Publicaciones en colaboración con investigadores/as de Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (33)

2022

  1. The TechnoFusion Consortium of Spanish institutions and facilities towards the development of fusion materials and related technologies in Europe

    Journal of Nuclear Materials, Vol. 568

2021

  1. IFMIF-DONES RF System

    Fusion Engineering and Design, Vol. 167

2019

  1. The CIEMAT LiPb Loop Permeation Experiment

    Fusion Engineering and Design, Vol. 146, pp. 1228-1232

2018

  1. Design of a System for Hydrogen isotopes Injection into Lead-Lithium

    Fusion Engineering and Design, Vol. 137, pp. 427-434

  2. Neutron characterization of ENSA-DPT type spent fuel cask at trillo nuclear power plant

    Radiation Protection Dosimetry, Vol. 180, Núm. 1-4, pp. 391-394

  3. Neutron field characterization at the independent spent fuel storage installation of the Trillo nuclear power plant

    Applied Radiation and Isotopes, Vol. 135, pp. 33-39

  4. Neutron shielding assessment for the Remote Handling Lower Port rack of ITER

    Fusion Engineering and Design, Vol. 135, pp. 50-58

  5. Study of the neutron field around ENSA-DPT spent fuel transport and storage casks

    Applied Radiation and Isotopes, Vol. 140, pp. 151-156

  6. The tritium extraction and removal system for the DCLL-DEMO fusion reactor

    Nuclear Fusion, Vol. 58, Núm. 9

2017

  1. Design and fabrication of a Permeator Against Vacuum prototype for small scale testing at Lead-Lithium facility

    Fusion Engineering and Design, Vol. 124, pp. 871-875

  2. Methodological approach for DEMO neutronics in the European PPPT programme: Tools, data and analyses

    Fusion Engineering and Design, Vol. 123, pp. 26-31

  3. Radiological impact mitigation of waste coming from the European fusion reactor DEMO with DCLL breeding blanket

    Fusion Engineering and Design, Vol. 124, pp. 1257-1262

2016

  1. Neutronic design studies of a conceptual DCLL fusion reactor for a DEMO and a commercial power plant

    Nuclear Fusion, Vol. 56, Núm. 1

2014

  1. Activation analysis of the water cooling system of the LIPAc beam dump

    Fusion Engineering and Design, Vol. 89, Núm. 9-10, pp. 2053-2056

  2. Neutronic analyses and tools development efforts in the European DEMO programme

    Fusion Engineering and Design, Vol. 89, Núm. 9-10, pp. 1880-1884

2013

  1. Assessment of radiation dose due to the accidental release of radionuclides from a DCLL reactor

    Fusion Engineering and Design

2012

  1. Material irradiation laboratory of the technofusion project: Preliminary radioprotection assessment

    Fusion Science and Technology

  2. Neutronic design analyses for a dual-coolant blanket concept: Optimization for a fusion reactor DEMO

    Fusion Engineering and Design, Vol. 87, Núm. 7-8, pp. 1019-1024

  3. Octalithium plumbate as breeding blanket ceramic: Neutronic performances, synthesis and partial characterization

    Fusion Engineering and Design

  4. Preliminary neutronic assessment of a helium-cooled Li 8PbO 6 breeding blanket design for DEMO

    Fusion Engineering and Design, Vol. 87, Núm. 2, pp. 195-199