Please cite this article in press as: R. Fetzer, et al., Efficiency of water coolant for DEMO divertor, Fusion Eng. Des. (2014),
http://dx.doi.org/10.1016/j.fusengdes.2014.11.012
ARTICLE IN PRESS
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FUSION-7646; No. of Pages 4
Fusion Engineering and Design xxx (2014) xxx–xxx
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Fusion Engineering and Design
jo ur nal home p age: www.elsevier.com/locate/fusengdes
Efficiency of water coolant for DEMO divertor
Renate Fetzer
∗
, Yuri Igitkhanov, Boris Bazylev
Karlsruhe Institute of Technology, Karlsruhe, Germany
a r t i c l e i n f o
Article history:
Received 2 September 2014
Received in revised form 15 October 2014
Accepted 24 November 2014
Available online xxx
Keywords:
DEMO
Tungsten monoblock
Water cooled divertor
ELMs
a b s t r a c t
Up to now, water-cooled divertor concepts have been developed for limited incident fluxes without taking
into account transient power loadings. In this paper we analyzed the efficiency of water as a coolant for
the particular PFC tungsten monoblock shield with a cooling tube made from Cu alloy (Cu OFHC) as a
laminate adjacent to W and a low activation martensitic steel (Eurofer) as inner tube contacting the
coolant. Thermal analysis is carried out by using the code MEMOS, which simulates W armour damage
under the repetitive ELM heat loads. We consider cooling conditions which allow one to keep relatively
high material temperatures (in the range 300–600
◦
C) thus minimizing Eurofer embrittlement under
neutron irradiation. Expected DEMO I and DEMO II heat loads including type I ELMs are found to cause
melting of the W surface during unmitigated ELMs. By mitigation of the ELMs melting of W is avoided.
DEMO I operation under these conditions is save for cooling at water pressure 15.5 MPa and temperature
325
◦
C, while for DEMO II with mitigated ELMs the critical heat flux is exceeded and safe operation is not
provided.
© 2014 Elsevier B.V. All rights reserved.
1. Introduction
The proper choice of coolant and cooling conditions is important
for a Fusion Power Plant DEMO. Selection of a suitable coolant for
the blanket and divertor in DEMO is made difficult by the number
of factors that must be considered, such as an efficient removal
of the high amount of energy at operating temperatures com-
patible with structural materials, thermal and radiation stability,
required pumping power, coolant availability, economics, etc. The
most credible option for DEMO nowadays seems to be helium [1].
However, helium as a coolant has some drawbacks. The high tem-
perature He-cooling technologies are still not developed for fusion
reactor conditions and it is far from certain that He-related R&D
will be successfully completed in time for DEMO. Therefore it is
appropriate to consider the credibility of a water cooled DEMO as
a back-up option.
Up to now, water-cooled divertor technologies have been devel-
oped for incident heat fluxes limited to 15–20 MW/m
2
[2,3]. DEMO
concepts that use steel (e.g., Eurofer) as a heat sink material
and tungsten as armour must be tested for incident fluxes at
least up to 25 MW/m
2
in case of transient heat loads. One of
the main concerns in this case is the Eurofer embrittlement at
around 300
◦
C under neutron irradiation [4] and there would be
∗
Corresponding author. Tel.: +49 72160824263.
E-mail address: renate.fetzer@kit.edu (R. Fetzer).
significant benefits in operating DEMO at relatively high Eurofer
temperatures (in the range 300–500
◦
C). It should be noted that
heat sink material temperatures in all tokamaks presently oper-
ating or under construction (including ITER) are below 300
◦
C. No
foreseen device will therefore provide demonstration of in-vessel
operation in DEMO relevant ranges of plasma facing component
temperatures. This is a significant gap in the fusion programme
worldwide, which needs to be covered by at least numerical
modelling.
In this paper we analyzed the efficiency of water as a coolant
for the particular PFC tungsten monoblock shield with a cooling
tube made from Cu alloy OFHC (oxygen free high conductivity Cu)
as a laminate adjacent to W and a low activation martensitic steel
(Eurofer) as inner tube contacting the coolant. Eurofer has been
selected because it is the reference candidate structural material
due to its expected capability of withstanding neutron damages
higher than 70 dpa, corresponding to 3–4 years of DEMO divertor
continuous operations.
The design of the DEMO divertor module is taken as suggested
by Li-Puma et al. [4], see Fig. 1. The diameter of the coolant tube
is 6 mm, the thicknesses of the Eurofer and Cu OFHC layers are,
respectively, 0.42 mm and 1 mm. The W armour is 3.5 mm thick at
its thinnest position. The described design has been found to be the
optimum in terms of thermo-mechanical properties for stationary
heat loads of 10 MW/m
2
and water cooling with inlet water tem-
perature 325
◦
C, pressure 15.5 MPa, and velocity 20 m/s [4]. Water
temperature and pressure correspond to the cooling conditions in
http://dx.doi.org/10.1016/j.fusengdes.2014.11.012
0920-3796/© 2014 Elsevier B.V. All rights reserved.