CEA-Cadarache-ko ikertzaileekin lankidetzan egindako argitalpenak (33)

2024

  1. 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

  2. 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

  3. 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

  4. ITER full model in MCNP for radiation safety demonstration

    Nature Communications , Vol. 15, Núm. 1

2023

  1. Assessment of ITER radiation environment during the remote-handling operation of In-Vessel components with D1SUNED

    Scientific Reports, Vol. 13, Núm. 1

  2. Computational study of the dose-rate field of an ITER heat exchanger due to activated corrosion products

    Fusion Engineering and Design, Vol. 193

  3. Nuclear Scoping Analysis of ITER Bioshield Top Lid Toward its Preliminary Design Review

    Fusion Engineering and Design, Vol. 195

2022

  1. Disruption prediction with artificial intelligence techniques in tokamak plasmas

    Nature Physics, Vol. 18, Núm. 7, pp. 741-750

  2. Enhanced performance in fusion plasmas through turbulence suppression by megaelectronvolt ions

    Nature Physics, Vol. 18, Núm. 7, pp. 776-782

  3. Overview of JET results for optimising ITER operation

    Nuclear Fusion, Vol. 62, Núm. 4

  4. Shielding conceptual designs of ITER TCP ports to protect electronics

    Fusion Engineering and Design, Vol. 176

2021

  1. A full and heterogeneous model of the ITER tokamak for comprehensive nuclear analyses

    Nature Energy, Vol. 6, Núm. 2, pp. 150-157

  2. Improved radiation shielding analysis considering vector calculus

    International Journal of Energy Research, Vol. 45, Núm. 8, pp. 11904-11915

  3. Integral modelling of the ITER cooling water systems radiation source for applications outside of the Bio-shield

    Fusion Engineering and Design, Vol. 171

2019

  1. Nuclear analysis of the ITER torus cryopumps

    Nuclear Fusion, Vol. 59, Núm. 10

  2. Standardized integration of ITER diagnostics Equatorial Port Plugs

    Fusion Engineering and Design, Vol. 146, pp. 1548-1552

2018

  1. ITER plasma source and building modelling to produce radiation maps

    Nuclear Fusion, Vol. 58, Núm. 12

  2. 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

  3. Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports

    Nuclear Fusion, Vol. 58, Núm. 7

  4. Shutdown dose rate mitigation in the ITER upper ports

    Fusion Engineering and Design, Vol. 136, pp. 228-232