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Ingeniería Industrial: Tecnologías de sistemas de fisión
Tecnologías de sistemas de fisión, fusión y de fuentes de irradiación

Tecnologías de Sistemas de Fisión, Fusión y de Fuentes de Irradiación


Miembros

- Javier Alguacil Orejudo

ResearcherID Orcid

- Juan Pablo Catalán Pérez

ResearcherID Orcid

- Laura Estevez Nuñez

Artículos WOS

- Mauricio García Camacho

ResearcherID Orcid

- Raquel García Martín

- Rafael Juarez Mañas

ResearcherID Orcid

- Aljaz Kolsek

- Antonio Jesus López Revelles

ResearcherID Orcid

- Francisco M. Ogando Serrano

ResearcherID Orcid

- Gabriel Pedroche Sánchez

- Javier Sanz Gozalo (IP)

ResearcherID Orcid

- Patrick Sauvan

ResearcherID Orcid

2020

2019

2018

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

FUSION ENGINEERING AND DESIGN Volumen: 137 Páginas: 427-434 DOI: 10.1016/j.fusengdes.2018.10.006

The ITER tokamak neutronics reference model C-Model

FUSION ENGINEERING AND DESIGN Volumen: 136 Páginas: 742-746 Subdivisión: A Número especial: SI DOI: 10.1016/j.fusengdes.2018.04.002

MCNP model of the ITER Tokamak Complex

FUSION ENGINEERING AND DESIGN Volumen: 136 Páginas: 859-863 Subdivisión: B Número especial: SI DOI: 10.1016/j.fusengdes.2018.04.023

Assessment and optimization of MCNP memory management for detailed geometry of nuclear fusion facilities

FUSION ENGINEERING AND DESIGN Volumen: 136 Páginas: 386-389 Subdivisión: A Número especial: SI DOI: 10.1016/j.fusengdes.2018.02.048

Neutronic effects of diagnostic shield module length on radiation environment of ITER diagnostic generic upper port plug

FUSION ENGINEERING AND DESIGN Volumen: 136 Páginas: 920-924 Subdivisión: B Número especial: SI DOI: 10.1016/j.fusengdes.2018.04.040

Shutdown dose rate mitigation in the ITER upper ports

FUSION ENGINEERING AND DESIGN Volumen: 136 Páginas: 228-232 Subdivisión: A Número especial: SI DOI: 10.1016/j.fusengdes.2018.01.070

The role of nuclear data for fusion nuclear technology

FUSION ENGINEERING AND DESIGN Volumen: 136 Páginas: 162-167 Subdivisión: A Número especial: SI DOI: 10.1016/j.fusengdes.2018.01.036

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

FUSION ENGINEERING AND DESIGN Volumen: 135 Páginas: 50-58 Subdivisión: A DOI: 10.1016/j.fusengdes.2018.06.023

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

APPLIED RADIATION AND ISOTOPES Volumen: 140 Páginas: 151-156 DOI: 10.1016/j.apradiso.2018.07.001

ITER plasma source and building modelling to produce radiation maps

NUCLEAR FUSION Volumen: 58 Número: 12 Número de artículo: 126012 DOI: 10.1088/1741-4326/aadf9c

Update in the nuclear responses of the European TBMs for ITER during operation and shutdown

FUSION ENGINEERING AND DESIGN Volumen: 134 Páginas: 92-96 DOI: 10.1016/j.fusengdes.2018.06.022

NEUTRON CHARACTERIZATION OF ENSA-DPT TYPE SPENT FUEL CASK AT TRILLO NUCLEAR POWER PLANT

RADIATION PROTECTION DOSIMETRY Volumen: 180 Número: 1-4 Páginas: 391-394 DOI: 10.1093/rpd/ncy060

EXPERIMENTAL EVALUATION OF NEUTRON SHIELDING MATERIALS

RADIATION PROTECTION DOSIMETRY Volumen: 180 Número: 1-4 Páginas: 382-385 DOI: 10.1093/rpd/ncx202

Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports

NUCLEAR FUSION Volumen: 58 Número: 7 Número de artículo: 076018 DOI: 10.1088/1741-4326/aac1c5

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

APPLIED RADIATION AND ISOTOPES Volumen: 135 Páginas: 33-39 DOI: 10.1016/j.apradiso.2018.01.002

The LIPAc beam dump

FUSION ENGINEERING AND DESIGN Volumen: 127 Páginas: 127-138 DOI: 10.1016/j.fusengdes.2017.12.018

The use of the long modular diagnostics shield module to mitigate shutdown dose rates in the ITER diagnostics equatorial ports

NUCLEAR FUSION Volumen: 58 Número: 5 Número de artículo: 056015 DOI: 10.1088/1741-4326/aaadce

Qualification of heavy water based irradiation device in the JSI TRIGA reactor for irradiations of FT-TIMS samples for nuclear safeguards

INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT Volumen: 885 Páginas: 139-144 DOI: 10.1016/j.nima.2017.12.046

2017

Nuclear data for fusion technology - the European approach

ND 2016: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY Editado por:Plompen, A; Hambsch, FJ; Schillebeeckx, P; Mondelaers, W; Heyse, J; Kopecky, S; Siegler, P; Oberstedt, S Colección: EPJ Web of Conferences Volumen: 146 Número de artículo: 09003 DOI: 10.1051/epjconf/201714609003

Implementation of a new energy-angular distribution of particles emitted by deuteron induced nuclear reaction in transport simulations

