The HCPB (Helium Cooled Pebble Bed) Test Blanket Module (TBM), developed in EU to be tested in ITER, adopts a ceramic containing lithium as breeder material, beryllium as neutron multiplier and helium at 80 bar as primary coolant. In HCPB-TBM the main function of Tritium Extraction System (TES) is to extract tritium from the breeder by gas purging, to remove it from the purge gas and to route it to the ITER Tritium Plant for the final tritium processing. In this paper, starting from a revision of the so far reference process considered for HCPB-TES and considering a new modeling activity aimed to evaluate tritium concentration in purge gas, an updated conceptual design of TES is reported. © 2012 Elsevier B.V. All rights reserved.
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering
Ciampichetti, A., Nitti, F. S., Aiello, A., Ricapito, I., Liger, K., Demange, D., Sedano, L., Moreno, C., & Succi, M. (2012). Conceptual design of tritium extraction system for the European HCPB test blanket module. Fusion Engineering and Design, 87(5-6), 620 - 624. https://doi.org/10.1016/j.fusengdes.2012.01.047