51
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Soto C, García-Rosales C, Echeberria J, Platacis E, Shisko A, Muktepavela F, Malo M, Hernández T. Characterization and thermomechanical assessment of a SiC-sandwich material for Flow Channel Inserts in DCLL blankets. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.03.082] [Citation(s) in RCA: 17] [Impact Index Per Article: 3.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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52
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Jiang K, Martelli E, Agostini P, Liu S, Del Nevo A. Investigation on cooling performance of WCLL breeding blanket first wall for EU DEMO. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.05.018] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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53
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Recent achievements of the Pd-Ag membrane technologies in tritium extraction system applications. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2019.03.162] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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54
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Zacha P, Entler S. High heat flux limits of the fusion reactor water-cooled first wall. NUCLEAR ENGINEERING AND TECHNOLOGY 2019. [DOI: 10.1016/j.net.2019.03.013] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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55
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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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56
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Mertens MAJ, Aerts A, Infante I, Neuhausen J, Cottenier S. Po-Containing Molecules in Fusion and Fission Reactors. J Phys Chem Lett 2019; 10:2879-2884. [PMID: 31063393 DOI: 10.1021/acs.jpclett.9b00824] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 06/09/2023]
Abstract
Fission and fusion reactors can only play a role in the future energy landscape if they are inherently safe by design. For some reactor concepts, a major remaining issue is the undesired production of radiotoxic 210Po. To filter out the volatile Po species, information on their molecular composition is needed. An experimental characterization is very challenging due to the large required amount of radioactive Po. An alternative quantum chemistry approach was taken to predict the temperature-dependent stability of relevant diatomic Po-containing molecules. Experimental data on lighter analogue molecules was used to establish a well-founded methodology. The relative occurrence of the Po species was estimated in the cover gas of (i) the lead-bismuth eutectic coolant in the accelerator-driven MYRRHA fission reactor and (ii) the Pb-Li eutectic tritium breeder in the DEMO fusion reactor. In both systems, Po is found to occur mainly as PbPo molecules and atomic Po.
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Affiliation(s)
- Merlijn A J Mertens
- Center for Molecular Modeling , Ghent University , 9052 Zwijnaarde , Belgium
- Department of Electrical Energy, Metals, Mechanical Construction and Systems , Ghent University , 9052 Zwijnaarde , Belgium
- Institute for Neutron Physics and Reactor Technology , Karlsruhe Institute of Technology , 76131 Karlsruhe , Germany
| | - Alexander Aerts
- Institute for Advanced Nuclear Systems , Belgian Nuclear Research Center (SCK·CEN) , 2400 Mol , Belgium
| | - Ivan Infante
- Nanochemistry Department , Italian Institute of Technology , 16163 Genova , Italy
- Department of Theoretical Chemistry , Vrije Universiteit Amsterdam , 1081 HV Amsterdam , The Netherlands
| | - Jörg Neuhausen
- Laboratory for Radiochemistry , Paul Scherrer Institute , 5232 Villigen PSI , Switzerland
| | - Stefaan Cottenier
- Center for Molecular Modeling , Ghent University , 9052 Zwijnaarde , Belgium
- Department of Electrical Energy, Metals, Mechanical Construction and Systems , Ghent University , 9052 Zwijnaarde , Belgium
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57
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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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58
