Progress in Nuclear Energy

Progress in Nuclear Energy

PROG NUCL ENERG
影响因子:3.2
是否综述期刊:
是否预警:不在预警名单内
是否OA:
出版国家/地区:ENGLAND
出版社:Elsevier Ltd
发刊时间:1977
发刊频率:Quarterly
收录数据库:SCIE/Scopus收录
ISSN:0149-1970

期刊介绍

Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.Please note the following:1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
《核能进展》是一本国际评论期刊,涵盖了核科学和工程的所有方面。随着核能的成熟,鼓励刊登关于安全、选址和环境问题的文章,以及与经济和燃料管理相关的文章。然而,基础物理学和工程学仍将是编辑政策的一个重要方面。发表的文章要么是评论性质的,要么是更深入地介绍新材料。它们的目标读者是在核能领域工作的研究人员和技术导向的管理人员。请注意以下几点:1)PNE寻求高质量的研究论文,这些论文的长度是中等到较长的。简短的研究论文应提交给《核能年鉴》杂志。2)PNE保留拒绝仅基于用于产生反应堆设计或解释现有反应堆现象的计算机代码的常规应用的论文的权利。这样的论文,虽然有价值,最好作为实验室报告留下,而核能进展寻求原创性的论文,这是档案性质,在数学和实验核技术领域,包括裂变,聚变(全面物理学、辐射损伤)、安全、材料方面、经济学等。3)评论论文,有时会被邀请,是该杂志特别寻求在这些领域。
年发文量 451
国人发稿量 197.22
国人发文占比 0.44%
自引率 -
平均录取率0
平均审稿周期 平均6.0个月
版面费 US$2580
偏重研究方向 工程技术-核科学技术
期刊官网 http://www.elsevier.com/wps/find/journaldescription.cws_home/478/description#description
投稿链接 https://www.editorialmanager.com/PNUCENE

期刊高被引文献

A review of ground-based robotic systems for the characterization of nuclear environments
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.023
Comparison study of photon attenuation characteristics of Poly vinyl alcohol (PVA) doped with Pb(NO3)2 by MCNP5 code, XCOM and experimental results
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.018
Estimation of gamma radiation shielding qualification of newly developed glasses by using WinXCOM and MCNPX code
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.029
Enhancement of flame retardancy and radiation shielding properties of ethylene vinyl acetate based radiation shielding composites by EB irradiation
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.001
Monte Carlo simulation of Novalis Classic 6 MV accelerator using phase space generation in GATE/Geant4 code
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.004
PWR secondary water chemistry guidelines in Japan - Purpose and technical background
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.027
An exploration of the relationship between nuclear decommissioning projects characteristics and cost performance
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.011
A new approach for nuclear reactor analysis based on complex network theory
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.12.008
Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.02.005
Numerical Investigation of Geometric Size Effect on the Internal Heated Water Pool Natural Convection Behavior
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.12.002
A time dependent Monte Carlo approach for nuclear reactor analysis in a 3-D arbitrary geometry
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.024
Global sensitivity analysis of passive safety systems of FHR by using meta-modeling and sampling methods
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.002
Classification of NPPs transients using change of representation technique: A hybrid of unsupervised MSOM and supervised SVM
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103100
Experimental investigation of fluid mixing inside a rod bundle using laser induced fluorescence
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.012
Utilization of harmony search algorithm to optimize a cascade for separating multicomponent mixtures
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.11.005
Precise determination of soil structure parameters in a X-ray and γ-ray CT combination methodology
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.02.007
Modern financial models of nuclear power plants
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.010
Nonlinear analysis of a reduced-order model with relaxation effects for BWRs
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103089
Potential areas for nuclear power plants siting in Saudi Arabia: GIS-based multi-criteria decision making analysis
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.018
Three-dimensional variational nodal method parallelization for pin resolved neutron transport calculations
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.007
A one-dimensional code of the passive residual heat removal system for the modular high temperature gas-cooled reactor
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.019
Efficient removal of radioactive iodide anions from simulated wastewater by HDTMA-geopolymer
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103112
Effect of cladding on thermal behavior of nuclear fuel element with non-uniform heat generation
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.013
Reliability methods in the design point of free-standing spent fuel racks under seismic conditions
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.021
Impact of integral burnable absorbers on SMART reactor behaviour under normal and anomalous operational conditions
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.005
A CFD-based simulation tool for the stability analysis of natural circulation systems
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103093
Na2Si3O7/BaO composites for the gamma-ray shielding in medical applications: Experimental, MCNP5, and WinXCom studies
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103119
Dissolution behaviour of simulated MOX nuclear fuel pellets in nitric acid medium
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.027
Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.11.004
Electronic structures, mechanical properties and defect formation energies of U3Si5 from density functional theory calculations
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.045
A refined time-delay modeling of the molten salt reactor dynamics
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103102
Development and verification of resonance elastic scattering kernel processing module in nuclear data processing code NECP-Atlas
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.10.006
Containment model library of the Apros process simulation software: an overview of development and validation work
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.031
An analytical approach to bifurcations and stability in simplified mathematical models of nuclear reactors
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.008
Fluid-elastic instability evaluation for reactor vessel internals with structural interaction
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.013
GPU-based implementation of a real-time model for atmospheric dispersion of radionuclides
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.015
A method for predicting the structure of corium pool in lower plenum of reactor vessel
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.005
Experimental study on performance of helium low pressure compressor of HTR-10GT
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.11.008
Scoping evaluation of trace isotopic ratios within the noble metal-phase as indicators of reactor class
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103059
Assessment of the impact of diversification of uranium switching on the risk of its non-energy use
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.014
Experimental study on the natural circulation capability and heat transfer characteristic of liquid lead bismuth eutectic
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.003
Multiphase flow in small-gap geometry: A combined numerical and experimental study
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.12.010
Non-linear, time dependent target accuracy assessment algorithm for multi-physics, high dimensional nuclear reactor calculations
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.023
Non-linear stability analysis of supercritical carbon dioxide flow in inclined heated channel
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.103048
Generalized sensitivity analysis of responses to nuclear data in 2-D/1-D transport code KYADJ
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.01.018
End point determination for spent nuclear fuel drying operations
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.04.004
Numerical analysis of dynamic heating modulation during rapid cooling of fuel layer in an indirect-drive cryogenic target
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.02.004
Physics study of liquid hydrogen moderator of CMRR reactor cold neutron source
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.09.002
Neutronic analysis of a VVER-1000 reactor with nanofluid as coolant through zeroth order average current nodal expansion method
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2019.03.016
Laboratory-scale quartz crucible melter tests for vitrifying a high-MoO3 raffinate waste simulant
来源期刊:Progress in Nuclear EnergyDOI:10.1016/J.PNUCENE.2018.08.022

质量指标占比

研究类文章占比 OA被引用占比 撤稿占比 出版后修正文章占比
93.35%9.57%-0.6%

相关指数

影响因子
影响因子
年发文量
自引率
Cite Score

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