Scientific-Technical Areas
Thematic lines
The objective of this line is contributing to the generation of nuclear fission energy by improving the safety of reactors and facilities and developing new reactor concepts and new nuclear fuels.
Its research includes the design, operation, and dismantling of fission reactors, the study of the fuel cycle, nuclear safety, and waste management (both primary and conditioning and barrier materials). Methodologies for risk assessment and uncertainty reduction are developed and validated for situations that may occur in a nuclear accident. Likewise, advanced nuclear fuel cycles are developed to facilitate the management of radioactive waste and the reduction of their inventories, thereby enhancing the sustainability of nuclear fission as an energy source.
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Characterization, Treatment and Conditioning of Medium, Low, and Very Low-Level Waste
Acondicionamiento de grafito irradiado en hormigones y geopolímeros escalado industrial
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Nuclear Systems
Radiobiology
Advanced Strategies and new Approaches for Protontherapy
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Reactor and Facility Safety
Aplicación a la planta de la investigación en Accidentes Severos
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Reactor and Facility Safety
Assessment of Liquid Source Term for Accidental Post Management Phase
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Physicochemistry of Actinides, Fission Products and Radionuclide Migration
Caracterización de materiales de barreras de RBMA y RBBA
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Nuclear Systems
Datos nucleares para física fundamental y tecnología nuclear
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Nuclear Systems
Detección de Actínidos Mediante Emisión de Neutrones
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Characterization and Treatment of High-Level Waste and Nuclear Fuel
EStudios Avanzados para al desarrollo de procesos de SEparación, Retención y Conversión
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Barrier Materials
Characterization and Treatment of High-Level Waste and Nuclear Fuel
Characterization, Treatment and Conditioning of Medium, Low, and Very Low-Level Waste
Hydrogeochemistry
Physicochemistry of Actinides, Fission Products and Radionuclide Migration
European Partnership on Radioactive Waste Management - 2
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Characterization and Treatment of High-Level Waste and Nuclear Fuel
Impacto de nuevos combustibles con aditivos grafénicos en el back-end nuclear
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Characterization and Treatment of High-Level Waste and Nuclear Fuel
Innovación en tecnología de fabricación nuclear
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Nuclear Systems
LEad fast reactor Safety design and TOols
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Characterization and Treatment of High-Level Waste and Nuclear Fuel
Metodologías de análisis de comportamiento termo-mecánico de combustibles resistentes a accidentes (ATFs): desarrollo y aplicaciones.
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Characterization and Treatment of High-Level Waste and Nuclear Fuel
Metodologías de Análisis Termomecánico de Combustible
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Nuclear Systems
n_TOF contribution
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Characterization and Treatment of High-Level Waste and Nuclear Fuel
OPEn HPC theRmomechanical tools for the development of eAtf fuels
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Physicochemistry of Actinides, Fission Products and Radionuclide Migration
Procesos físico químicos acoplados en la interfaz contenedor metálico / bentonita: efectos sobre la migración de los radionucleidos
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Reactor and Facility Safety
Safety Analysis of SMR with PAssive Mitigation strategies - Severe Accident
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Reactor and Facility Safety
Severe accident research and knowledge management for LWRS
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Characterization and Treatment of High-Level Waste and Nuclear Fuel
Nuclear Systems
Technological Research Action Necessary for Safe PARrtitioning And Nuclear Transmutation
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Characterization and Treatment of High-Level Waste and Nuclear Fuel
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Characterization, Treatment and Conditioning of Medium, Low, and Very Low-Level Waste
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Nuclear Systems
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Physicochemistry of Actinides, Fission Products and Radionuclide Migration
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Reactor and Facility Safety
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Actinide and Fission Product Physicochemical Laboratory
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High-activity Radioactive Waste Research Laboratory
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Low-to-Medium Activity Radioactive Waste Measurement Laboratory
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Nuclear data laboratory
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Safety Systems Analysis Laboratory (LASS)
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FORM-006
Course on radioactive waste characterization
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FORM-029
Course on radioactive waste management
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RESID-001
Determination of U-234/238 in radioactive samples and environmental liquid samples.
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RESID-002
Determination of U-234/238 in radioactive samples and environmental solid samples.
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RESID-003
Determination of activity of gamma emitters in radioactive samples and environmental liquid and solid samples
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RESID-004
Determination of Fe-55 in radioactive samples and environmental liquid samples.
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RESID-005
Determination of Fe-55 in radioactive samples and environmental solid samples.
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RESID-006
Determination of H-3 in radioactive samples and environmental liquid and solid samples (only combustible material).
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RESID-007
Determination of I-129 in radioactive samples and environmental liquid samples.
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RESID-008
Determination of I-129 in radioactive samples and environmental solid samples, after their radiochemical separation.
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RESID-009
Determination of total alpha index of Am-241 in radioactive samples and environmental liquid and solid samples.
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RESID-010
Determination of total beta index of Sr-90 in radioactive samples and liquid and solid samples.
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RESID-011
Determination of Ni-63 in radioactive samples and environmental liquid samples.
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RESID-012
Determination of Ni-63 in radioactive samples and environmental solid samples.
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RESID-013
Determination of Pu-238/Pu-239/Pu-240 in radioactive samples and environmental solid samples.
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RESID-014
Determination of Pu-238/Pu-239/Pu-240 in radioactive samples and environmental liquid samples.
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RESID-015
Determination of Sr-90 in radioactive samples and environmental liquid samples.
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RESID-016
Determination of Sr-90 in radioactive samples and environmental solid samples.
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RESID-017
Determination of Tc-99 in radioactive samples and environmental liquid samples.
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RESID-018
Determination of Tc-99 in radioactive samples and environmental solid samples.
