RAFAEL
JUAREZ MAÑAS
Profesor Contratado Doctor
CEA-Cadarache
Aix-en-Provence, FranciaPublications in collaboration with researchers from CEA-Cadarache (32)
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
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
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
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
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Neutronic effects of diagnostic shield module length on radiation environment of ITER diagnostic generic upper port plug
Fusion Engineering and Design, Vol. 136, pp. 920-924
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Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports
Nuclear Fusion, Vol. 58, Núm. 7
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Shutdown dose rate mitigation in the ITER upper ports
Fusion Engineering and Design, Vol. 136, pp. 228-232
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The ITER tokamak neutronics reference model C-Model
Fusion Engineering and Design, Vol. 136, pp. 742-746