E.T.S. DE INGENIEROS INDUSTRIALES
Centre
CEA-Cadarache
Aix-en-Provence, FranciaPublications en collaboration avec des chercheurs de CEA-Cadarache (40)
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
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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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Radwaste analysis and package optimization with the F4E-radwaste tool and application to the ITER IVVS
Fusion Engineering and Design, Vol. 198
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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The Radiation Impact of Delayed Photoneutron Production in ITER Components
Fusion Science and Technology
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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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
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
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Integral modelling of the ITER cooling water systems radiation source for applications outside of the Bio-shield
Fusion Engineering and Design, Vol. 171
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Shutdown dose rate assessment of the interspace components of wide angle viewing system diagnostic for ITER
Fusion Engineering and Design, Vol. 172
2020
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Estimation of radiation conditions in the ITER electron cyclotron upper launcher with state-of-the-art simulation techniques
Fusion Engineering and Design, Vol. 157
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The joint evaluated fission and fusion nuclear data library, JEFF-3.3
European Physical Journal A, Vol. 56, Núm. 7
2019
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Nuclear analysis of the ITER torus cryopumps
Nuclear Fusion, Vol. 59, Núm. 10
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Standardized integration of ITER diagnostics Equatorial Port Plugs
Fusion Engineering and Design, Vol. 146, pp. 1548-1552
2018
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ITER plasma source and building modelling to produce radiation maps
Nuclear Fusion, Vol. 58, Núm. 12