The present paper describes irradiation devices proposed by SCK CEN to test
segments of water cooled lithium-lead blankets (WCLL), and in particular t
heir double-wall tubes (DWT), under irradiation in the BR2 reactor. The pur
pose of the first experiment is to assess the efficiency of a tritium perme
ation barrier (TPB) coating at the outer surface of the DWT. Hence, two DWT
segments are plunged in a lithium-lead pool. The inside of the DWT is flus
hed by helium and collects the tritium permeating through the wall. One of
the DWTs has received a TPB coating, the other not, so that comparative mea
surements are possible. For the second experiment, a DWT segment is heated
by the gamma flux of BR2 and cooled at the inside by pressurised water. Hen
ce, the temperature gradient tends to separate the two tubes. The purpose i
s to verify how the brazing agent performs at doses up to 3 dpa. The irradi
ation device is installed inside the central hole of a BR2 fuel element, in
order to maximise the fast neutron component of the flux received by the t
arget. As an attractive alternative, the utilisation of the PWR loop Callis
to is also proposed. (C) 2000 Elsevier Science B.V. All rights reserved.