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Title: Tritium processing for the European test blanket systems: current status of the design and development strategy

Abstract

Tritium processing technologies of the two European Test Blanket Systems (TBS), HCLL (Helium Cooled Lithium Lead) and HCPB (Helium Cooled Pebble Bed), play an essential role in meeting the main objectives of the TBS experimental campaign in ITER. The compliancy with the ITER interface requirements, in terms of space availability, service fluids, limits on tritium release, constraints on maintenance, is driving the design of the TBS tritium processing systems. Other requirements come from the characteristics of the relevant test blanket module and the scientific programme that has to be developed and implemented. This paper identifies the main requirements for the design of the TBS tritium systems and equipment and, at the same time, provides an updated overview on the current design status, mainly focusing onto the tritium extractor from Pb-16Li and TBS tritium accountancy. Considerations are also given on the possible extrapolation to DEMO breeding blanket. (authors)

Authors:
; ;  [1]; ;  [2];  [3]
  1. Fusion for Energy, Barcelona (Spain)
  2. ENEA, Camugnano (Italy)
  3. Karlsruhe Institute of Technology - KIT, Karlsruhe (Germany)
Publication Date:
OSTI Identifier:
22429762
Resource Type:
Journal Article
Resource Relation:
Journal Name: Fusion Science and Technology; Journal Volume: 67; Journal Issue: 3; Conference: TRITIUM 2013: 10. International Conference on Tritium Science and Technology, Nice Acropolis (France), 21-25 Oct 2013; Other Information: Country of input: France; 4 refs.
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BREEDING BLANKETS; HELIUM; ITER TOKAMAK; LEAD COMPOUNDS; LITHIUM COMPOUNDS; MAINTENANCE; PROCESSING; TRITIUM

Citation Formats

Ricapito, I., Calderoni, P., Poitevin, Y., Aiello, A., Utili, M., and Demange, D.. Tritium processing for the European test blanket systems: current status of the design and development strategy. United States: N. p., 2015. Web. doi:10.13182/FST14-T75.
Ricapito, I., Calderoni, P., Poitevin, Y., Aiello, A., Utili, M., & Demange, D.. Tritium processing for the European test blanket systems: current status of the design and development strategy. United States. doi:10.13182/FST14-T75.
Ricapito, I., Calderoni, P., Poitevin, Y., Aiello, A., Utili, M., and Demange, D.. Sun . "Tritium processing for the European test blanket systems: current status of the design and development strategy". United States. doi:10.13182/FST14-T75.
@article{osti_22429762,
title = {Tritium processing for the European test blanket systems: current status of the design and development strategy},
author = {Ricapito, I. and Calderoni, P. and Poitevin, Y. and Aiello, A. and Utili, M. and Demange, D.},
abstractNote = {Tritium processing technologies of the two European Test Blanket Systems (TBS), HCLL (Helium Cooled Lithium Lead) and HCPB (Helium Cooled Pebble Bed), play an essential role in meeting the main objectives of the TBS experimental campaign in ITER. The compliancy with the ITER interface requirements, in terms of space availability, service fluids, limits on tritium release, constraints on maintenance, is driving the design of the TBS tritium processing systems. Other requirements come from the characteristics of the relevant test blanket module and the scientific programme that has to be developed and implemented. This paper identifies the main requirements for the design of the TBS tritium systems and equipment and, at the same time, provides an updated overview on the current design status, mainly focusing onto the tritium extractor from Pb-16Li and TBS tritium accountancy. Considerations are also given on the possible extrapolation to DEMO breeding blanket. (authors)},
doi = {10.13182/FST14-T75},
journal = {Fusion Science and Technology},
number = 3,
volume = 67,
place = {United States},
year = {Sun Mar 15 00:00:00 EDT 2015},
month = {Sun Mar 15 00:00:00 EDT 2015}
}