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
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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 v´ 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 Tˇ 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.