Publicaciones en colaboración con investigadores/as de Karlsruhe Institute of Technology (31)

2024

  1. Engineering design status of IFMIF-DONES High Energy Beam Transport line and Beam Dump system inside the TIR and RIZ

    Fusion Engineering and Design, Vol. 202

  2. Overview of recent advancements in IFMIF-DONES neutronics activities

    Fusion Engineering and Design, Vol. 201

2023

  1. Overview of IFMIF-DONES diagnostics: Requirements and techniques

    Fusion Engineering and Design, Vol. 191

  2. Status of the engineering design of the IFMIF-DONES high energy beam transport line and beam dump system

    Journal of Physics: Conference Series

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. Maturation of critical technologies for the DEMO balance of plant systems

    Fusion Engineering and Design, Vol. 179

  4. Overview of JET results for optimising ITER operation

    Nuclear Fusion, Vol. 62, Núm. 4

2020

  1. Nuclear data activities of the EUROfusion consortium

    ND 2019: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY

  2. Preliminary design of the HEBT of IFMIF DONES

    Fusion Engineering and Design, Vol. 153

  3. The joint evaluated fission and fusion nuclear data library, JEFF-3.3

    European Physical Journal A, Vol. 56, Núm. 7

2019

  1. Integration of safety in IFMIF-DONES design

    Safety, Vol. 5, Núm. 4

  2. Neutronics of the IFMIF-DONES irradiation facility

    Fusion Engineering and Design, Vol. 146, pp. 1276-1281

2018

  1. 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

  2. Shutdown dose rate mitigation in the ITER upper ports

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

  3. The ITER tokamak neutronics reference model C-Model

    Fusion Engineering and Design, Vol. 136, pp. 742-746

  4. The role of nuclear data for fusion nuclear technology

    Fusion Engineering and Design, Vol. 136, pp. 162-167

2017

  1. Activation and decay heat analysis of the European DEMO blanket concepts

    Fusion Engineering and Design, Vol. 124, pp. 1241-1245

  2. CAD-Based Shielding Analysis for ITER Port Diagnostics

    EPJ Web of Conferences

  3. ITER oriented neutronics benchmark experiments on neutron streaming and shutdown dose rate at JET

    Fusion Engineering and Design, Vol. 123, pp. 171-176