2018

R. Juarez, J. Guirao, R. Pampin, M. Loughlin, E. Polunovskiy, Y. Le Tonqueze, L. Bertalot, A. Kolsek, F. Ogando, V. Udintsev, M. Walsh, "Scoping studies of shielding to reduce the Shutdown Dose Rates in the ITER ports", Nuclear Fusion Journal, https://doi.org/10.1088/1741-4326/aac1c5

R. Juárez, J. Guirao, A. Kolsek, A. Lopez, G. Pedroche, L. Bertalot, V.S. Udintsev, M.J. Walsh, P. Sauvan and J. Sanz, "The use of the long modular diagnostics shield module to mitigate shutdown dose rates in the ITER diagnostics equatorial ports", Nuclear Fusion Journal, Volume 58 (2018), Number 5

J. Alguacil, P. Sauvan, R. Juarez, J.P. Catalan, “Assessment and optimization of MCNP memory management for detailed geometry of nuclear fusion facilities”, Fusion Engineering and Design, (2018)

A. Serikov, L. Bertalot, U. Fischer, R. Juarez, “Neutronic effects of Diagnostic Shield Module length on radiation environment of ITER Diagnostic Generic Upper Port Plug”, Fusion Engineering and Design (2018)

D. Leichtle, B. Colling, M. Fabbri, R. Juarez, M. Loughlin, R. Pampin, E. Polunovskiy, A. Serikov, A. Turner, L. Bertalot, “The ITER tokamak neutronics reference model C-model”, Fusion Engineering and Design (2018)

A. J. López-Revelles, J. P. Catalán, A. Kolsek, R. Juarez, R. García, M. García, J. Sanz, “MCNP model of the ITER Tokamak Complex” Fusion Engineering and Design (2018)

A. Kolšek, R. Juarez, A. Lopez, G. Pedroche, A. Serikov, R. Pampin, L. Bertalot, V. Udintsev, J. Guirao, J. Sanz, "Shutdown dose rate mitigation in the ITER upper ports", Fusion Engineering and Design, (2018)

V. Radulović, A. Kolšek, A.-L. Fauré, A.-C. Pottin, F. Pointurier, L. Snoj, “Qualification of heavy water based irradiation device in the JSI TRIGA reactor for irradiations of FT-TIMS samples for nuclear safeguards”, Nuclear Instruments and Methods in Physics Research, A, Volume 885 (2018), Pages 139-144

R. Juárez, A. López, P. Sauvan, G. Pedroche, A. Kolsek, J. Alguacil, D. Ugolini, J. Vallory, I. Ricapito, Y. Poitevin, F. Calvo, Javier Sanz, “Update in the nuclear responses of the European TBMs for ITER during operation and shutdown”, Fusion Engineering and Design (2018)


2017

N. Casal, P. Andrew, R. Barnsley, M. Bassan, J.L. Barbero, L. Bertalot, M. De Bock, B. Brichard, T. Giacomin, R. Juarez, M. Kocan, F. Le Guern, M. Loughlin, Y. Ma, F. Mackel, H. Meister, P. Maquet, V. Martin, R. Reichle, F. Seyvet, A. Sirinelli, P. Shigin, V. Udintsev, G. Vayakis, C. Vorpahl, C. Watts, M. Walsh, “Functional materials for ITER diagnostic systems – Radiation aspects Fusion Engineering and Design Volume 125, (2017), Pages 277-282

J. Ayllon-Guerola, M. Garcia-Munoz, M. Kocan, J. Gonzalez-Martin, J. Rivero-Rodriguez, L. Bertalot, Y. Bonnet, JP. Catalan, J. Galdon, J. Garcia Lopez, T. Giacomin, JP. Gunn, M. Rodriguez-Ramos, R. Reichle, L. Sanchis-Sanchez, G. Vayakis, E. Veshchev, Ch. Vorpahl, M. Walsh, R. Walton. “Dynamic and thermal simulations of a fast-ion loss detector for ITER” , Fusion engineering and Design, Volume 123, (2017), Pages 807-810

