Publicaciones

• PUBLICACIONES EN REVISTAS

  1.      Neutron induced activation in the EVEDA Accelerator materials: Implications for the accelerator maintenance.

            J. Sanz, M. García, P. Sauvan, D. López, C. Moreno, A. Ibarra, L. Sedano

            Journal of Nuclear Materials. Volume: 386. Pages: 991-993.

            DOI: 10.1016/j.jnucmat.2008.12.277. Published: APR 30 2009

            2.      Design of a Beam Dump for the IFMIF-EVEDA Accelerator

  B. Brañas, D. Iglesias, F. Arranz, G. Barrera, N. Casal, M. García, J. Gómez, D. López, J. I. Martínez, F. Martín-Fuertes, F. Ogando, C. Oliver, J. Sanz, P. Sauvan, A. Ibarra

            Fusion Engineering and Design. Volume: 84 Issue: 2-6. Pages: 509-513.

            DOI: 10.1016/j.fusengdes.2008.12.078. Published: JUN 2009

  3.      First IFMIF/EVEDA radioprotection studies for the preliminary design of the accelerator beam dump

             J. Sanz, M. García, F. Ogando, A. Mayoral, D. López, P. Sauvan, B.Brañas

  Fusion Science and Technology. Volume: 56. Issue: 1. Pages: 273-280. Published: 2009

  4.      Decay Gamma Dose Rates in the EVEDA accelerator: Impact of the deuteron losses uncertainties in the accelerator maintenance

            M. García, J. Sanz, P. Sauvan, F. Ogando, D. López, C. Moreno, A. Mayoral

            Nuclear Technology. Volume: 168. Issue: 1. Pages: 132-138. Published: OCT 2009

  5.      Evaluation of the electroforming technique for IFMIF/EVEDA Beam Dump manufacturing

  F. Arranz, B. Brañas, M. Busch, M. González, A. Muñoz, B. Scepaniack, L. Castro, P. Galán, D. Iglesias, J. Lapeña, D. López, I. Rucandio, D. Plaza, M. García, B. Gómez.

  Fusion Science and Technology. Volume: 60. Issue: 2. Pages: 538-543 Published: 2011

  6.      Relevance of d-D interactions on neutron and tritium production in IFMIF-EVEDA accelerator prototype

            A. Mayoral, J. Sanz, P. Sauvan, D. López , M. García, F. Ogando.

            Journal of Nuclear Materials Volume: 417 Issue: 1-3 Pages: 1288-1293

            DOI: 10.1016/j.jnucmat.2010.12.274 Published: OCT 1 2011

            7.      The IFMIF-EVEDA accelerator Beam Dump design

  D. Iglesias, F. Arranz, J. M. Arroyo, G. Barrera, B. Brañas, N. Casal, M. García, D. López, J. I. Martínez, A. Mayoral, F. Ogando, M. Parro, C. Oliver, D. Rapisarda, J. Sanz, P. Sauvan, A. Ibarra

            Journal of Nuclear Materials. Volume: 417. Issue: 1-3. Pages: 1275-1279

            DOI: 10.1016/j.jnucmat.2010.12.273 Published: OCT 1 2011

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

            V. Blideanu, M. García, P. Joyer, D. López, A. Mayoral, F. Ogando, J. Sanz, P. Sauvan

            Journal of Nuclear Materials. Volume: 417. Issue: 1-3. Pages: 1271-1274

            DOI: 10.1016/j.jnucmat.2010.12.270 Published: OCT 1 2011

  9.      Computational Tools and Nuclear Data for Radioprotection Studies in Low Energy Light Ions Accelerators.

  P. Sauvan, A. Mayoral, J. Sanz, F. Ogando, M. García, D. López, A. J. Koning, A. Ibarra.

            Journal of the Korean Physical Society. Volume: 59. Issue: 2. Pages: 1195-1198

            DOI: 10.3938/jkps.59.1195 Published: AUG 2011

  10.    Sensitivity to nuclear data in the radioprotection design of the LIPAC (IFMIF/EVEDA) BEAM DUMP

             M. García, F. Ogando, P. Sauvan, J. Sanz, D. López, B. Brañas

  Fusion Science and Technology. Volume: 62. Issue: 1. Pages: 265-27. Published: JUL-AUG 2012

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

  F. Ogando, A. Mayoral, R. Juárez, A. Delgado, F. Mota, K. Kondo, M. García, P. Sauvan, J. Sanz, A. Ibarra, J. Molla

  Fusion Science and Technology. Volume: 62. Issue: 1. Pages: 240-245. Published: JUL-AUG 2012

  12.    Status of reliability in determining SDR for manual maintenance activities in ITER: quality assessment of relevant activation cross sections involved.  

