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...
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MDPI AG
2022-02-01
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| Series: | Applied Sciences |
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| Online Access: | https://www.mdpi.com/2076-3417/12/3/1624 |
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| author | Marco Utili Ciro Alberghi Luigi Candido Fabio Di Fonzo Francesca Papa Alessandro Venturini |
| author_facet | Marco Utili Ciro Alberghi Luigi Candido Fabio Di Fonzo Francesca Papa Alessandro Venturini |
| author_sort | Marco Utili |
| collection | DOAJ |
| description | 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. |
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| format | Article |
| id | doaj.art-7e156170f43c47caafd7ef77c252743c |
| institution | Directory Open Access Journal |
| issn | 2076-3417 |
| language | English |
| last_indexed | 2024-03-10T00:10:10Z |
| publishDate | 2022-02-01 |
| publisher | MDPI AG |
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| spelling | doaj.art-7e156170f43c47caafd7ef77c252743c2023-11-23T16:00:41ZengMDPI AGApplied Sciences2076-34172022-02-01123162410.3390/app12031624Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BBMarco Utili0Ciro Alberghi1Luigi Candido2Fabio Di Fonzo3Francesca Papa4Alessandro Venturini5ENEA FSN Department, C.R. Brasimone, Bacino del Brasimone, Camugnano, 40032 Bologna, ItalyESSENTIAL Group, Politecnico di Torino, Corso Duca degli Abruzzi, 24, 10129 Torino, ItalyESSENTIAL Group, Politecnico di Torino, Corso Duca degli Abruzzi, 24, 10129 Torino, ItalyCenter for Nano Science and Technology @PoliMi, Istituto Italiano di Tecnologia, via G. Pascoli 70/3, 20133 Milan, ItalyDIAEE Nuclear Section, Sapienza University of Rome, Corso Vittorio Emanuele II, 244, 00186 Rome, ItalyENEA FSN Department, C.R. Brasimone, Bacino del Brasimone, Camugnano, 40032 Bologna, ItalyTritium 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.https://www.mdpi.com/2076-3417/12/3/1624WCLLITERDEMOantipermeation barriercorrosion barrierlithium-lead |
| spellingShingle | Marco Utili Ciro Alberghi Luigi Candido Fabio Di Fonzo Francesca Papa Alessandro Venturini Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB Applied Sciences WCLL ITER DEMO antipermeation barrier corrosion barrier lithium-lead |
| title | Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB |
| title_full | Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB |
| title_fullStr | Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB |
| title_full_unstemmed | Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB |
| title_short | Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB |
| title_sort | design of the test section for the experimental validation of antipermeation and corrosion barriers for wcll bb |
| topic | WCLL ITER DEMO antipermeation barrier corrosion barrier lithium-lead |
| url | https://www.mdpi.com/2076-3417/12/3/1624 |
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