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)
《核材料杂志》发表了核应用材料研究方面的高质量论文，主要是裂变反应堆、聚变反应堆和类似环境，包括带电粒子加速器的辐射区域。无论是基础性质还是应用性质的实验、理论和计算方面的原始研究和评论论文都是受欢迎的。该领域的广度使得读者对材料科学和工程领域的各种工艺和性能感兴趣，例如，涉及原子级工艺、微观结构、热力学、机械性能、物理性能和腐蚀。以下列表描述了期刊范围内的主题。裂变反应堆材料，包括燃料、包壳、堆芯结构、压力容器、冷却剂与材料的相互作用、慢化剂和控制元件；裂变产物行为。整个燃料循环的材料方面。锕系元素及其化合物的材料方面。核废料的性能；废料的固定化。聚变反应堆材料，包括第一道墙、毯子、绝缘体和磁铁。材料中的中子和带电粒子辐射效应，包括缺陷、变形、微观结构、相变和宏观特性。等离子体、离子束、电子束和电磁辐射与材料的相互作用。请注意：手稿必须集中在与核应用有关的材料科学和工程方面。因此，核科学与工程或材料科学与工程中的所有主题不一定都在范围之内。不考虑期刊范围以外的主题，潜在的替代期刊见下表中的括号。超出期刊范围的主题的典型示例包括：（1）核工程和其他不涉及材料的领域，如：粒子输运、截面或同位素比率（辐射物理学和化学；核能年鉴）工艺工程（材料科学与工程A；材料与设计）热工水力学（核工程与设计）同位素分离过程（核仪器和方法B）聚变堆设计与技术（聚变工程与设计）等离子体物理学（物理字母A）（2）不涉及核应用的材料专题，例如：物理特性，包括建模和模拟（材料科学与工程A，材料字母）冶金（合金与化合物杂志；材料科学与工程A）腐蚀（腐蚀科学）焊接和连接（合金和化合物杂志；材料和设计）陶瓷（欧洲陶瓷学会杂志；国际陶瓷）
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