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Journal of Nuclear Materials
ISSN：0022-3115

Journal of Nuclear Materials

J NUCL MATER
学科领域：工程技术
是否预警：不在预警名单内
是否OA：否
录用周期：约2.0个月
新锐分区：工程技术3区
年发文量：564
影响因子：3.2
JCR分区：Q1

基本信息

《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。
0022-3115SCIE/Scopus收录
3.2
点击查看最新影响趋势>
3
新
2026年3月发布
点击查看历史分区趋势    >
大类学科小类学科Top期刊综述期刊
工程技术3区
MATERIALS SCIENCE, MULTIDISCIPLINARY 材料科学：综合
3区
NUCLEAR SCIENCE & TECHNOLOGY 核科学技术
1区
否
N/A
新
WOS期刊SCI分区  2024-2025最新升级版
按JIF指标学科分区收集子录JIF分区JIF排名百分位
学科：MATERIALS SCIENCE, MULTIDISCIPLINARY
SCIE
Q3
237/461
学科：NUCLEAR SCIENCE & TECHNOLOGY
SCIE
Q1
4/41
按JCR指标学科分区收集子录JCR分区JCR排名百分位
学科：MATERIALS SCIENCE, MULTIDISCIPLINARY
SCIE
Q2
117/463
学科：NUCLEAR SCIENCE & TECHNOLOGY
SCIE
Q1
7/41
123
564
点击查看年发文量趋势图>
19%0约2.0个月-工程技术-材料科学：综合
21.9%
点击查看自引率趋势图>
时间预警情况
2026年03月发布的新锐学术版不在预警名单中
2025年03月发布的2025版不在预警名单中
2024年02月发布的2024版不在预警名单中
2023年01月发布的2023版不在预警名单中
2021年12月发布的2021版不在预警名单中
2020年12月发布的2020版不在预警名单中
99.47%12.75%1.25%
CiteScore：6.20
SJR：0.984
SNIP：1.390
学科类别分区排名百分位
大类：Energy
小类：Nuclear Energy and Engineering
Q1
11 / 80
大类：Energy
小类：Nuclear and High Energy Physics
Q1
17 / 91
大类：Energy
小类：General Materials Science
Q2
142 / 460

期刊高被引文献

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

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论文发表 2-4个月录用 7500+文章录用 不成功可退款
新
2026年3月发布
大类学科小类学科Top期刊综述期刊
工程技术3区
MATERIALS SCIENCE, MULTIDISCIPLINARY 材料科学：综合
3区
NUCLEAR SCIENCE & TECHNOLOGY 核科学技术
1区
否
N/A
2025年3月升级版
大类学科小类学科Top期刊综述期刊
工程技术2区
NUCLEAR SCIENCE & TECHNOLOGY 核科学技术
1区
MATERIALS SCIENCE, MULTIDISCIPLINARY 材料科学：综合
2区
否
否
2023年12月旧的升级版
大类学科小类学科Top期刊综述期刊
工程技术2区
NUCLEAR SCIENCE & TECHNOLOGY 核科学技术
1区
MATERIALS SCIENCE, MULTIDISCIPLINARY 材料科学：综合
2区
否
否