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2. Development of a viable route for lithium-6 supply of DEMO and future fusion power plants

Author

Giegerich, T., Battes, K., Schwenzer, J. C., and Day, C.

Subjects
HgLab, ICOMAX process, Lithium-6, Mercury, Lithium enrichment, 7. Clean energy, DEMO
Abstract

In the European DEMO program, the design development of a demonstration power plant (DEMO) is currently in its pre-conceptual phase. In DEMO, breeding blankets will use large quantities of lithium, enriched in the isotope lithium-6 (6Li), for breeding the tritium needed to feed the DT fusion reaction. Unfortunately, enriched lithium is commercially not available in the required quantities, which is threatening the success of future power plant applications of nuclear fusion. Even if the manufacturing of the breeding blankets is still two decades ahead of us, it is now mandatory to address the topic of lithium-6 supply and to make sure that a viable supply (and reprocessing) route is available when needed. This paper presents an unbiased systems engineering approach assessing a number of available lithium isotope separation methods by defining requirements, rating them systematically and finally calculating a ranking number expressing the value of different methods. As a result, we suggest using a chemical exchange method based on a lithium amalgam system, but including some important improvements leading to a more efficient and ‘clean’ process (the ICOMAX process) in comparison with the formerly used COLEX process. Furthermore, by modelling activities and experiments in the KIT mercury laboratory (HgLab Karlsruhe), it is shown which work has to be done in the next years to make sure that the technical-scale process is available in time to supply DEMO and future fusion power plants by middle of the 21st century.

3. Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design

Author

A. Del Nevo, Salvatore D’Amico, Pierluigi Chiovaro, Lorenzo Virgilio Boccaccini, F.R. Urgorri, Maria Teresa Porfiri, Antonio Froio, Alessia Santucci, Fabio Cismondi, Sergio Ciattaglia, Ion Cristescu, Silvano Tosti, A. Li Puma, R. Arredondo, Michael Rieth, C. Gliss, Robert Stieglitz, P.A. Di Maio, Matteo D’Onorio, David Rapisarda, G. Federici, Carlos Hugo Moreno, M. Coleman, F. Franza, E. Vallone, Ch. Day, J.C. Schwenzer, Marco Utili, I. Moscato, Pavel Pereslavtsev, Francisco A. Hernández, Gandolfo Alessandro Spagnuolo, Spagnuolo, G. A., Arredondo, R., Boccaccini, L. V., Chiovaro, P., Ciattaglia, S., Cismondi, F., Coleman, M., Cristescu, I., D'Amico, S., Day, C., Del Nevo, A., Di Maio, P. A., D'Onorio, M., Federici, G., Franza, F., Froio, A., Gliss, C., Hernandez, F. A., Li Puma, A., Moreno, C., Moscato, I., Pereslavtsev, P., Porfiri, M. T., Rapisarda, D., Rieth, M., Santucci, A., Schwenzer, J. C., Stieglitz, R., Tosti, S., Urgorri, F. R., Utili, M., Vallone, E., Spagnuolo G.A., Arredondo R., Boccaccini L.V., Chiovaro P., Ciattaglia S., Cismondi F., Coleman M., Cristescu I., D'Amico S., Day C., Del Nevo A., Di Maio P.A., D'Onorio M., Federici G., Franza F., Froio A., Gliss C., Hernandez F.A., Li Puma A., Moreno C., Moscato I., Pereslavtsev P., Porfiri M.T., Rapisarda D., Rieth M., Santucci A., Schwenzer J.C., Stieglitz R., Tosti S., Urgorri F.R., Utili M., and Vallone E.

Subjects
Technology, Nuclear engineering, integration issues, Breeding blanket, Integration issues, Water activation, Tritium management, VVPSS, chemistry.chemical_element, Isolation valve, System safety, Blanket, Tritium, 01 natural sciences, 010305 fluids & plasmas, 0103 physical sciences, Fusion reactors -- Design and construction, General Materials Science, 010306 general physics, water activation, Settore ING-IND/19 - Impianti Nucleari, Helium, Civil and Structural Engineering, Integrated design, breeding blanket, tritium management, Mechanical Engineering, Water -- Thermal properties, Coolant, Nuclear Energy and Engineering, chemistry, Heat transfer, Environmental science, Helium -- Thermal properties, Plant design, ddc:600, Power-plants -- Design and construction
Abstract

Currently, for the EU DEMO, two Breeding Blankets (BBs) have been selected as potential candidates for the integration in the reactor. They are the Water Cooled Lithium Lead and the Helium Cooled Pebble Bed BB concepts. The two BB variants together with the associated ancillary systems drive the design of the overall plant. Therefore, a holistic investigation of integration issues derived by the BB and the installation of its ancillary systems has been performed. The issues related to the water activation due to the 16N and 17N isotopes and the impact on the primary heat transfer systems have been investigated providing guidelines and dedicated solution for the integration of safety devices as isolation valves. The tritium retention and the permeation rates through the blanket and its ancillary systems have been also assessed taking into account different operating points both for the BB and ancillaries and comparing, when possible, the releases with the operating and safety limits. Moreover, the issues related to the tritium start-up inventory as well as the uncertainties on the Tritium Breeding Ratio (TBR) due to the integration of the auxiliary systems within the Vacuum Vessel have been also studied. Finally, the impact of the BB concepts on the safety systems like the Vacuum Vessel Pressure Suppression System is described with a particular focus on the different measures that should be implemented according to the considered concept. All these aspects are then taken into account to drive future developments during the Concept Design Phase., peer-reviewed

Published
2021

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