Catálogo de publicaciones - revistas
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
Tabla de contenidos
Surface charging patterns of stainless alloys – Effect of ageing in conditions of primary cooling circuit of pressurized water reactors
B. Martin Cabanas; J. Lützenkirchen; S. Leclercq; P. Barboux; G. Lefèvre
Pp. 150-155
Densification of uranium dioxide fuel pellets prepared by spark plasma sintering (SPS)
Lihao Ge; Ghatu Subhash; Ronald H. Baney; James S. Tulenko; Edward McKenna
Palabras clave: Nuclear Energy and Engineering; General Materials Science; Nuclear and High Energy Physics.
Pp. 1-9
Confirmatory investigations on the flux effect and associated unstable matrix damage in RPV materials exposed to high neutron fluence
R. Chaouadi; R. Gérard
Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.
Pp. 267-274
Flux effect analysis in WWER-440 reactor pressure vessel steels
A. Kryukov; D. Blagoeva; L. Debarberis
Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.
Pp. 171-175
Correlation between radiation damage and magnetic properties in reactor vessel steels
R.A. Kempf; J. Sacanell; J. Milano; N. Guerra Méndez; E. Winkler; A. Butera; H. Troiani; M.E. Saleta; A.M. Fortis
Pp. 57-62
Effects of neutron irradiation on microstructures and hardness of stainless steel weld-overlay cladding of nuclear reactor pressure vessels
T. Takeuchi; Y. Kakubo; Y. Matsukawa; Y. Nozawa; T. Toyama; Y. Nagai; Y. Nishiyama; J. Katsuyama; Y. Yamaguchi; K. Onizawa
Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.
Pp. 273-276
Thermal ageing mechanisms of VVER-1000 reactor pressure vessel steels
Yaroslav I. Shtrombakh; Boris A. Gurovich; Evgenia A. Kuleshova; Dmitry A. Maltsev; Svetlana V. Fedotova; Anna A. Chernobaeva
Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.
Pp. 348-358
Evolution of structure and properties of VVER-1000 RPV steels under accelerated irradiation up to beyond design fluences
B. Gurovich; E. Kuleshova; Ya. Shtrombakh; S. Fedotova; D. Maltsev; A. Frolov; O. Zabusov; D. Erak; D. Zhurko
Pp. 23-32
Contributions of Cu-rich clusters, dislocation loops and nanovoids to the irradiation-induced hardening of Cu-bearing low-Ni reactor pressure vessel steels
F. Bergner; F. Gillemot; M. Hernández-Mayoral; M. Serrano; G. Török; A. Ulbricht; E. Altstadt
Pp. 37-44
Temperature dependence of irradiation hardening due to dislocation loops and precipitates in RPV steels and model alloys
S. Kotrechko; V. Dubinko; N. Stetsenko; D. Terentyev; Xinfu He; M. Sorokin
Pp. 6-15