The coolant purification system of the European test blanket modules: Preliminary design

A. Ciampichetti, A. Aiello, G. Coccoluto, I. Ricapito, K. Liger, D. Demange, C. Moreno

Research output: Contribution to journalArticle

11 Citations (Scopus)


The HCPB (Helium Cooled Pebble Bed) and HCLL (Helium Cooled Lithium Lead) Test Blanket Modules (TBMs), developed in EU to be tested in ITER, adopt helium at 80 bar as primary coolant. This paper contains a conceptual design of the TBMs Coolant Purification System (CPS) based on the need to remove permeated tritium and gas impurities. The following steps have been considered: identification of CPS design requirements; review of the purification systems developed for Helium Cooled Fission Reactors and proposed for DEMO Fusion Reactor; selection of the most promising technologies for CPS; indications on instrumentation and procedures for tritium balance. The proposed solution is a three-stage process constituted by an oxidiser to convert Q2and CO to Q2O and CO2, an adsorption step, performed on molecular sieve at room temperature to remove Q2O and CO2, and a final step performed on a heated getter to remove residual impurities. © 2010 Published by Elsevier B.V. All rights reserved.
Original languageEnglish
Pages (from-to)2033 - 2039
Number of pages7
JournalFusion Engineering and Design
Issue number10-12
Publication statusPublished - Dec 2010
Externally publishedYes


All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

Cite this

Ciampichetti, A., Aiello, A., Coccoluto, G., Ricapito, I., Liger, K., Demange, D., & Moreno, C. (2010). The coolant purification system of the European test blanket modules: Preliminary design. Fusion Engineering and Design, 85(10-12), 2033 - 2039.