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Janeschitz G. An economical viable tokamak fusion reactor based on the ITER experience. PHILOSOPHICAL TRANSACTIONS. SERIES A, MATHEMATICAL, PHYSICAL, AND ENGINEERING SCIENCES 2019; 377:20170433. [PMID: 30967048 DOI: 10.1098/rsta.2017.0433] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Subscribe] [Scholar Register] [Accepted: 10/08/2018] [Indexed: 06/09/2023]
Abstract
This is my personal vision and outlook towards a fusion reactor based on my extensive experience from being part of the ITER design, and now construction, as well as leading the largest fusion technology program worldwide (KIT-Karlsruhe Institute of Technology) for 7 years. In particular, I want to discuss how a fusion reactor can be economically viable without employing too advanced physics and technology. It certainly will be a pulsed machine (approx. 20 000 s pulses) with thermal energy storage (turbine is steady state). I also want to discuss the optimum machine size and toroidal field for such a machine and why I think that high field and smaller plasmas may not necessarily make a fusion reactor more competitive. When one extrapolates from today's knowledge on ITER construction, even considering that ITER can be built much cheaper, it is clear that a fusion power plant will cost more than 10 or more likely more than 15 billion Euros/Dollars (the first of a kind even approx. 30 billion). Therefore, in order to have an economically attractive fusion reactor, it needs to produce a large amount of power (on the order of 2.5 GW electric). The possible size (R ∼ 10 m) and reasonably conservative physics basis of such a machine will be briefly described in the presentation. If we are successful in achieving advanced physics in a burning plasma, e.g. in ITER, then we can make the machine slightly smaller but the principal arguments for a large machine will not change significantly. Key technologies and their status will be discussed with particular emphasis on a realistic blanket and divertor design and the size and issues of a tritium-plant (T-plant) for such a machine as well as the challenges which have to be overcome beyond what is needed for ITER. Finally, a simple economic consideration will be discussed to show that a large machine could be economically viable, even in today's environment, in particular, in competition with renewables. This article is part of a discussion meeting issue 'Fusion energy using tokamaks: can development be accelerated?'.
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Affiliation(s)
- G Janeschitz
- Central Integration, Retired from ITER Organisation , St Paul lez Durance , France
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59
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Donné AJH. The European roadmap towards fusion electricity. PHILOSOPHICAL TRANSACTIONS. SERIES A, MATHEMATICAL, PHYSICAL, AND ENGINEERING SCIENCES 2019; 377:20170432. [PMID: 30967047 PMCID: PMC6365854 DOI: 10.1098/rsta.2017.0432] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Abstract] [Key Words] [Grants] [Track Full Text] [Subscribe] [Scholar Register] [Accepted: 06/15/2018] [Indexed: 05/31/2023]
Abstract
The European roadmap to the realization of fusion electricity breaks the quest into eight missions. For each mission, it reviews the current status of research, identifies open issues, and proposes a research and development programme. ITER is the key facility on the roadmap as it is expected to achieve most of the important milestones on the path to fusion power. The Fusion Roadmap is tightly connected to the ITER schedule and the vast majority of resources in fusion research are presently dedicated to ITER and its accompanying experiments. Parallel to the ITER exploitation in the 2030s, the construction of the demonstration power plant DEMO needs to be prepared. DEMO will for the first time supply fusion electricity to the grid and it will have a self-sufficient fuel cycle. The design, construction and operation of DEMO require full involvement of industry to ensure that, after a successful DEMO operation, industry can take responsibility for commercial fusion power. The European fusion roadmap provides a coherent path towards the fusion power plant, and it proposes in an integrated way to find solutions for all challenges that still need to be addressed. This article is part of a discussion meeting issue 'Fusion energy using tokamaks: can development be accelerated?'