  R. García, M. García, R. Pampin, J. Sanz

  Fusion Engineering and Design. Volume 112, 15 November 2016, Pages 177–191.

  http://dx.doi.org/10.1016/j.fusengdes.2016.08.016

  13.    Radiological impact mitigation of waste coming from the European Fusion Reactor DCLL DEMO.

  I. Palermo, R. García, M. García, J. Sanz

  Fusion Engineering and Design, 2017

  https://doi.org/10.1016/j.fusengdes.2017.02.080

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

  T. Eade, M. García, R. García, F. Ogando, P. Pereslavtsev, J. Sanz, A. Travleev, G. Stankunas,

  Fusion Engineering and Design. 2017

  https://doi.org/10.1016/j.fusengdes.2017.02.100

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

  M. García, P. Sauvan, R. García, F. Ogando, J. Sanz

  ND 2016. EPJ Web Conf. Volume 146, 2017.

  https://doi.org/10.1051/epjconf/201714609037

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

  R. García, M. García, F. Ogando, R. Pampin, J. Sanz

  ND 2016: EPJ Web Conf. Volume 146, 2017.

  https://doi.org/10.1051/epjconf/201714609016

  17.    MCNP model of the ITER Tokamak Complex

  A. J. López-Revelles, J. P. Catalán, A. Kolsek, R. Juárez, R. García, M. García, J. Sanz, S. Jakhar, and M. Loughlin

  Special issue “Proceedings of ISFNT-13” in Fusion Engineering and Design. 2018

  18.    Development of methodology to determine PbLi activation in DEMO Breeding Blankets

  M. García, J. P. Catalán, R. García, J. Sanz

  IAEA special issue: “1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems”. 2018

            IAEA-TECDOC-1912. ISBN 978-92-0-107820-9

           19.    Impact of the flowing activated water on maintenance and electronic functioning for the

           pre-conceptual design of the European DEMO fusion reactor

           I. Palermo, M. García, C. Bachmann, S. Ciattaglia, U. Fischer, C. Gliss

  Fusion Engineering and Design, 2020

  https://doi.org/10.1016/j.fusengdes.2020.111499

  20.    Integration of DEMO hazard piping into the tokamak building

  C. Gliss, C. Bachmann, S. Ciattaglia, M. García, G. Federici, M. Koerber, I. Moscato, F. Riedl, I. Palermo, M. Utili

           Fusion Engineering and Design, 2021

           https://doi.org/10.1016/j.fusengdes.2021.112415

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

  I. Palermo, C. Bachmann, L. Di Pace, M. García, C. Gliss, D. Leichtle, N. Terranova

           Fusion Engineering and Design, 2021

           https://doi.org/10.1016/j.fusengdes.2021.112373

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

  G. Caruso, S. Ciattaglia, B. Colling, L. Di Pace, D.N. Dongiovanni, M. D'Onorio, M. Garcia, X.Z.Jin, J. Johnston, D. Leichtle, T. Pinna, M.T. Porfiri, W. Raskob, N. Taylor, N. Terranova, R. Vale

  Fusion Engineering and Design, 2022

  https://doi.org/10.1016/j.fusengdes.2022.113025

  23.    Integrated design of tokamak building concepts including ex-vessel maintenance

  C. Gliss, C. Bachmann, S. Ciattaglia, B. Drumm, M. Garcia, I. Moscato, T. Mull, I. Palermo

  Fusion Engineering and Design, 2022

  https://doi.org/10.1016/j.fusengdes.2022.113068