Tritium related studies at the JET facilities

R. Lässer (Corresponding Author), N. Bekris, A.C. Bell, C. Caldwell-Nichols, I. Cristescu, S. Ciattaglia, P. Coad, Ch. Day, M. Glugla, Jari Likonen, D.K. Murdoch, S. Rosanvallon, F. Scaffidi-Argentina

Research output: Contribution to journalArticleScientificpeer-review

3 Citations (Scopus)

Abstract

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.
Original languageEnglish
Pages (from-to)75-80
Number of pages6
JournalFusion Engineering and Design
Volume69
Issue number1-4
DOIs
Publication statusPublished - 2003
MoE publication typeA1 Journal article-refereed

Fingerprint

Tritium
Fusion reactions
Tile
Plasmas
Erosion
Recovery
Catalysts
Liquids
Polymers
Gases
Water
Experiments

Keywords

  • tritium
  • JET
  • fusion energy
  • fusion reactors
  • ITER

Cite this

Lässer, R., Bekris, N., Bell, A. C., Caldwell-Nichols, C., Cristescu, I., Ciattaglia, S., ... Scaffidi-Argentina, F. (2003). Tritium related studies at the JET facilities. Fusion Engineering and Design, 69(1-4), 75-80. https://doi.org/10.1016/S0920-3796(03)00248-5
Lässer, R. ; Bekris, N. ; Bell, A.C. ; Caldwell-Nichols, C. ; Cristescu, I. ; Ciattaglia, S. ; Coad, P. ; Day, Ch. ; Glugla, M. ; Likonen, Jari ; Murdoch, D.K. ; Rosanvallon, S. ; Scaffidi-Argentina, F. / Tritium related studies at the JET facilities. In: Fusion Engineering and Design. 2003 ; Vol. 69, No. 1-4. pp. 75-80.
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abstract = "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.",
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Lässer, R, Bekris, N, Bell, AC, Caldwell-Nichols, C, Cristescu, I, Ciattaglia, S, Coad, P, Day, C, Glugla, M, Likonen, J, Murdoch, DK, Rosanvallon, S & Scaffidi-Argentina, F 2003, 'Tritium related studies at the JET facilities', Fusion Engineering and Design, vol. 69, no. 1-4, pp. 75-80. https://doi.org/10.1016/S0920-3796(03)00248-5

Tritium related studies at the JET facilities. / Lässer, R. (Corresponding Author); Bekris, N. ; Bell, A.C.; Caldwell-Nichols, C.; Cristescu, I.; Ciattaglia, S.; Coad, P.; Day, Ch.; Glugla, M.; Likonen, Jari; Murdoch, D.K.; Rosanvallon, S.; Scaffidi-Argentina, F.

In: Fusion Engineering and Design, Vol. 69, No. 1-4, 2003, p. 75-80.

Research output: Contribution to journalArticleScientificpeer-review

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

VL - 69

SP - 75

EP - 80

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

IS - 1-4

ER -

Lässer R, Bekris N, Bell AC, Caldwell-Nichols C, Cristescu I, Ciattaglia S et al. Tritium related studies at the JET facilities. Fusion Engineering and Design. 2003;69(1-4):75-80. https://doi.org/10.1016/S0920-3796(03)00248-5