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60
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Heuser JM, Zarins A, Baumane L, Kizane G, Knitter R. Radiation stability of long-term annealed bi-phasic advanced ceramic breeder pebbles. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2018.12.034] [Citation(s) in RCA: 10] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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61
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Wang S, Hernández FA, Bubelis E, Chen H. Comparative analysis of the efficiency of a CO2-cooled and a He-cooled pebble bed breeding blanket for the EU DEMO fusion reactor. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2018.10.026] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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62
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Palermo I, Fernández-Berceruelo I, Rapisarda D, Ibarra A. Neutronic assessments towards a comprehensive design of DEMO with DCLL breeding blanket. FUSION ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.fusengdes.2018.11.039] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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63
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Design of a System for Hydrogen isotopes Injection into Lead-Lithium. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.10.006] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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64
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Hernández F, Pereslavtsev P. First principles review of options for tritium breeder and neutron multiplier materials for breeding blankets in fusion reactors. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.09.014] [Citation(s) in RCA: 39] [Impact Index Per Article: 6.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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65
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Federici G, Bachmann C, Barucca L, Biel W, Boccaccini L, Brown R, Bustreo C, Ciattaglia S, Cismondi F, Coleman M, Corato V, Day C, Diegele E, Fischer U, Franke T, Gliss C, Ibarra A, Kembleton R, Loving A, Maviglia F, Meszaros B, Pintsuk G, Taylor N, Tran M, Vorpahl C, Wenninger R, You J. DEMO design activity in Europe: Progress and updates. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.001] [Citation(s) in RCA: 172] [Impact Index Per Article: 28.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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66
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Design and analysis of a new configuration of secondary circuit of the EU-DEMO fusion power plant using GateCycle. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.091] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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67
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Aubert J, Aiello G, Arena P, Barrett T, Boccaccini LV, Bongiovì G, Boullon R, Cismondi F, Critescu I, Domalapally PK, Forest L, Jaboulay JC, Kiss B, Morin A, Peyraud J, Porempovics G, Utili M, Vála L. Status of the EU DEMO HCLL breeding blanket design development. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.133] [Citation(s) in RCA: 22] [Impact Index Per Article: 3.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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68
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Gilbert M, Eade T, Bachmann C, Fischer U, Taylor N. Waste assessment of European DEMO fusion reactor designs. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2017.12.019] [Citation(s) in RCA: 13] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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69
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Maione IA, Lucca F, Marin A, Bertolini C, Roccella M, Villone F, Del Nevo A. Analysis of EM loads on DEMO WCLL breeding blanket during VDE-up. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.05.048] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/14/2022]
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70
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Domalapally PK, Aubert J, Reungoat M, Vála L. Optimization of the pressure drops in the helium in-module manifolds of the EU DEMO “Optimized Conservative” HCLL Breeding Blanket. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.021] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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71
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Hörstensmeyer YN, Butler B, Day C, Franza F. Analysis of the EU-DEMO fuel cycle elements: Intrinsic impact of technology choices. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.02.015] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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72
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Numerical analyses for conceptual design of an irradiation PbLi capsule for testing of protective coatings for the European DEMO breeding blanket project. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.011] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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73
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Structural assessment of the HCPB breeding blanket segments in the EU DEMO reactor under normal operation and a central plasma disruption. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.02.024] [Citation(s) in RCA: 16] [Impact Index Per Article: 2.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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74
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Moscato I, Barucca L, Ciattaglia S, Di Maio P, Federici G. Preliminary design of EU DEMO helium-cooled breeding blanket primary heat transfer system. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.05.058] [Citation(s) in RCA: 15] [Impact Index Per Article: 2.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
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75
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Cismondi F, Boccaccini L, Aiello G, Aubert J, Bachmann C, Barrett T, Barucca L, Bubelis E, Ciattaglia S, Del Nevo A, Diegele E, Gasparotto M, Di Gironimo G, Di Maio P, Hernandez F, Federici G, Fernández-Berceruelo I, Franke T, Froio A, Gliss C, Keep J, Loving A, Martelli E, Maviglia F, Moscato I, Mozzillo R, Poitevin Y, Rapisarda D, Savoldi L, Tarallo A, Utili M, Vala L, Veres G, Zanino R. Progress in EU Breeding Blanket design and integration. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.009] [Citation(s) in RCA: 37] [Impact Index Per Article: 6.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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76
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Di Marcello V, Ghidersa BE, Jin XZ, Abou-Sena A, Stieglitz R. Development and validation of the blanket First Wall mock-up model in RELAP5-3D. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.05.050] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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77
