TY - JOUR
T1 - A tritium diagnostic and trap for JUDITH - first results in disruption simulation experiments with neutron irradiated beryllium during cyclic electron beam testing
AU - Schmidt, A.
AU - Uytdenhouwen, Inge
AU - Kuhnlein, W.
AU - Roedig, M.
AU - Linke, J.
AU - Hirai, T.
AU - Pintsuk, G.
A2 - Chaouadi, Rachid
N1 - Score = 10
PY - 2008/9/27
Y1 - 2008/9/27
N2 - In the present study, the effect of disruptions on beryllium has been studied. Disruptions are simulated in the electron beam facility JUDITH by high energetic pulses of up to 250 MJ/m2. Under these loads, the beryllium surface may roughen combined with the forming of cracks. During the experiments, a special problem arises from the fact that during the neutron irradiation beryllium transmutes to tritium. This tritium is bound in the beryllium matrix, but during the heating of the samples, the tritium may be set free and through the vacuumpump itmay be released to the environment. In order to avoid and to quantify this release of tritium, a special tritium trap has been constructed. In this tritium trap the gas is pumped by means of a metal bellows pump through a catalyst tube filled with copper oxide. At a temperature of 300 ◦C, the tritium is oxidized to HTO. This HTO is lead through gas washing bottles filled with water. Here approximately 98% of the released tritium is caught. The temperatures in the process are controlled
by thermocouples, and the tritium content is controlled by a tritium gas monitor and in addition with a liquid scintillation counter (LSC).
AB - In the present study, the effect of disruptions on beryllium has been studied. Disruptions are simulated in the electron beam facility JUDITH by high energetic pulses of up to 250 MJ/m2. Under these loads, the beryllium surface may roughen combined with the forming of cracks. During the experiments, a special problem arises from the fact that during the neutron irradiation beryllium transmutes to tritium. This tritium is bound in the beryllium matrix, but during the heating of the samples, the tritium may be set free and through the vacuumpump itmay be released to the environment. In order to avoid and to quantify this release of tritium, a special tritium trap has been constructed. In this tritium trap the gas is pumped by means of a metal bellows pump through a catalyst tube filled with copper oxide. At a temperature of 300 ◦C, the tritium is oxidized to HTO. This HTO is lead through gas washing bottles filled with water. Here approximately 98% of the released tritium is caught. The temperatures in the process are controlled
by thermocouples, and the tritium content is controlled by a tritium gas monitor and in addition with a liquid scintillation counter (LSC).
KW - beryllium
KW - JUDITH
KW - crack behaviour
KW - tritium trap
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_93151
UR - http://knowledgecentre.sckcen.be/so2/bibref/5441
U2 - 10.1016/j.fusengdes.2008.08.017
DO - 10.1016/j.fusengdes.2008.08.017
M3 - Article
SN - 0920-3796
VL - 83
SP - 1108
EP - 1113
JO - fusion engineering and design
JF - fusion engineering and design
IS - 7-9
T2 - 8th ISFNT (International Symposium of Fusion Nuclear Technology)
Y2 - 30 September 2007 through 5 October 2007
ER -