Publications (28) Publications de MAURICIO GARCIA CAMACHO

2024

  1. ACABLoop simulation tool: Improving the activation prediction of flowing PbLi alloy in support of DEMO fusion reactor design

    Fusion Engineering and Design, Vol. 204

2023

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

    Fusion Engineering and Design, Vol. 191

2022

  1. DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR

    Fusion Engineering and Design, Vol. 176

  2. DONES Systems identification and requirements allocation

    Nuclear Materials and Energy, Vol. 31

  3. Design and manufacturing of the combined quadrupole and corrector magnets for the LIPAc accelerator high energy beam transport line

    Nuclear Fusion, Vol. 62, Núm. 8

2021

  1. Integration of DEMO hazard piping into the tokamak building

    Fusion Engineering and Design, Vol. 168

  2. Radiation level in the DEMO tokamak complex due to activated flowing water: Impact on the architecture of the building

    Fusion Engineering and Design, Vol. 166

  3. Self-rated health among people living with HIV in Spain in 2019: a cross-sectional study

    BMC Infectious Diseases, Vol. 21, Núm. 1

2020

  1. Impact of the flowing activated water on maintenance and electronic functioning for the pre-conceptual design of the European DEMO fusion reactor

    Fusion Engineering and Design, Vol. 153

2018

  1. MCNP model of the ITER Tokamak Complex

    Fusion Engineering and Design, Vol. 136, pp. 859-863

2017

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

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

  2. 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

  3. Reliability of activation cross sections for estimation of shutdown dose rate in the ITER port cell and port interspace

    EPJ Web of Conferences

  4. Study of concrete activation with IFMIF-like neutron irradiation: Status of EAF and TENDL neutron activation cross-sections

    EPJ Web of Conferences

2016

  1. Status of reliability in determining SDDR for manual maintenance activities in ITER: Quality assessment of relevant activation cross sections involved

    Fusion Engineering and Design, Vol. 112, pp. 177-191

2012

  1. Radioprotection analysis for the high energy beam transport line of the accelerator facility of IFMIF

    Fusion Science and Technology

  2. Sensitivity to nuclear data in the radioprotection design of the lipac (IFMIF/EVEDA) beam dump

    Fusion Science and Technology

2011

  1. Computational tools and nuclear data for radioprotection studies in low energy light ions accelerators

    Journal of the Korean Physical Society, Vol. 59, Núm. 23, pp. 1195-1198

  2. Deuteron cross section evaluation for safety and radioprotection calculations of IFMIF/EVEDA accelerator prototype

    Journal of Nuclear Materials

  3. Evaluation of the electroforming technique for IFMIF-EVEDA beam dump manufacturing

    Fusion Science and Technology