Výsledky vyhledávání - "J. M. Perlado"

Akademický článek

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

Autor: R. Gonzalez-Arrabal, A. Rivera, J. M. Perlado

Publikováno v: Matter and Radiation at Extremes, Vol 5, Iss 5, Pp 055201-055201-21 (2020)

The high-power laser energy research (HiPER) project was a European project for demonstrating the feasibility of inertial fusion energy based on using direct-drive targets in a shock ignition scheme using a drywall evacuated chamber. HiPER was intend

Externí odkaz: https://doaj.org/article/a07987e3b67644f287e2ef72c23ffb4e

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Spectral composition of thermonuclear particle and recoil nuclear emissions from laser fusion targets intended for modern ignition experiments

Autor: D. V. Il’in, S. Yu. Gus’kov, Vladislav B Rozanov, V. E. Sherman, N. V. Zmitrenko, J M Perlado

Publikováno v: Plasma Physics and Controlled Fusion. 60:085004

Determination of the spectra and yields of thermonuclear particles is an actual research line for inertial confinement fusion (ICF) in two areas: the development of diagnostic methods for ICF plasma and thermonuclear reactor design for energy product

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::36f3a18f2ed3efb785361ea19883988a
https://doi.org/10.1088/1361-6587/aac739

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Dosimetric Impact Evaluation of Primary Coolant Chemistry of the Internal Tritium Breeding Cycle of a Fusion Reactor DEMO

Autor: J. M. Perlado, L.A. Sedano, M. Velarde

Publikováno v: Fusion Science and Technology. 54:122-126

Tritium will be responsible for a large fraction of the environmental impact of the first generation of DT fusion reactors. Today, the efforts of conceptual development of the tritium cycle for DEMO are mainly centred in the so called Inner Breeding

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f0749ec69d82b988feeb7d6f309347d0
https://doi.org/10.13182/fst08-a1778

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Tritium Dose Assessments with Regulatory and Advanced Computer Models for the Potential European ITER Site Vandellós (Spain)

Autor: J. M. Perlado, M. Velarde, W. Raskob

Publikováno v: Fusion Science and Technology. 48:492-495

Deterministic and probabilistic dose assessments for releases of tritium have been performed for the potential European ITER Site of Vandellos (Spain). Besides national regulatory models, internationally accepted computer codes such as NORMTRI (for n

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::514a7ce871b83d51838b3906cd5968a5
https://doi.org/10.13182/fst05-a973

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[Untitled]

Autor: S. Tanaka, M. T. Tobin, Y. Seki, J. M. Perlado, S. J. Brereton, S. J. Piet

Publikováno v: Journal of Fusion Energy. 16:133-140

This paper summarizes safety and environmental issues of Inertial Fusion Energy (IFE): inventories, effluents, maintenance, accident safety, waste management, and recycling. The fusion confinement approach among inertial and magnetic options affects

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5f6865df248b2b8e52739c9acd5de943
https://doi.org/10.1023/a:1022581400624

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

Autor: D Cereceda, A Stukowski, M R Gilbert, S Queyreau, Lisa Ventelon, M-C Marinica, J M Perlado, J Marian

Publikováno v: Journal of Physics: Condensed Matter, ISSN 0953-8984, 2013-02, Vol. 25, No. 8
Archivo Digital UPM
Universidad Politécnica de Madrid

Screw dislocations in bcc metals display non-planar cores at zero temperature which result in high lattice friction and thermally-activated strain rate behavior. In bcc W, electronic structure molecular statics calculations reveal a compact, non-dege

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::452b82a527938cbd102795acece1644d
http://arxiv.org/abs/1204.5501

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Numerical and theoretical studies on the ignition of ICF plasmas driven by ion beams

Autor: M. Piera, J. J. Honrubia, E. Minguez, J. M. Aragones, P. Velarde, J. M. Martinez-Val, H. Hora, G. Velarde, J. M. Perlado, S. Eliezer

Publikováno v: Il Nuovo Cimento A. 106:1873-1881

Deuterium-tritium plasmas inertially confined can undergo fusion ignition if some requirements are met. The final temperature of the plasma at the end of the implosion process has to be large enough to produce the overheating of the plasma by the ene

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::565943b8c6fc557f25d0cc1155e7cd4d
https://doi.org/10.1007/bf02780590

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