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Assessment of interatomic potentials for atomistic analysis of static and dynamic properties of screw dislocations in W

Journal of physics. Condensed matter, 2013-02, Vol.25 (8), p.085702-085702

2013

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First principles study of the behavior of hydrogen atoms in a W monovacancy

Journal of materials science, 2016-02, Vol.51 (3), p.1445-1455

2016

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Atomistic molecular point of view for liquid lead and lithium in Nuclear Fusion technology

Journal of nuclear materials, 2013-09, Vol.440 (1-3), p.98-103

2013

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Influence of grain boundaries on the radiation-induced defects and hydrogen in nanostructured and coarse-grained tungsten

Acta materialia, 2017-01, Vol.122, p.277-286

2017

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A dislocation dynamics study of the strength of stacking fault tetrahedra. Part I: interactions with screw dislocations

Philosophical magazine (Abingdon, England), 2008-02, Vol.88 (6), p.809-840

2008

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Viability of the ESS-Bilbao neutron source for irradiation of nuclear fusion materials

Journal of nuclear materials, 2014-01, Vol.444 (1-3), p.469-474

2014

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Comparative study of radiation damage accumulation in Cu and Fe

Journal of nuclear materials, 2000, Vol.276 (1), p.13-21

2000

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Limitations for tungsten as plasma facing material in the diverse scenarios of the European inertial confinement fusion facility HiPER: Current status and new approaches

Matter and Radiation at Extremes, 2020-09, Vol.5 (5)

2020

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A dislocation dynamics study of the strength of stacking fault tetrahedra. Part II: interactions with mixed and edge dislocations

Philosophical magazine (Abingdon, England), 2008-02, Vol.88 (6), p.841-863

2008

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Atomistically informed dislocation dynamics in fcc crystals

Journal of the mechanics and physics of solids, 2008-03, Vol.56 (3), p.869-895

2008

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Development of experimental irradiation strategies to evaluate the robustness of TODGA and water-soluble BTP extraction systems for advanced nuclear fuel recycling

Radiation physics and chemistry (Oxford, England : 1993), 2020-12, Vol.177, p.109094, Article 109094

2020

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The influence of high grain boundary density on helium retention in tungsten

Journal of nuclear materials, 2015-02, Vol.457, p.80-87

2015

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Molecular dynamics study of structure transformation and H effects in irradiated silica

Journal of nuclear materials, 2009-04, Vol.386, p.75-78

2009

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Hydrogen accumulation in nanostructured as compared to the coarse-grained tungsten

Journal of nuclear materials, 2014-10, Vol.453 (1-3), p.287-295

2014

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H trapping and mobility in nanostructured tungsten grain boundaries: a combined experimental and theoretical approach

Nuclear fusion, 2015-11, Vol.55 (11), p.113009

2015

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Materials Research for HiPER Laser Fusion Facilities: Chamber Wall, Structural Material and Final Optics

Fusion science and technology, 2011-08, Vol.60 (2), p.565-569

2011

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Femtosecond laser irradiation induced-high electronic excitation in band gap materials: A quantum-kinetic model based on Boltzmann equation

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2015-06, Vol.352, p.167-170

2015

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Radiolytic degradation of sulphonated BTP and acetohydroxamic acid under EURO-GANEX process conditions

Radiation physics and chemistry (Oxford, England : 1993), 2021-06, Vol.183, p.109402, Article 109402

2021

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LIBRETTO-4: Understanding and modeling tritium transport under irradiation

Fusion engineering and design, 2011-10, Vol.86 (9), p.2374-2377

2011

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Morphological and microstructural characterization of nanostructured pure α-phase W coatings on a wide thickness range

Applied surface science, 2014-10, Vol.316, p.1-8

2014

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Temperature dependence of damage accumulation in α-zirconium

Journal of nuclear materials, 2007-08, Vol.367, p.338-343

2007

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Ab initio study of tungsten defects near the surface

Modelling and simulation in materials science and engineering, 2016-05, Vol.24 (4), p.45006-45020

2016

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Synchronous parallel kinetic Monte Carlo for continuum diffusion-reaction systems

Journal of computational physics, 2008-04, Vol.227 (8), p.3804-3823

2008

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Influence of self-interstitial mobility on damage accumulation in zirconium under fission irradiation conditions

Journal of nuclear materials, 2007-05, Vol.362 (2-3), p.293-299

2007

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Conceptual design of a ceramic breeding blanket for laser fusion power plants with online tunable tritium breeding ratio based on a variable neutron reflector: Remarkable no need of isotopic enrichment

Fusion engineering and design, 2020-06, Vol.155, p.111648, Article 111648

2020

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Assessment of interatomic potentials for atomistic analysis of static and dynamic properties of screw dislocations in W

First principles study of the behavior of hydrogen atoms in a W monovacancy

Atomistic molecular point of view for liquid lead and lithium in Nuclear Fusion technology

Influence of grain boundaries on the radiation-induced defects and hydrogen in nanostructured and coarse-grained tungsten

A dislocation dynamics study of the strength of stacking fault tetrahedra. Part I: interactions with screw dislocations

Viability of the ESS-Bilbao neutron source for irradiation of nuclear fusion materials

Comparative study of radiation damage accumulation in Cu and Fe

Limitations for tungsten as plasma facing material in the diverse scenarios of the European inertial confinement fusion facility HiPER: Current status and new approaches

A dislocation dynamics study of the strength of stacking fault tetrahedra. Part II: interactions with mixed and edge dislocations

Atomistically informed dislocation dynamics in fcc crystals

Development of experimental irradiation strategies to evaluate the robustness of TODGA and water-soluble BTP extraction systems for advanced nuclear fuel recycling

The influence of high grain boundary density on helium retention in tungsten

Molecular dynamics study of structure transformation and H effects in irradiated silica

Hydrogen accumulation in nanostructured as compared to the coarse-grained tungsten

H trapping and mobility in nanostructured tungsten grain boundaries: a combined experimental and theoretical approach

Materials Research for HiPER Laser Fusion Facilities: Chamber Wall, Structural Material and Final Optics

Femtosecond laser irradiation induced-high electronic excitation in band gap materials: A quantum-kinetic model based on Boltzmann equation

Radiolytic degradation of sulphonated BTP and acetohydroxamic acid under EURO-GANEX process conditions

LIBRETTO-4: Understanding and modeling tritium transport under irradiation

Morphological and microstructural characterization of nanostructured pure α-phase W coatings on a wide thickness range

Temperature dependence of damage accumulation in α-zirconium

Ab initio study of tungsten defects near the surface

Synchronous parallel kinetic Monte Carlo for continuum diffusion-reaction systems

Influence of self-interstitial mobility on damage accumulation in zirconium under fission irradiation conditions

Conceptual design of a ceramic breeding blanket for laser fusion power plants with online tunable tritium breeding ratio based on a variable neutron reflector: Remarkable no need of isotopic enrichment

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