Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB

Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of the challenging issues to be solved in order to demonstrate the feasibility of nuclear fusion power plants construction. Several technologies were investigated as antipermeation and corrosion barriers to reduce the tritium permeation flux from the breeder into the PHTS. Within this frame, alumina coating manufactured by Pulsed Laser Deposition (PLD) and Atomic Layer Deposition (ALD) are two of the main candidates for the Water Cooled Lithium Lead (WCLL) Breeder Blanket (BB). In order to validate the performance of the coatings on relevant WCLL BB geometries, a mock-up was designed and will be characterized in an experimental facility operating with flowing lithium-lead, called TRIEX-II. The present work aims to illustrate the preliminary engineering design of a WCLL BB mock-up in order to deeply investigate permeation of hydrogen isotopes through PHTS water pipes. The permeation tests are planned in the temperature range between 330 and 500 °C, with hydrogen and deuterium partial pressure in the range of 1–1000 Pa. The hydrogen isotopes transport analysis carried out for the design and integration of the mock-up in TRIEX-II facility is also shown.

[1]  M. Zucchetti,et al.  HyPer-QuarCh II: A laboratory-scale device for hydrogen isotopes permeation experiments , 2021, Fusion Engineering and Design.

[2]  Roman Petráš,et al.  Characterization of aluminum-based coatings after short term exposure during irradiation campaign in the LVR-15 fission reactor , 2021 .

[3]  Gandolfo Alessandro Spagnuolo,et al.  Development of load specifications for the design of the breeding blanket system , 2020, Fusion Engineering and Design.

[4]  A. Ciampichetti,et al.  Characterization of Pb-15.7Li Hydrogen Isotopes Permeation Sensors and Upgrade of Hyper- Quarch Experimental Device , 2020, IEEE Transactions on Plasma Science.

[5]  Gandolfo Alessandro Spagnuolo,et al.  Systems Engineering approach in support to the breeding blanket design , 2019, Fusion Engineering and Design.

[6]  F. García Ferré,et al.  Multifunctional nanoceramic coatings for future generation nuclear systems , 2019, Fusion Engineering and Design.

[7]  R. Zanino,et al.  Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project , 2019, Fusion Engineering and Design.

[8]  D. Martelli,et al.  Status of Pb-16Li technologies for European DEMO fusion reactor , 2019, Fusion Engineering and Design.

[9]  F. Di Fonzo,et al.  Radiation effects on deuterium permeation for PLD alumina coated Eurofer steel measured during 1.8 MeV electron irradiation , 2018, Journal of Nuclear Materials.

[10]  M. Zucchetti,et al.  Design Optimization of a Hydrogen Sensor for ITER Pb16Li Blankets , 2017, IEEE Transactions on Plasma Science.

[11]  Brad J. Merrill,et al.  Vacuum Permeator Analysis for Extraction of Tritium from DCLL Blankets , 2015 .

[12]  A. Perujo,et al.  The surface rate constants of deuterium in the reduced activating martensitic steel OPTIFER-IVb , 2000 .

[13]  P. Wienhold,et al.  The rate of hydrogen release out of clean metallic surfaces , 1978 .

[14]  M. Tarantino,et al.  Development of anti-permeation and corrosion barrier coatings for the WCLL breeding blanket of the European DEMO , 2021 .

[15]  M. Coleman,et al.  Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems , 2020 .