Reux, et al., Runaway beam studies during disruptions at JET-ILW, J. Nucl. Mater. 463 (2015) 143-149.   DOI
5 J. Horacek, et al., Feasibility study of fast swept divertor strike point suppressing transient heat fluxes in tokamaks DEMO and COMPASS-Upgrade, Fusion Eng. Des. 123 (2017) 646-649.   DOI
6 D. Maisonnier, et al., A Conceptual Study of Commercial Fusion Power Plants, Final Report of the European Fusion Power Plant Conceptual Study (PPCS), 2005. EFDA-RP-RE-5.0.
7 J. Aubert, et al., Development of the water-cooled lithium lead blanket for DEMO, Fusion Eng. Des. 89 (2014) 1386-1391.   DOI
8 J. Aubert, et al., Optimization of the first wall for the DEMO water cooled lithium lead blanket, Fusion Eng. Des. 98-99 (2015) 1206-1210.   DOI
9 R. Aymar, et al., The ITER design, Plasma Phys. Contr. Fusion 44 (2002) 519-565.   DOI
10 S. Entler, et al., Approximation of the economy of fusion energy, Energy 152 (2018) 489-497.   DOI
11 G. Zdaniuk, et al., Experimental determination of heat transfer and friction in helically-finned tubes, Exp. Therm. Fluid Sci. 32 (2008) 761-775.   DOI
12 T.R. Barrett, et al., Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma-facing components, Fusion Eng. Des. 109-111 (2016) 917-924.   DOI
13 L.V. Boccaccini, et al., Objectives and status of EUROfusion DEMO blanket studies, Fusion Eng. Des. 109-111 (2016) 1199-1206.   DOI
14 J. Prokupek, et al., HELCZA - high heat flux test facility for testing ITER EU first wall components, Fusion Eng. Des. 124 (2017) 187-190.   DOI
15 A. Hasanpour, et al., A review study on twisted tape inserts on turbulent flow heat exchangers: the overall enhancement ratio criteria, Int. Commun. Heat Mass Transf. 55 (2014) 53-62.   DOI
16 X. Zhang, et al., Numerical studies on heat transfer and friction factor characteristics of a tube fitted with helical screw-tape without core-rod inserts, Int. J. Heat Mass Transf. 60 (2013) 490-498.   DOI
17 M.K. Bhuiya, et al., Heat transfer and friction factor characteristics in turbulent flow through a tube fitted with perforated twisted tape inserts, Int. Commun. Heat Mass Transf. 46 (2013) 49-57.   DOI
18 L.J. Brognaux, et al., Single-phase heat transfer in micro-fin tubes, Int. J. Heat Mass Transf. 40 (1997) 4345-4357.   DOI
19 P.K. Nagarajan, et al., Studies on heat transfer and friction factor characteristics of turbulent flow through a micro-finned tube fitted with left-right inserts, Appl. Therm. Eng. 30 (2010) 1666-1672.   DOI
20 P. Sivashanmugam, et al., Experimental studies on heat transfer and friction factor characteristics of turbulent flow through a circular tube fitted with regularly spaced helical screw-tape inserts, Appl. Therm. Eng. 27 (2007) 1311-1319.   DOI
21 B. Salam, et al., Heat transfer enhancement in a tube using rectangular-cut twisted tape insert, Procedia Engineering 56 (2013) 96-103.   DOI
22 A. Mwesigye, et al., Heat transfer and entropy generation in a parabolic trough receiver with wall-detached twisted tape inserts, Int. J. Therm. Sci. 99 (2016) 238-257.   DOI
23 P. Eiamsa-ard, et al., A case study on thermal performance assessment of a heat exchanger tube equipped with regularly-spaced twisted tapes as swirl generators, Case Studies in Thermal Engineering 3 (2014) 86-102.   DOI
24 J. Guo, et al., A numerical study on heat transfer and friction factor characteristics of laminar flow in a circular tube fitted with center-cleared twisted tape, Int. J. Therm. Sci. 50 (2011) 1263-1270.   DOI
25 J. Mahaffy, et al., Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications, NEA/CSNI/R, 2007, p. 5.
26 J.H. You, et al., Conceptual design studies for the European DEMO divertor:rationale and first results, Fusion Eng. Des. 109-111 (2016) 1598-1603.   DOI