Please cite this article in press as: J. Prok ˚ upek, et al., HELCZA—High heat flux test facility for testing ITER EU first wall components, Fusion Eng. Des. (2017), http://dx.doi.org/10.1016/j.fusengdes.2017.03.059 ARTICLE IN PRESS G Model FUSION-9239; No. of Pages 4 Fusion Engineering and Design xxx (2017) xxx–xxx Contents lists available at ScienceDirect Fusion Engineering and Design journal homepage: www.elsevier.com/locate/fusengdes HELCZA—High heat flux test facility for testing ITER EU first wall components Jan Prok ˚ upek a, , Karel Samec a , Richard Jílek a , Pierre Gavila b , Sobˇ eslav Neufuss c , Slavomír Entler d a Centrum yzkumu ˇ Reˇ z, s.r.o., Hlavní 130, 250 68 Husinec- ˇ Reˇ z, Czech Republic b Fusion for Energy, Josep Pla, 2, Torres Diagonal Litoral B3, 08019 Barcelona, Spain c NUVIA a.s., Modˇ rínová 1094, 674 01 rebíˇ c, Czech Republic d Institute of Plasma Physics of the CAS, Za Slovankou 3, 182 00 Prague 8, Czech Republic h i g h l i g h t s High heat flux test facility HELCZA for testing full-scale ITER plasma facing components. Electron beam based heat flux cyclic loading. Testing Beryllium containing first wall panels, divertor inner vertical target and ICRF antenna screens. a r t i c l e i n f o Article history: Received 3 October 2016 Received in revised form 8 February 2017 Accepted 13 March 2017 Available online xxx Keywords: HELCZA High heat flux Electron beam testing Test facility Plasma facing components First wall Divertor a b s t r a c t The ITER first wall panels are exposed directly to thermonuclear plasma and must extract heat loads of approximately 2 MW/m 2 (normal heat flux) to 4.7 MW/m 2 (enhanced heat flux). The panels are qualified through high heat flux cyclic testing before installation in ITER. Initially, the first wall panel prototypes will undergo full-power tests, they will be followed by the pre-series panels and finally the series ones. The experimental complex HELCZA (High Energy Load CZech Assembly) has been completed and is currently in the commissioning phase. HELCZA shall be optimised to provide a cyclic heating of the ITER EU first wall panels with a heat flux in the multi-MW/m 2 range using an 800 kW electron beam. On a reduced area it is possible to reach GW/m 2 scale. Total available test area in HELCZA is 4 m 2 depending on the experimental setup. Operational conditions of the HELCZA facility enable the temperature of the cooling water to be set between 25 C and 320 C, within a pressure range up to 15 MPa. The cooling system provides an optimal flow rate up to 40 m 3 /h independent of the pressure. © 2017 Elsevier B.V. All rights reserved. 1. Introduction The plasma-facing components comprising the first wall (FW) and divertor targets will be the most heat-loaded components of ITER. Among other challenges, they must accommodate a high heat flux from the plasma. The ITER FW panels must extract heat loads of about 2 MW/m 2 (normal heat flux design) and 4.7 MW/m 2 (enhanced heat flux design). The panels will be qualified through high heat flux cyclic testing in a dedicated facility before their installation in ITER [1]. In Europe there exists several electron beam facilities for cyclic heat load testing. FE200 in France [2] for mock-up testing, Corresponding author. E-mail address: Jan.Prokupek@cvrez.cz (J. Prok ˚ upek). JUDITH II in Germany [3] for semi-prototypes of FW panels test- ing, IDTF in Russia [4] for full scale divertor component testing are all electron-beam based test facilities. Furthermore, some other smaller facilities are or have been in operation [5,6]. However, their characteristics do not allow full-scale FW testing, which is the pri- mary goal of HELCZA. The experimental complex HELCZA is dedicated to the series of acceptance tests of the FW panels, divertor inner vertical targets and ICRF antenna screens, which are part of the EU contribution to the ITER project. The FW panel prototypes will undergo full-power tests followed by the pre-series and finally the series panels tests. HELCZA has recently been completed and is now in its commission- ing phase. http://dx.doi.org/10.1016/j.fusengdes.2017.03.059 0920-3796/© 2017 Elsevier B.V. All rights reserved.