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Journal of Nuclear Materials

Resumen/Descripción – provisto por la editorial en inglés

The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.

The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.

The following list describes topics within the scope of the Journal.Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components; fission product behavior.Materials aspects of the entire fuel cycle.Materials aspects of the actinides and their compounds.Performance of nuclear waste materials; immobilization of wastes.Fusion reactor materials, including first walls, blankets, insulators and magnets.Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials.Please note: a manuscript must focus on materials science and engineering related to nuclear applications. Thus, all topics within nuclear science and engineering or materials science and engineering do not necessarily fall within the scope. Topics outside the scope of the Journal will not be considered, and potential alternative journals are indicated in brackets in the list below. Typical examples of topics which are out of scope for the Journal include:

(1) Topics in nuclear engineering and other areas not addressing materials, such as: Particle transport, cross-sections or isotope ratios (Radiation Physics and Chemistry; Annals of Nuclear Energy) Process engineering (Materials Science and Engineering A; Materials and Design) Thermal hydraulics (Nuclear engineering and design) Isotope separation processes (Nuclear Instrument and Methods B) Fusion reactor design and technology (Fusion Engineering & Design) Plasma physics (Physics Letters A)(2) Materials topics not addressing nuclear applications, such as general studies in:Physical properties including modeling and simulation (Materials Science and Engineering A, Materials Letters) Metallurgy (Journal of Alloys and Compounds; Materials Science and Engineering A) Corrosion (Corrosion Science) Welding and joining (Journal of Alloys and Compounds; Materials and Design) Ceramics (Journal of the European Ceramics Society; Ceramics international)

Palabras clave – provistas por la editorial

No disponibles.

Disponibilidad

Institución detectada	Período	Navegá	Descargá	Solicitá
No detectada	desde abr. 1959 / hasta dic. 2023	ScienceDirect

Información

Tipo de recurso:

revistas

ISSN impreso

0022-3115

ISSN electrónico

1873-4820

Fecha de publicación

1959-

Cobertura temática

Ingeniería mecánica

Tabla de contenidos

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doi: 10.1016/s0022-3115(02)00935-2

Contribution of thermal neutrons to radiation hardening of pure copper

S.A Fabritsiev; A.S Pokrovsky

Pp. 78-83

doi: 10.1016/j.jnucmat.2006.06.012

Solubility of crystalline and metamict zircon: A thermodynamic analysis

Desmond Tromans

Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.

Pp. 221-233

doi: 10.1016/j.jnucmat.2008.08.056

High temperature reactors

I.V. Dulera; R.K. Sinha

Palabras clave: Nuclear Energy and Engineering; General Materials Science; Nuclear and High Energy Physics.

Pp. 183-188

doi: 10.1016/j.jnucmat.2010.08.003

Ab initio-based diffusion theory and tracer diffusion in Ni–Cr and Ni–Fe alloys

J.D. Tucker; R. Najafabadi; T.R. Allen; D. Morgan

Pp. 216-234

doi: 10.1016/j.jnucmat.2010.09.029

PERFECT – Prediction of Irradiation Damage Effects on Reactor Components: A summary

Jean-Paul Massoud; Stéphane Bugat; Bernard Marini; David Lidbury; Steven Van Dyck

Pp. 2-6

doi: 10.1016/j.jnucmat.2010.05.019

Modeling the long-term evolution of the primary damage in ferritic alloys using coarse-grained methods

C.S. Becquart; A. Barbu; J.L. Bocquet; M.J. Caturla; C. Domain; C.-C. Fu; S.I. Golubov; M. Hou; L. Malerba; C.J. Ortiz; A. Souidi; R.E. Stoller

Pp. 39-54

doi: 10.1016/j.jnucmat.2010.05.020

On the correlation between irradiation-induced microstructural features and the hardening of reactor pressure vessel steels

M. Lambrecht; E. Meslin; L. Malerba; M. Hernández-Mayoral; F. Bergner; P. Pareige; B. Radiguet; A. Almazouzi

Pp. 84-89

doi: 10.1016/j.jnucmat.2010.09.056

A method of examining iron oxides speciation and transport to steam generators during nuclear power reactor startups

Jerzy A. Sawicki; Barbara D. Sawicka; James E. Price

Pp. 157-164

doi: 10.1016/j.jnucmat.2010.12.175

Displacement damage induced in iron by gammas and neutrons under irradiation in the IFMIF test cell

S.P. Simakov; U. Fischer

Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.

Pp. 1321-1324

doi: 10.1016/j.jnucmat.2011.12.004

Microstructural changes of a thermally aged stainless steel submerged arc weld overlay cladding of nuclear reactor pressure vessels

T. Takeuchi; J. Kameda; Y. Nagai; T. Toyama; Y. Matsukawa; Y. Nishiyama; K. Onizawa

Pp. 60-64