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Experimental setup for study of mechanical performance of materials in liquid Pb-16Li and first results. FUSION ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.fusengdes.2023.113474] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 01/31/2023]
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2
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Neu R, Maier H, Böswirth B, Elgeti S, Greuner H, Hunger K, Kondas J, von Müller A. Investigations on cold spray tungsten/tantalum coatings for plasma facing applications. NUCLEAR MATERIALS AND ENERGY 2023. [DOI: 10.1016/j.nme.2022.101343] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/23/2022]
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3
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4
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Parametric study of the radiative load distribution on the EU-DEMO first wall due to SPI-mitigated disruptions. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112917] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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5
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Petráš R, Kunzová K, Fedoriková A, Kekrt J, Kordač M, Di Fonzo F, Paladino B, Schroer C, Lorenz J, Utili M, Vála L. Characterization of aluminum-based coatings after short term exposure during irradiation campaign in the LVR-15 fission reactor. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112521] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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6
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Barucca L, Bubelis E, Ciattaglia S, D’Alessandro A, Del Nevo A, Giannetti F, Hering W, Lorusso P, Martelli E, Moscato I, Quartararo A, Tarallo A, Vallone E. Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112504] [Citation(s) in RCA: 12] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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7
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Wang J, Lei M, Xu S, Yang H, Zhao P, Xu K, Song Y. DEM simulation of mechanical behavior in one-dimensional compression of crushable ceramic pebble bed. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112606] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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8
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CFD analysis of natural convection cooling of the in-vessel components during a shutdown of the EU DEMO fusion reactor. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112252] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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9
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Moscheni M, Carr M, Dulla S, Maviglia F, Meakins A, Nallo G, Subba F, Zanino R. Radiative heat load distribution on the EU-DEMO first wall due to mitigated disruptions. NUCLEAR MATERIALS AND ENERGY 2020. [DOI: 10.1016/j.nme.2020.100824] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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10
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Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111884] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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11
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Analysis of the effects of primary heat transfer system isolation valves in case of in-vessel loss-of-coolant accidents in the EU DEMO. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111926] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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12
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Desu RK, Peeketi AR, Annabattula RK. Influence of bed conditions on the effective thermal conductivity of ceramic breeder pebble beds using thermal DEM (TDEM). FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111767] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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13
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Cismondi F, Spagnuolo G, Boccaccini L, Chiovaro P, Ciattaglia S, Cristescu I, Day C, Del Nevo A, Di Maio P, Federici G, Hernandez F, Moreno C, Moscato I, Pereslavtsev P, Rapisarda D, Santucci A, Utili M. Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111640] [Citation(s) in RCA: 29] [Impact Index Per Article: 7.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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14
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Hybrid 1D + 2D Modelling for the Assessment of the Heat Transfer in the EU DEMO Water-Cooled Lithium-Lead Manifolds. ENERGIES 2020. [DOI: 10.3390/en13143525] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
Abstract
The European demonstration fusion power reactor (EU DEMO) tokamak will be the first European fusion device to produce electricity and to include a breeding blanket (BB). In the framework of the design of the EU DEMO BB, the analysis of the heat transfer between the inlet and outlet manifold of the coolant is needed, to assess the actual cooling capability of the water entering the cooling channels, as well as the actual coolant outlet temperature from the machine. The complex, fully three-dimensional conjugate heat transfer problem is reduced here with a novel approach to a simpler one, decoupling the longitudinal and transverse scales for the heat transport by developing correlations for a conductive heat-transfer problem. While in the longitudinal direction a standard 1D model for the heat transport by fluid advection is adopted, a set of 2D finite elements analyses are run in the transverse direction, in order to lump the 2D heat conduction effects in suitable correlations. Such correlations are implemented in a 1D finite volume model with the 1D GEneral Tokamak THErmal-hydraulic Model (GETTHEM) code (Politecnico di Torino, Torino, Italy); the proposed approach thus reduces the 3D problem to a 1D one, allowing a parametric evaluation of the heat transfer in the entire blanket with a reduced computational cost. The deviation from nominal inlet and outlet temperature values, for the case of the Water-Cooled Lithium-Lead BB concept, is found to be always below 1.4 K and, in some cases, even to be beneficial. Consequently, the heat transfer among the manifolds at different temperatures can be safely (and conservatively) neglected.
