Conceptual design of Tritium Extraction System for the European HCPB Test Blanket Module |
| |
| Authors: | A. Ciampichetti F.S. Nitti A. Aiello I. Ricapito K. Liger D. Demange L. Sedano C. Moreno M. Succi |
| |
| Affiliation: | 1. ENEA CR Brasimone, 40032 Camugnano (Bo), Italy;2. Fusion for Energy, 08019 Barcelona, Spain;3. CEA, DEN, DTN/STPA/LIPC, Cadarache, 13108 St. Paul-lez-Durance, France;4. Karlsruhe Institute of Technology, ITEP-TLK, Postfach 36 40, 76021 Karlsruhe, Germany;5. EURATOM-CIEMAT Association, 28040 Madrid, Spain;6. SAES Getters Spa, 20020 Lainate (Mi), Italy;7. European TBM Consortium of Associates, Germany |
| |
| Abstract: | 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. |
| |
| Keywords: | |
| 本文献已被 ScienceDirect 等数据库收录！ |
|
