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.Topics covered by JNMFission 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; materials aspects of the 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 relevant to nuclear systems.
《核材料杂志》发表高质量的核应用材料研究论文，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领域。无论是原创性的研究和评论论文涵盖实验，理论和计算方面的基础或应用性质是受欢迎的。该领域的广度是这样的，在材料科学和工程领域的广泛过程和性质是读者感兴趣的，跨越原子尺度的过程，微观结构，热力学，机械性能，物理性能和腐蚀。例如，《核废料管理手册》所涵盖的主题：核反应堆材料，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、慢化剂和控制部件、裂变产物的行为、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;（c）核反应堆材料，包括第一壁、包层、绝缘体和磁体;（d）材料中的中子和带电粒子辐射效应，包括缺陷、嬗变、微观结构、相变和宏观特性;（e）等离子体、离子束、电子束和电磁辐射与核系统相关材料的相互作用。
Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2018.10.044
In situ SEM-EBSD analysis of plastic deformation mechanisms in neutron-irradiated austenitic steel
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.01.034
Ion-irradiation hardening and microstructural evolution in F82H and ferritic alloys
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2018.12.047
ABAQUS analysis of the SiC cladding fuel rod behavior under PWR normal operation conditions
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2018.12.017
Adsorption and immobilization of radioactive ionic-corrosion-products using magnetic hydroxyapatite and cold-sintering for nuclear waste management applications
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2018.11.026
Corrosion resistance and microstructural stability of austenitic Fe–Cr–Al–Ni model alloys exposed to oxygen-containing molten lead
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.06.043
Tribochemistry of inconel 617 during sliding contact at 950 °C under helium environment for nuclear reactors
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.04.032
Effect of hot isostatic pressing on microstructure and mechanical properties of CLAM steel produced by selective laser melting
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2018.12.028
Texture evolution of cold-rolled Zr-1Sn-0.3Nb-0.3Fe-0.1Cr alloy during annealing
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.06.038
Fission recoil-induced microstructural evolution of the fuel-cladding interface [FCI] in high burnup BWR fuel
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.04.044
Emulation of fast reactor irradiated T91 using dual ion beam irradiation
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/j.jnucmat.2019.151831
The study of irradiation-induced failure behavior for the TRISO-coated fuel particle in HTGR
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.01.029
Phase analysis of uranium oxides after reaction with stainless steel components and ZrO2 at high temperature by XRD, XAFS, and SEM/EDX
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.03.055
General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.04.023
One-step direct synthesis of mesoporous AMP/SBA-15 using PMA as acid media and its use in cesium ion removal
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/j.jnucmat.2019.151809
On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/j.jnucmat.2019.151863
Xenon ion irradiation induced hardening in inconel 617 containing experiment and numerical calculation
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.07.032
BaO-Fe2O3-P2O5 glasses: Understanding the thermal stability
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.01.046
Contribution to the understanding of brittle fracture conditions of zirconium alloy fuel cladding tubes during LOCA transient
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/j.jnucmat.2019.151815
Thermal conductivity estimation of fully ceramic microencapsulated pellets with ZrO2 as simulated particles
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.07.027
Crystallographic and compositional analysis of impurity phase U2MoSi2C in UMo alloys
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.03.044
Ab initio molecular dynamics simulation of the radiation damage effects of GaAs/AlGaAs superlattice
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.01.030
Variance-based sensitivity analysis applied to hydrogen migration and redistribution model in Bison. Part I: Simulation of historical experiments
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.06.035
Magnetoelectropolishing treatment for improving the oxidation resistance of 316L stainless steel in pressurized water reactor primary water
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.03.028
Relationships between experimental signatures and processing history for a variety of PuO2 materials
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.04.036
Bulk moduli and high pressure crystal structure of U3Si2
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.06.006
Void evolution in tungsten and tungsten-5wt.% tantalum under in-situ proton irradiation at 800 and 1000 °C
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.07.030
Recrystallization kinetics of cold-rolled U-10 wt% Mo
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2018.10.046
Microstructures of ZrC coated kernels for fuel of Pu-burner high temperature gas-cooled reactor in Japan
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.05.012
HT9 swelling in high burnup fast reactor fuel pin components
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.03.053
Study on vacancy-type defects in SIMP steel induced by separate and sequential H and He ion implantation
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.04.012
An estimation of neutron-induced production of gases with propagation of uncertainties in nuclear data for structural materials of fission and fusion reactors
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.03.040
Ultra-high temperature creep rupture and transient burst strength of ODS steel claddings
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.01.052
Effect of ion and neutron irradiation on oxide of PHWR fuel tube material
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2018.11.018
Investigation of corrosion-erosion behavior of stainless steel considering SS-B4C melt
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2018.12.026
Ballistic-damage-induced size changes in equilibrium and under-pressurized Xe precipitates in amorphous silica
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.03.051
200 MeV proton irradiation of the oxide-dispersion-strengthened copper alloy (GlidCop-Al15)
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.01.026
Long-term stability of the microstructure of austenitic ODS steel rods produced with a carbon-containing process control agent
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.05.060
Electrochemical investigation of in-service thermal aging in two CF8M cast stainless steels
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.04.001
Study of lithium germanate additions to advanced ceramic breeder pebbles
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.03.010
Study of the physical and nuclear properties of liquid PbBiCd alloy coolant in nuclear fast reactor
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.05.006
The effect of nitride formation on the oxidation kinetics of Zry-4 fuel cladding under steam-air atmospheres at 1273–1573 K
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.07.010
Development of an advanced core-shell ceramic pebble with Li4TiO4 pure phase core and Li2TiO3 nanostructured shell by a physical coating method
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.04.029
Thermal analysis of projected molten salt compositions during FFTF and EBR-II used nuclear fuel processing
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.04.016
Use of Einstein-Debye method in the analytical and semi empirical analysis of isobaric heat capacity and thermal conductivity of nuclear materials
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/j.jnucmat.2019.151827
Leaching of spent nuclear fuels in aerated conditions: Influences of sample preparation on radionuclide release patterns
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/j.jnucmat.2019.151789
Micro-compression testing of gold ion irradiated zirconolite glass-ceramics as nuclear waste forms
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/j.jnucmat.2019.151813
The distribution and forming of tritium in two types of China reduced activation ferritic-martensitic steels
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.06.003
Nondestructive evaluation of plastic damage in a RAFM steel considering the influence of loading history
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.05.048
Fuel clad chemical interaction of U-Mo fast reactor fuel
来源期刊：Journal of Nuclear MaterialsDOI：10.1016/J.JNUCMAT.2019.01.011
