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)

《核材料雜志》發(fā)表了核應(yīng)用材料研究方面的高質(zhì)量論文，主要是裂變反應(yīng)堆、聚變反應(yīng)堆和類似環(huán)境，包括帶電粒子加速器的輻射區(qū)域。無(wú)論是基礎(chǔ)性質(zhì)還是應(yīng)用性質(zhì)的實(shí)驗(yàn)、理論和計(jì)算方面的原始研究和評(píng)論論文都是受歡迎的。該領(lǐng)域的廣度使得讀者對(duì)材料科學(xué)和工程領(lǐng)域的各種工藝和性能感興趣，例如，涉及原子級(jí)工藝、微觀結(jié)構(gòu)、熱力學(xué)、機(jī)械性能、物理性能和腐蝕。以下列表描述了期刊范圍內(nèi)的主題。裂變反應(yīng)堆材料，包括燃料、包殼、堆芯結(jié)構(gòu)、壓力容器、冷卻劑與材料的相互作用、慢化劑和控制元件；裂變產(chǎn)物行為。整個(gè)燃料循環(huán)的材料方面。錒系元素及其化合物的材料方面。核廢料的性能；廢料的固定化。聚變反應(yīng)堆材料，包括第一道墻、毯子、絕緣體和磁鐵。材料中的中子和帶電粒子輻射效應(yīng)，包括缺陷、變形、微觀結(jié)構(gòu)、相變和宏觀特性。等離子體、離子束、電子束和電磁輻射與材料的相互作用。請(qǐng)注意：手稿必須集中在與核應(yīng)用有關(guān)的材料科學(xué)和工程方面。因此，核科學(xué)與工程或材料科學(xué)與工程中的所有主題不一定都在范圍之內(nèi)。不考慮期刊范圍以外的主題，潛在的替代期刊見(jiàn)下表中的括號(hào)。超出期刊范圍的主題的典型示例包括：（1）核工程和其他不涉及材料的領(lǐng)域，如：粒子輸運(yùn)、截面或同位素比率（輻射物理學(xué)和化學(xué)；核能年鑒）工藝工程（材料科學(xué)與工程A；材料與設(shè)計(jì)）熱工水力學(xué)（核工程與設(shè)計(jì)）同位素分離過(guò)程（核儀器和方法B）聚變堆設(shè)計(jì)與技術(shù)（聚變工程與設(shè)計(jì)）等離子體物理學(xué)（物理字母A）（2）不涉及核應(yīng)用的材料專題，例如：物理特性，包括建模和模擬（材料科學(xué)與工程A，材料字母）冶金（合金與化合物雜志；材料科學(xué)與工程A）腐蝕（腐蝕科學(xué)）焊接和連接（合金和化合物雜志；材料和設(shè)計(jì)）陶瓷（歐洲陶瓷學(xué)會(huì)雜志；國(guó)際陶瓷）