E.T.S. DE INGENIEROS INDUSTRIALES
Centro
CEA-Cadarache
Aix-en-Provence, FranciaPublicaciones en colaboración con investigadores/as de CEA-Cadarache (58)
2024
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Computational study of the Nitrogen-16 source term in the ITER vacuum vessel cooling circuit through the coupling of system-level analysis code and CFD
Nuclear Engineering and Technology, Vol. 56, Núm. 8, pp. 2990-2998
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Corrigendum to “Total Ionizing Dose Estimation of ITER Upper Port Remote Handling Equipment” [Fusion Engineering and Design volume 202 (2024) 114359] (Fusion Engineering and Design (2024) 202, (S0920379624002126), (10.1016/j.fusengdes.2024.114359))
Fusion Engineering and Design
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Dust contamination of Divertor Remote Handling System in ITER Hot Cell: A novel approach to model complex superficial radiation sources
Fusion Engineering and Design, Vol. 199
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EUROfusion contributions to ITER nuclear operation
Nuclear Fusion, Vol. 64, Núm. 11
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ITER full model in MCNP for radiation safety demonstration
Nature Communications , Vol. 15, Núm. 1
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Overview of T and D-T results in JET with ITER-like wall
Nuclear Fusion, Vol. 64, Núm. 11
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Radwaste analysis and package optimization with the F4E-radwaste tool and application to the ITER IVVS
Fusion Engineering and Design, Vol. 198
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The Radiation Impact of Delayed Photoneutron Production in ITER Components
Fusion Science and Technology, Vol. 80, Núm. 8, pp. 1012-1023
2023
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Assessment of ITER radiation environment during the remote-handling operation of In-Vessel components with D1SUNED
Scientific Reports, Vol. 13, Núm. 1
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Computational study of the dose-rate field of an ITER heat exchanger due to activated corrosion products
Fusion Engineering and Design, Vol. 193
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Nuclear Scoping Analysis of ITER Bioshield Top Lid Toward its Preliminary Design Review
Fusion Engineering and Design, Vol. 195
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Update of nuclear responses in the ITER superconducting magnets using the E-lite 3600 analysis model
Transactions of the American Nuclear Society
2022
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Disruption prediction with artificial intelligence techniques in tokamak plasmas
Nature Physics, Vol. 18, Núm. 7, pp. 741-750
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Enhanced performance in fusion plasmas through turbulence suppression by megaelectronvolt ions
Nature Physics, Vol. 18, Núm. 7, pp. 776-782
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Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X
Nuclear Fusion, Vol. 62, Núm. 4
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Overview of JET results for optimising ITER operation
Nuclear Fusion, Vol. 62, Núm. 4
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Shielding conceptual designs of ITER TCP ports to protect electronics
Fusion Engineering and Design, Vol. 176
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Update of nuclear responses in the ITER superconducting magnets using the E-lite 3600 analysis model
Proceedings of the 14th International Conference on Radiation Shielding and 21st Topical Meeting of the Radiation Protection and Shielding Division, ICRS 2022/RPSD 2022
2021
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A full and heterogeneous model of the ITER tokamak for comprehensive nuclear analyses
Nature Energy, Vol. 6, Núm. 2, pp. 150-157
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Improved radiation shielding analysis considering vector calculus
International Journal of Energy Research, Vol. 45, Núm. 8, pp. 11904-11915