Journal of Nuclear Science and Technology
短名 | J. Nucl. Sci. Technol. |
Journal Impact | 1.69 |
国际分区 | NUCLEAR SCIENCE & TECHNOLOGY(Q2) |
期刊索引 | SCI Q3中科院 4 区 |
ISSN | 0022-3131, 1881-1248 |
h-index | 73 |
国内分区 | 工程技术(4区)工程技术核科学技术(3区) |
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY (JNST) 发表国际同行评审论文,有助于交流核科学技术领域的研究、思想和发展,为世界的和平与可持续发展做出贡献。JNST 的广泛范围涵盖其学科类别内的广泛主题,包括但不限于:与核电利用相关的一般问题:哲学和伦理、正义和政策、国际关系、经济和社会学方面、环境方面、教育、文件和数据库、核不扩散、辐射保障、加速器和射束技术:核物理、工程核反应、核数据测量和评估、核数据的整体验证/验证和基准、辐射行为和屏蔽、辐射物理、辐射探测和测量, 加速器和光束技术, 同步辐射, MEDI CAL REACTOR AND ACCELERATOR, 中子源, NEUTRON TECHNOLOGY -机器系统:反应堆仪表和控制系统,人为因素,控制室和操作界面设计,远程控制,机器人,图像处理热工水力学:热工水力实验与分析,热工水力设计,单/两/多相流的热工水力学,流体交互现象、测量技术等。
期刊主页投稿网址涉及主题 | 物理化学工程类量子力学核物理学材料科学核工程有机化学放射化学计算机科学冶金热力学复合材料数学生物环境科学核化学光学中子 |
出版信息 | 出版商: Taylor and Francis Ltd.,出版周期: Monthly,期刊类型: journal |
基本数据 | 创刊年份: 1964,原创研究文献占比: 100.00%,自引率:40.00%, Gold OA占比: 14.60% |
平均审稿周期 | 网友分享经验:偏慢,4-8周 |
平均录用比例 | 网友分享经验:容易 |
期刊引文格式
这些示例是对学术期刊文章的引用,以及它们应该如何出现在您的参考文献中。
并非所有期刊都按卷和期组织其已发表的文章,因此这些字段是可选的。有些电子期刊不提供页面范围,而是列出文章标识符。在这种情况下,使用文章标识符而不是页面范围是安全的。
只有1位作者的期刊
有2位作者的期刊
有3位作者的期刊
有5位以上作者的期刊
书籍引用格式
以下是创作和编辑的书籍的参考文献的示例。
学位论文引用格式
网页引用格式
这些示例是对网页的引用,以及它们应该如何出现在您的参考文献中。
专利引用格式
最新文章
Extraction behaviors of minor actinides and rare earth elements with NTA amide extractants
2024-9-11
Design and development of the machine protection system for HIAF
2024-8-29
Optimization of BP neural network for fault parameter prediction in nuclear power plants utilizing the firefly algorithm
2024-8-27
Towards safe, efficient long-reach manipulation in nuclear decommissioning: a case study on fuel debris retrieval at Fukushima Daiichi
2024-8-16
Application of methods for the chemical and radiometric monitoring of liquid radioactive waste processing
2024-8-13
Automating execution of surveillance procedures for NPP main control rooms
2024-8-9
Chemical interaction of CsOH vapor with UO <sub>2</sub> and Fe-Zr melt
2024-8-8
Ion exchange selectivity for protons by sodium ion-form crystalline silicotitanate
2024-7-30
Using Lorentz force flowmeter to measure the narrow channel flow that mimics lead-bismuth cooled reactors
2024-7-22
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector
2024-7-19
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique
2024-7-17
A novel strategy for iodine removal from nuclear reactor accidental gases: efficient adsorption of CH <sub>3</sub> I on the moderately hydrophobic modified silver-loaded zeolite under high temperature and humidity conditions
2024-7-15
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages
2024-7-12
Feedback on neutron capture cross-section of <sup>234</sup> U from analysis of measured inventories of UO <sub>2</sub> fuel irradiated in TMI unit 1
2024-7-12
Fundamental study on hydrogen production by radiation related to material properties of boron-containing geopolymers with reduced water content
2024-7-12
Correction
2024-7-7
Implementation of surface crack detection method for nuclear fuel pellets by weakly supervised learning
2024-7-7
Redistribution of Nb and other alloying elements in Nb-doped Zr alloy under high dose ion irradiation
2024-6-27
Dynamic performance analysis of a new low-temperature nuclear heating system with APROS
2024-6-24
Evaluation of shielding performance and light emission characteristics of luminescent radiation shields using Gd <sub>2</sub> O <sub>2</sub> S
2024-6-16
