開放獲取的《核材料與能源》雜志致力于日益增長的核材料在核能生產(chǎn)中的應(yīng)用研究領(lǐng)域。核材料和能源由加興的馬普學(xué)會提供科學(xué)支持。該雜志的重點是在反應(yīng)堆中使用的材料，他們暴露在極端環(huán)境的輻射，溫度和腐蝕條件。主要議題包括:聚變反應(yīng)堆材料，包括等離子體表面組件，如轉(zhuǎn)向器、限流罩和第一壁。聚變等離子體邊界的物質(zhì)侵蝕和輸運及其對入射等離子體條件的影響。等離子體、離子束、電子束和熱流與材料的相互作用，強(qiáng)調(diào)材料的壽命、氚的保留和滲透以及結(jié)構(gòu)的穩(wěn)定性。裂變反應(yīng)堆材料，包括燃料、包層、慢化劑、控制棒、核心結(jié)構(gòu)、壓力容器，但不包括從采礦到核廢料的燃料循環(huán)。聚變和裂變反應(yīng)堆材料在非常高的溫度下承受輻射劑量，遠(yuǎn)遠(yuǎn)超出了目前可用于組件的材料的能力。在正常運行和意外情況下與反應(yīng)堆冷卻劑相互作用時的材料行為。處理在意外情況下燃料、活性粉塵和反應(yīng)產(chǎn)物的釋放，以及堆芯和密封材料的物理和化學(xué)相互作用的材料行為。中子和帶電粒子在材料中的輻射效應(yīng)，包括缺陷、氣體保持和滲透、透射、微觀結(jié)構(gòu)變化、相變和宏觀性質(zhì)。

The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy.Nuclear Materials and Energy is supported scientifically by the Max-Planck-Institut für Plasmaphysik, Garching.The emphasis of the journal is on materials employed in reactors where they are exposed to extreme environments in terms of radiation, temperature and corrosive conditions. The main topics are:Fusion reactor materials, including plasma-facing components, such as divertors, limiters blankets, and the first wall.Material erosion and transport in the boundary of fusion plasmas and its effect on the incident plasma conditions.Interaction of plasmas, ion beams, electron beams and intense heat fluxes with materials with emphasis on lifetime, tritium retention and permeation, and structural stability.Fission reactor materials, including fuels, cladding, moderator, control rods, core structures, pressure vessels, but excluding fuel cycle from mining to nuclear waste.Fusion and fission reactor materials enduring radiation doses at very high temperature far beyond the capability of materials now available for components.Materials behaviour in the interaction with reactor coolants during normal operation and in accidental conditions.Materials behaviour addressing the release of fuel, activated dust and reaction products during accidental conditions, and the physical and chemical interactions of reactor core and containment materials.Neutron and charged particle radiation effects in materials, including defects, gas retention and permeation, transmutations, microstructural changes, phase changes and macroscopic properties.