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Di Maio P, Arena P, Bongiovì G, Chiovaro P, Del Nevo A, Forte R. Numerical assessment of the thermomechanical behaviour of the DEMO Water-Cooled Lithium Lead inboard blanket equatorial module. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.098] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
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78
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Bongiovì G, Arena P, Chiovaro P, Di Maio PA, Del Nevo A, Forte R. Multi-Module vs. Single-Module concept: Comparison of thermomechanical performances for the DEMO Water-Cooled Lithium Lead breeding blanket. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.05.037] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
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79
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The possible effect of high magnetic fields on the aqueous corrosion behaviour of Eurofer. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.04.054] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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80
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Transient thermal analysis and structural assessment of an ex-vessel LOCA event on the EU DEMO HCPB breeding blanket and the attachment system. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2017.12.017] [Citation(s) in RCA: 18] [Impact Index Per Article: 3.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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81
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Huang Y, Cismondi F, Diegele E, Federici G, Del Nevo A, Moro F, Ghoniem N. Thermo-structural design of the European DEMO water-cooled blanket with a multiscale-multiphysics framework. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.07.007] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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82
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Wulf SE, Krauss W, Konys J. Long-term corrosion behavior of Al-based coatings in flowing Pb–15.7Li, produced by electrochemical ECX process. NUCLEAR MATERIALS AND ENERGY 2018. [DOI: 10.1016/j.nme.2018.06.019] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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83
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Palermo I, Villari R, Ibarra A. Divertor options impact on DEMO nuclear performances. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2018.03.020] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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84
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Lu P, Pereslavtsev P, Fischer U, Wegmann C. Sensitivity of R2Smesh shutdown dose rate results on the mesh resolution. FUSION ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.fusengdes.2017.10.030] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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85
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Optimization of the first wall helium cooling system of the European DCLL using CFD approach. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.02.015] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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86
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Palermo I, Garcia R, Garcia M, Sanz J. Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.02.080] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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87
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Del Nevo A, Martelli E, Agostini P, Arena P, Bongiovì G, Caruso G, Di Gironimo G, Di Maio P, Eboli M, Giammusso R, Giannetti F, Giovinazzi A, Mariano G, Moro F, Mozzillo R, Tassone A, Rozzia D, Tarallo A, Tarantino M, Utili M, Villari R. WCLL breeding blanket design and integration for DEMO 2015: status and perspectives. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.03.020] [Citation(s) in RCA: 83] [Impact Index Per Article: 11.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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88
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Review of hydrogen isotopes transport parameters and considerations to corresponding experiments. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.04.024] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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89
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Froio A, Casella F, Cismondi F, Del Nevo A, Savoldi L, Zanino R. Dynamic thermal-hydraulic modelling of the EU DEMO WCLL breeding blanket cooling loops. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.01.062] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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90
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Study of the cooling systems with S-CO 2 for the DEMO fusion power reactor. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.05.029] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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91
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Aubert J, Aiello G, Arena P, Boullon R, Jaboulay JC, Morin A. Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2016.12.040] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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92
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Wulf SE, Krauss W, Konys J. Impact of pretreatment conditions on defect formation during the fabrication of Al-based corrosion barriers by ECX process. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.03.115] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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93
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Preliminary safety analysis of LOCAs in one EU DEMO HCPB blanket module. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.03.082] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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94
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Thermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.03.086] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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95
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96
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97
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Structural analysis of the back supporting structure of the DEMO WCLL outboard blanket. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2016.12.018] [Citation(s) in RCA: 16] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Di Maio P, Arena P, Bongiovì G, Chiovaro P, Del Nevo A, Richiusa M. On the thermo-mechanical behaviour of DEMO water-cooled lithium lead equatorial outboard blanket module. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.05.051] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Santucci A, Frattolillo A, Incelli M, Tosti S. The coolant purification system in DEMO: Interfaces and requirements. FUSION ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.fusengdes.2017.04.094] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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