ND 2016: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY Editado por:Plompen, A; Hambsch, FJ; Schillebeeckx, P; Mondelaers, W; Heyse, J; Kopecky, S; Siegler, P; Oberstedt, S Colección: EPJ Web of Conferences Volumen: 146 Número de artículo: 02010 DOI: 10.1051/epjconf/201714602010

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

ND 2016: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY Editado por:Plompen, A; Hambsch, FJ; Schillebeeckx, P; Mondelaers, W; Heyse, J; Kopecky, S; Siegler, P; Oberstedt, S Colección: EPJ Web of Conferences Volumen: 146 Número de artículo: 09037 DOI: 10.1051/epjconf/201714609037

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

ND 2016: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY Editado por:Plompen, A; Hambsch, FJ; Schillebeeckx, P; Mondelaers, W; Heyse, J; Kopecky, S; Siegler, P; Oberstedt, S Colección: EPJ Web of Conferences Volumen: 146 Número de artículo: 09016 DOI: 10.1051/epjconf/201714609016

CAD-Based Shielding Analysis for ITER Port Diagnostics

ICRS-13 & RPSD-2016, 13TH INTERNATIONAL CONFERENCE ON RADIATION SHIELDING & 19TH TOPICAL MEETING OF THE RADIATION PROTECTION AND SHIELDING DIVISION OF THE AMERICAN NUCLEAR SOCIETY - 2016 Editado por:Malvagi, F; Malouch, F; Diop, CMB; Miss, J; Trama, JC Colección: EPJ Web of Conferences Volumen: 153 Número de artículo: 03010 DOI: 10.1051/epjconf/201715303010

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

FUSION ENGINEERING AND DESIGN Volumen: 123 Páginas: 26-31 DOI: 10.1016/j.fusengdes.2017.01.053

Activation and decay heat analysis of the European DEMO blanket concepts

FUSION ENGINEERING AND DESIGN Volumen: 124 Páginas: 1241-1245 DOI: 10.1016/j.fusengdes.2017.02.100

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

FUSION ENGINEERING AND DESIGN Volumen: 124 Páginas: 871-875 DOI: 10.1016/j.fusengdes.2017.02.060

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

FUSION ENGINEERING AND DESIGN Volumen: 124 Páginas: 1257-1262 DOI: 10.1016/j.fusengdes.2017.02.080

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

FUSION ENGINEERING AND DESIGN Volumen: 123 Páginas: 171-176 DOI: 10.1016/j.fusengdes.2017.03.037

Dynamic and thermal simulations of a fast-ion loss detector for ITER

FUSION ENGINEERING AND DESIGN Volumen: 123 Páginas: 807-810 DOI: 10.1016/j.fusengdes.2017.04.071

Functional materials for ITER diagnostic systems - Radiation aspects

FUSION ENGINEERING AND DESIGN Volumen: 125 Páginas: 277-282 DOI: 10.1016/j.fusengdes.2017.08.017

Radiation In-Port Cross-Talks for ITER Port Diagnostics

FUSION SCIENCE AND TECHNOLOGY Volumen: 72 Número: 4 Páginas: 559-565 DOI: 10.1080/15361055.2017.1347470

2016

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

FUSION ENGINEERING AND DESIGN Volumen: 112 Páginas: 177-191 DOI: 10.1016/j.fusengdes.2016.08.016

Status of the ITER tokamak nuclear shielding and radiological protection design

FUSION ENGINEERING AND DESIGN Volumen: 109 Páginas: 666-672 Subdivisión: A DOI: 10.1016/j.fusengdes.2016.02.023

Activity inventories and decay heat calculations for a DEMO with HCPB and HCLL blanket modules

FUSION ENGINEERING AND DESIGN Volumen: 109 Páginas: 347-352 Subdivisión: A DOI: 10.1016/j.fusengdes.2016.02.101

Comparison of DT neutron production codes MCUNED, ENEA-JSI source subroutine and DDT

FUSION ENGINEERING AND DESIGN Volumen: 109 Páginas: 164-168 Subdivisión: A DOI: 10.1016/j.fusengdes.2016.03.036

Neutronics experiments and analyses in preparation of DT operations at JET

FUSION ENGINEERING AND DESIGN Volumen: 109 Páginas: 895-905 Subdivisión: A DOI: 10.1016/j.fusengdes.2016.01.055

Study of shielding options for lower ports for mitigation of neutron environment and shutdown dose inside the ITER cryostat

FUSION ENGINEERING AND DESIGN Volumen: 109 Páginas: 1408-1411 Subdivisión: B DOI: 10.1016/j.fusengdes.2015.12.010

Assessment for the management of NORM wastes in conventional hazardous and nonhazardous waste landfills

JOURNAL OF HAZARDOUS MATERIALS Volumen: 310 Páginas: 161-169 DOI: 10.1016/j.jhazmat.2016.02.039

Development of the R2SUNED Code System for Shutdown Dose Rate Calculations

IEEE TRANSACTIONS ON NUCLEAR SCIENCE Volumen: 63 Número: 1 Páginas: 375-384 Subdivisión: 2 DOI: 10.1109/TNS.2015.2507138

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

NUCLEAR FUSION Volumen: 56 Número: 1 Número de artículo: 016001 DOI: 10.1088/0029-5515/56/1/016001

Tecnologías de sistemas de fisión, fusión y de fuentes de irradiación