Flux distribution tallies using proper orthogonal decomposition in Monte Carlo calculations
2024-6-6
Sorption of Cs <sup>+</sup> and Eu <sup>3+</sup> onto coherent and melange-type pre-neogene sedimentary rocks
2024-6-1
Bayesian approach to energy dependence of fission product yields of <sup>235</sup> U by data augmentation
2024-5-30
Arsenazo III-spectrophotometry for the determination of thorium content
2024-5-29
Development of a simple calculation method for the conductance of rarefied gas flow in cylindrical pipe applicable to divertor exhaust investigation of nuclear fusion reactor
2024-5-28
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction
2024-5-20
Evaluation of influence of wall roughness on wall turbulence using LES simulation with MSGD model for liquid Li flow inside two-staged contraction nozzle
2024-5-7
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi Nuclear Power Plant Unit 2
2024-5-4
Limited linear source approximation with Edge Detection for Convergence Stability of Method of Characteristics
2024-5-3
Deep Learning-based Bubble Detection with swin transformer
2024-4-28
Measurements of neutron capture cross-sections for nuclides of interest in decommissioning: <sup>45</sup> Sc, <sup>63</sup> Cu, <sup>64</sup> Zn, <sup>109</sup> Ag and <sup>113</sup> In
2024-4-25
Corrosion behavior of hastelloy alloys and stainless steel in the molten chloride salt NaCl-CaCl <sub>2</sub> -CeCl <sub>3</sub>
2024-4-8
Measurement of the thermal neutron capture-cross section of <sup>191</sup> Ir at ANNRI MLF J-PARC
2024-4-2
Experimental techniques for investigating thermal transport in nuclear materials
2024-3-28
Heat of transport for hydrogen and hydrides in Zircaloy
2024-3-22
Application of new axial power distribution synthesis method using in-core detector signal in digital core protection system
2024-3-22
Molecular dynamics simulation study of the effect of Ce <sup>4+</sup> incorporation at Zr site on the threshold displacement energy in Y <sub>4</sub> Zr <sub>3</sub> O <sub>12</sub> material
2024-3-4
Bayesian statistical model for cladding high-temperature burst under loss-of-coolant accident conditions
2024-2-29
Experimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for small lead-based reactor
2024-2-27
Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India
2024-2-23
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks
2024-2-22
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment
2024-2-19
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment
2024-2-19
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of nickel-base Alloy 82 weld metal
2024-2-19
A study on the fracture pattern change of high-burnup fuel cladding failed by pellet-cladding mechanical interaction failure under reactivity-initiated accident conditions
2024-2-15
Design of moderator and collimator based on compact D-T neutron source for neutron imaging
2024-2-12
Activation level of the concrete building and pressure vessel in JAEA-Tokai tandem accelerator
2024-2-12
Numerical study of turbulent heat transfer of annular fuel assembly in a sodium-cooled fast reactor by a SST <i> k-ω-k <sub>θ</sub> -ε <sub>θ</sub> </i> model
2024-2-5
EXPERIENCES from the CUTTING of METALLIC BLOCKS from SIMULANT FUKUSHIMA DAIICHI FUEL DEBRIS
2024-2-5
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment Model
2024-2-1
帮你贴心管理全部的文献
研飞ivySCI,高效的论文管理
投稿经验分享
分享我的经验,帮你走得更远