TY - JOUR
T1 - Tritium related studies at the JET facilities
AU - Lässer, R.
AU - Bekris, N.
AU - Bell, A.C.
AU - Caldwell-Nichols, C.
AU - Cristescu, I.
AU - Ciattaglia, S.
AU - Coad, P.
AU - Day, Ch.
AU - Glugla, M.
AU - Likonen, Jari
AU - Murdoch, D.K.
AU - Rosanvallon, S.
AU - Scaffidi-Argentina, F.
PY - 2003
Y1 - 2003
N2 - The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and of handling Be and therefore best suited to study tritium and fusion related issues. JET is now managed under the European Fusion Development Agreement (EFDA) and experiments, enhancements and technology issues are organized as Scientific and Technical (S/T) tasks within various Task Forces (TFs). A large variety of different activities is performed within the fusion technology (FT) TF. A brief summary of FT-studies related to tritium is given presenting topics such as tritium inventory in flakes and tiles, tritium depth profiles in plasma facing components (PFCs), development of a facility for full recovery of the tritium in flakes and tiles, erosion and deposition of plasma exposed materials determined by surface sensitive techniques, development of detritiation techniques for different waste categories, characterization of packing/catalyst combinations for liquid phase catalytic exchange column and design studies of a water detritiation plant using either a solid polymer or KOH electrolyser, test of ITER cryo-panels in the JET Active Gas Handling System, etc.
AB - The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and of handling Be and therefore best suited to study tritium and fusion related issues. JET is now managed under the European Fusion Development Agreement (EFDA) and experiments, enhancements and technology issues are organized as Scientific and Technical (S/T) tasks within various Task Forces (TFs). A large variety of different activities is performed within the fusion technology (FT) TF. A brief summary of FT-studies related to tritium is given presenting topics such as tritium inventory in flakes and tiles, tritium depth profiles in plasma facing components (PFCs), development of a facility for full recovery of the tritium in flakes and tiles, erosion and deposition of plasma exposed materials determined by surface sensitive techniques, development of detritiation techniques for different waste categories, characterization of packing/catalyst combinations for liquid phase catalytic exchange column and design studies of a water detritiation plant using either a solid polymer or KOH electrolyser, test of ITER cryo-panels in the JET Active Gas Handling System, etc.
KW - tritium
KW - JET
KW - fusion energy
KW - fusion reactors
KW - ITER
U2 - 10.1016/S0920-3796(03)00248-5
DO - 10.1016/S0920-3796(03)00248-5
M3 - Article
SN - 0920-3796
VL - 69
SP - 75
EP - 80
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
IS - 1-4
ER -
