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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
Tabla de contenidos
Chemical composition effect on VVER-1000 RPV weld metal thermal aging
B.A. Gurovich; A.A. Chernobaeva; D.Yu Erak; E.A. Kuleshova; D.A. Zhurko; V.B. Papina; M.A. Skundin; D.A. Maltsev
Pp. 540-549
Energy spectra of primary knock-on atoms under neutron irradiation
M.R. Gilbert; J. Marian; J.-Ch. Sublet
Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.
Pp. 121-134
Hardening and microstructural evolution of A533b steels irradiated with Fe ions and electrons
H. Watanabe; S. Arase; T. Yamamoto; P. Wells; T. Onishi; G.R. Odette
Pp. 243-250
Experimental investigation on molten pool representing corium composition at Fukushima Daiichi nuclear power plant
Sang Mo An; Jin Ho Song; Jong-Yun Kim; HwanYeol Kim; Masanori Naitoh
Pp. 164-171
Fission products and nuclear fuel behaviour under severe accident conditions part 3: Speciation of fission products in the VERDON-1 sample
C. Le Gall; E. Geiger
; A. Gallais-During; Y. Pontillon; J. Lamontagne; E. Hanus; G. Ducros
Palabras clave: Nuclear Energy and Engineering; General Materials Science; Nuclear and High Energy Physics.
Pp. 291-298
Fission products and nuclear fuel behaviour under severe accident conditions part 1: Main lessons learnt from the first VERDON test
Y. Pontillon; E. Geiger; C. Le Gall; S. Bernard; A. Gallais-During; P.P. Malgouyres; E. Hanus; G. Ducros
Palabras clave: Nuclear Energy and Engineering; General Materials Science; Nuclear and High Energy Physics.
Pp. 363-384
Differential dpa calculations with SPECTRA-PKA
M.R. Gilbert; J.-Ch. Sublet
Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.
Pp. 101-108
Review of sintering and densification in nuclear fuels: Physical mechanisms, experimental results, and computational models
Ian Greenquist; Michael R. Tonks; Yongfeng Zhang
Palabras clave: Nuclear Energy and Engineering; General Materials Science; Nuclear and High Energy Physics.
Pp. 381-395
The electrochemical properties of alloy 690 in simulated pressurized water reactor primary water: Effect of temperature
Jie Yang; Yanhui Li; Aoni Xu; Balazs Fekete; Digby D. Macdonald
Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.
Pp. 305-315
CRUD deposition in accelerated high-temperature water: Investigation on the effect of substrate material and water chemistry
Stefano Cassineri; Jonathan Duff; Michele Curioni; Andrew Banks; Fabio Scenini
Palabras clave: Nuclear and High Energy Physics; General Materials Science; Nuclear Energy and Engineering.
Pp. 151915