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15
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Update of electromagnetic loads on HCPB breeding blanked for DEMO 2017 configuration. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111604] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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16
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Tassone A, Caruso G, Del Nevo A. Influence of PbLi hydraulic path and integration layout on MHD pressure losses. FUSION ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.fusengdes.2020.111517] [Citation(s) in RCA: 17] [Impact Index Per Article: 4.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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17
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Rovira A, Sánchez C, Montes MJ, Muñoz M. Proposal of optimized power cycles for the DEMO power plant (EUROfusion). FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.111290] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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18
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Bongiovì G, Spagnuolo G, Maione I, Cismondi F, Del Nevo A, Hernandez F, Rapisarda D, Mozzillo R. Systems engineering activities supporting the heating & current drive and fuelling lines systems integration in the European DEMO breeding blanket. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.111265] [Citation(s) in RCA: 11] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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19
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Moscato I, Barucca L, Ciattaglia S, D’Aleo F, Di Maio P, Federici G, Tarallo A. Progress in the design development of EU DEMO helium-cooled pebble bed primary heat transfer system. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.04.006] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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20
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A complete EM analysis of DEMO WCLL Breeding Blanket segments during VDE-up. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2018.12.017] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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21
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22
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An enhanced, near-term HCPB design as driver blanket for the EU DEMO. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.02.037] [Citation(s) in RCA: 38] [Impact Index Per Article: 7.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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23
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MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.01.087] [Citation(s) in RCA: 20] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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24
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On the effect of stiffening plates configuration on the DEMO Water Cooled Lithium Lead Breeding Blanket module thermo-mechanical behaviour. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.03.163] [Citation(s) in RCA: 12] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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25
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On the effects of the Double-Walled Tubes lay-out on the DEMO WCLL breeding blanket module thermal behavior. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.01.105] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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26
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Utili M, Bassini S, Boccaccini L, Bühler L, Cismondi F, Del Nevo A, Eboli M, DiFonzo F, Hernandez T, Wulf S, Kordač M, Martelli D, De les Valls EM, Melichar T, Mistrangelo C, Tarantino M, Tincani A, Vála L. Status of Pb-16Li technologies for European DEMO fusion reactor. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.04.083] [Citation(s) in RCA: 12] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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27
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Systems Engineering approach in support to the breeding blanket design. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2018.11.016] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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28
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Mazzini G, Kaliatka T, Porfiri MT. Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2019. [DOI: 10.1115/1.4043379] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
The safety features of the future nuclear fusion reactors are one of the key issues for their attractiveness if compared with the fission plants. In fusion devices, accidents with high release of radioactive materials have low probabilities because the most part of abnormal transients lead to passive plasma shutdown. It does not mean that radiological source terms such tritium and activated dust are not generated and released, but their inventory does not increase during abnormal events. Therefore, the source term inventory has to be assessed during normal operation and traced when accidents occur. For this reason, a study for qualification and quantification of the tritium and dust source term (DTS) was established with the aim to understand their production, deposition, and penetration in the vacuum vessel (VV) and in the breeding blanket (BB). The main concern is source term release during the main accident scenarios to comply with a future licensing process. In case of abnormal event scenarios, the source term inventory involved in the release changes and requires a different confinement approach and mitigation. For the estimation of the source term in the DEMOnstration Fusion Power Station (DEMO), a methodology was developed. The methodology scales the tritium and DTS inside the VV from the International Thermonuclear Experimental Reactor, the European Power Plant Conceptual Study, and reports the tritium generated inside the breeder blanket from data quantified in other studies for DEMO. In this article, the methodology was updated and tritium and DTS for DEMO 2016 design were estimated. Moreover, the tritium and dust release pathways were highlighted according to different accidental scenarios. These results were obtained for all blanket concepts, which are analyzing in the ongoing DEMO EUROFusion project. The values estimated in this article will be used in the safety analyses to evaluate releases or to quantify the operational limits starting from values postulated in International Thermonuclear Experimental Reactor.
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Affiliation(s)
- Guido Mazzini
- Centrum Vyzkumu Rez (CVRez), Hlavní 130, Husinec–Řež 250 68, Czech Republic e-mail:
| | - Tadas Kaliatka
- Lithuanian Energy Institute, Breslaujos g. 3, Kaunas 44403, Lithuania
| | - Maria Teresa Porfiri
- Agenzia nazionale per le nuove tecnologie, l'energia e lo sviluppo economico sostenibile (ENEA) UTFUS-TECN, Via Enrico Fermi, 45, Frascati, Roma 00044, Italy
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Hernández FA, Pereslavtsev P, Zhou G, Kiss B, Kang Q, Neuberger H, Chakin V, Gaisin R, Vladimirov P, Boccaccini LV, Spagnuolo GA, D’Amico S, Moscato I. Advancements in the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO: Holistic Design Approach and Lessons Learned. FUSION SCIENCE AND TECHNOLOGY 2019. [DOI: 10.1080/15361055.2019.1607695] [Citation(s) in RCA: 27] [Impact Index Per Article: 5.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Affiliation(s)
- Francisco A. Hernández
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Pavel Pereslavtsev
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Guangming Zhou
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Béla Kiss
- Budapest University of Technology and Economics, Budapest 1111, Hungary
| | - Qinlan Kang
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Heiko Neuberger
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Vladimir Chakin
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Ramil Gaisin
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Pavel Vladimirov
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Lorenzo V. Boccaccini
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Gandolfo A. Spagnuolo
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
| | - Salvatore D’Amico
- Karlsruhe Institute of Technology, 76344 Eggenstein-Leopoldshafen, Baden-Württemberg, Germany
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An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.01.141] [Citation(s) in RCA: 125] [Impact Index Per Article: 25.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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31
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Froio A, Del Nevo A, Martelli E, Savoldi L, Zanino R. Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.10.003] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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32
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