R. Villari, P. Batistoni, JP. Catalan, B. Colling, D. Croft, U. Fischer, D. Flammini, N. Fonnesu, L. Jones, A. Klix, B. Kos, M. Kłosowski, I. Kodeli, S. Loreti, F. Moro, J. Naish, B. Obryk, L. Packer, P. Pereslavtsev, R. Pilotti, S. Popovichev, P. Sauvan, IE. Stamatelatos, T. Vasilopoulou, JET Contributors, “ITER oriented neutronics benchmark experiments on neutron streaming and shutdown dose rate at JET”, Fusion engineering and Design, Volume 123, (2017), Pages 171-176

U. Fischer, C. Bachmann, JP. Catalan, T. Eade, D. Flammini, M. Gilbert, J-Ch. Jaboulay, A. Konobeev, D. Leichtle, L. Lu, F. Malouch, F. Moro, P. Pereslavtsev, Y. Qiu, J. Sanz, P. Sauvan, G. Stankunas, A. Travleev, A. Turner, F. Ogando, I. Palermo, R. Villari, “Methodological approach for DEMO neutronics in the European PPPT programme: Tools, data and analyses” , Fusion engineering and Design, Volume 123, (2017), Pages 26-31

T. Eade, M. García, R. García, F. Ogando, P. Pereslavtsev, J. Sanz, G. Stankunas, A. Travleev.” Activation and decay heat analysis of the European DEMO blanket concepts”. Fusion Engineering and Design, Volume 124 (2017) Pages 1241-1245.

I. Palermo, R. García, M. García, J. Sanz. “Radiological impact mitigation of waste coming from the European Fusion Reactor DCLL DEMO”. Fusion Engineering and Design, Volume 127 (2017), Pages 1257-1262.


2016

P. Sauvan, J. P. Catalán, F. Ogando, R. Juárez and J. Sanz. “Development of the R2SUNED Code System for Shutdown Dose Rate Calculations”, IEEE Transactions on Nuclear Science, Volume 63 (2016), Pages 375-384

R. Juarez, P. Sauvan, L. Perez, D. Panayotov, J. Vallory, M. Zmitko, Y. Poitevin, J. Sanz, “Shutdown dose rate analysis of European test blanket modules shields in ITER Equatorial Port #16”, Fusion Engineering and Design, Volumes 109–111, Part B, (2016), Pages 1554-1558

G. Stankunas, A. Tidikas, P. Pereslavstev, J. P. Catalán, R. García, F. Ogando, U. Fischer. “Activity inventories and decay heat calculations for a DEMO with HCPB and HCLL blanket modules”. Fusion Engineering and Design Volumes 109–111, Part A (2016) Pages, 347-352

R. Villari, P. Batistoni, M. Angelone, JP. Catalan, B. Colling, D. Croft, U. Fischer, D. Flammini, A. Klix, S. Loreti, S. Lilley, F. Moro, J. Naish, L. Packer, P. Pereslavtsev, S. Popovichev, P. Sauvan, B. Syme, JET Contributors. “Neutronics experiments and analyses in preparation of DT operations at JET” Fusion Engineering and Design, Volume 109, (2016) Pages 895-905

A. Čufar, I. Lengar, I. Kodeli, A. Milocco, P. Sauvan, S. Conroy, L. Snoj. “Comparison of DT neutron production codes MCUNED, ENEA-JSI source subroutine and DDT” Fusion Engineering and Design, Volume 109 (2016 )pp 164-168

D. Leichtle, P.Y. Chaffard, J. Izquierdo, R. Juarez, R. Pampin, A. Portone, "Status of the ITER tokamak nuclear shielding and radiological protection design", Fusion Engineering and Design, Volumes 109–111, Part A, (2016), Pages 666-672.

R. Pampin, A. Suarez, A. Arnould, N. Casal, R. Juarez, A. Martin, F. Moro, F. Mota, E. Polunovskiy, F. Sabourin, "Study of shielding options for lower ports for mitigation of neutron environment and shutdown dose inside the ITER cryostat", Fusion Engineering and Design, Volumes 109–111, Part B, (2016), Pages 1408-1411

Juan C. Mora, A. Baeza, B. Robles, J. Sanz; "Assessment for the management of NORM wastes in conventional hazardous and nonhazardous waste landfills", Journal of Hazardous Materials, Volume 310, (2016), Pages 161–169

R. Garcia, M. Garcia, R. Pampin, J. Sanz; "Status of reliability in determining SDDR for manual maintenance activities in ITER: Quality assessment of relevant activation cross sections involved", Fusion Engineering and Design, Volume 112, (2016), Pages 177-191.