The Coolant Purification Systems (CPSs) is one of the most relevant ancillary systems of European Helium Cooled Lead Lithium (HCLL) and Helium Cooled Pebble Bed (HCPB) Test Blanket Modules (TBMs) which are currently in the preliminary design phase in view of their installation and operation in ITER. The CPS implements mainly two functions: the extraction and concentration of the tritium permeated from the TBM modules into the primary cooling circuit and the chemistry control of helium primary coolant. During the HCLL and HCPB-TBSs (Test Blanket Systems) Conceptual Design Review (CDR) in 2015 it was recognized the need of reducing the tritium permeation into the Port Cell #16 of ITER. To achieve this and, then, to lower the tritium partial pressure in the Helium Cooling Systems in normal operation, the helium flow-rate treated by each CPS has been increased of almost one order of magnitude. In 2017, to satisfy the CDR outcomes and the new design requirements requested by Fusion for Energy (F4E, the European Domestic Agency for ITER), ENEA performed a preliminary design of the “enhanced” CPSs. This paper presents the current design of the “enhanced” CPSs, focusing on design requirements, assumptions, selection of technologies and preliminary components sizing.

Tincani A., Aiello A., Ferrucci B., Granieri M., Voukelatou K., Ricapito I., et al. (2019). Conceptual design of the enhanced coolant purification systems for the European HCLL and HCPB test blanket modules. FUSION ENGINEERING AND DESIGN, 146, 365-368 [10.1016/j.fusengdes.2018.12.069].

Conceptual design of the enhanced coolant purification systems for the European HCLL and HCPB test blanket modules

Arena P.;Di Maio P. A.;Forte R.
2019-01-01

Abstract

The Coolant Purification Systems (CPSs) is one of the most relevant ancillary systems of European Helium Cooled Lead Lithium (HCLL) and Helium Cooled Pebble Bed (HCPB) Test Blanket Modules (TBMs) which are currently in the preliminary design phase in view of their installation and operation in ITER. The CPS implements mainly two functions: the extraction and concentration of the tritium permeated from the TBM modules into the primary cooling circuit and the chemistry control of helium primary coolant. During the HCLL and HCPB-TBSs (Test Blanket Systems) Conceptual Design Review (CDR) in 2015 it was recognized the need of reducing the tritium permeation into the Port Cell #16 of ITER. To achieve this and, then, to lower the tritium partial pressure in the Helium Cooling Systems in normal operation, the helium flow-rate treated by each CPS has been increased of almost one order of magnitude. In 2017, to satisfy the CDR outcomes and the new design requirements requested by Fusion for Energy (F4E, the European Domestic Agency for ITER), ENEA performed a preliminary design of the “enhanced” CPSs. This paper presents the current design of the “enhanced” CPSs, focusing on design requirements, assumptions, selection of technologies and preliminary components sizing.
Settore ING-IND/19 - Impianti Nucleari
http://www.journals.elsevier.com/fusion-engineering-and-design/
Tincani A., Aiello A., Ferrucci B., Granieri M., Voukelatou K., Ricapito I., et al. (2019). Conceptual design of the enhanced coolant purification systems for the European HCLL and HCPB test blanket modules. FUSION ENGINEERING AND DESIGN, 146, 365-368 [10.1016/j.fusengdes.2018.12.069].
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/10447/393618
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