研飞ivySCI (青藤学术）

Progress in Nuclear Energy

短名	Prog. Nucl. Energy
Journal Impact	3.27
国际分区	NUCLEAR SCIENCE & TECHNOLOGY(Q1)
期刊索引	SCI Q1中科院 3 区

ISSN	0149-1970, 1878-4224
h-index	82
国内分区	工程技术(3区)工程技术核科学技术(2区)

PROGRESS IN NUCLEAR ENERGY 是一本涵盖核科学与工程各个方面的国际评论期刊。随着核电的成熟，鼓励发表关于安全、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。它们面向在核能领域工作的研究人员和技术型管理人员。请注意以下几点：1) PNE 寻求中长篇的高质量研究论文。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生产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。这些论文虽然有价值，但最好作为实验室报告保留，而《核能进展》则寻求具有原创性的论文，这些论文本质上是档案性的，在数学和实验核技术领域，包括裂变、聚变（全面物理、辐射损伤）、安全、材料方面、经济学等。3) 偶尔会被邀请的评论论文在这些领域是期刊特别需要的。

期刊主页投稿网址

涉及主题	物理工程类量子力学计算机科学核物理学材料科学核工程化学热力学数学环境科学复合材料生物有机化学机械机械工程冶金中子核化学地理
出版信息	出版商: Elsevier Ltd，出版周期: Quarterly，期刊类型: journal
基本数据	创刊年份: 1994，原创研究文献占比: 95.44%，自引率:12.10%， Gold OA占比: 12.68%
平均审稿周期	网友分享经验：平均6.0个月
平均录用比例	网友分享经验：容易

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Reaction of uranium with poly-hydroxy-aromatic groups on particles through mono- and multi-dentate surface complexes on the basis of pH and redox potential: A modelling approach

2024-12-1

Load-Follow Operation in LEU+ loaded very-low soluble boron APR1400

2024-12-1

Investigation of the dynamics of transverse oscillations of a vertical rod under gravity, friction, and thermal expansion

2024-12-1

Thermo-neutronic integrated coupling effects on nuclear reactor core calculations

2024-12-1

Adaptive center constraint for joint release rate estimation and model correction: Multi-scenario validation against wind tunnel experiments

2024-12-1

Establishing machine-learning approach for predicting outer-diametral strains in ferritic/martensitic (F/M) steel tubes during in-reactor neutron-irradiation creep experiments

2024-12-1

Experiments on fluid-structure interaction dynamic response of multiple free-standing spent fuel storage baskets

2024-12-1

Management of the SBLOCA sequences with HPIS failure in VVER-1000/V320 reactors; comparison with Westinghouse PWR strategies

2024-12-1

Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids

2024-12-1

Implementation of one-phonon correction method to calculate inelastic scattering law data in nuclear data processing code NECP-Atlas

2024-12-1

An optimal plate-fin heat exchanger design using opposition-based Orthogonal Learning Kho-Kho Optimization algorithm

2024-12-1

An ethical analysis of the impact of reversibility and retrievability provisions on well-being

2024-12-1

Stochastic implications of Monte Carlo cross section generation on utilization in advanced nodal simulators

2024-11-1

A review of supercritical fluid flow instability

2024-11-1

A comprehensive dosimetry analysis of barakah nuclear power plant: Integrating gaseous and liquid radionuclide dispersion across multiple units

2024-11-1

Decay heat generation of VVER-1200 reactor spent fuel during the pool period

2024-11-1

Development of 16N monitoring system for real-time detection of small leakage in reactor coolant systems

2024-11-1

Effect of cationic substitution in the oxidative decontamination processes of nickel chromium ferrites

2024-11-1

Parameters of exothermic processes in nitric acid solutions containing reducing agents

2024-11-1

Influence of temperature and dry density coupled effects on HTO, 36Cl, 85Sr and 133Ba diffusion through compacted bentonite

2024-11-1

A multi-objective decision-making method for small modular reactor operation based on A3C algorithm

2024-11-1

Editorial Board

2024-11-1

Thaumasite formation in cementitious composites used in underground repositories – Conditions and impact on composite's properties: A review

2024-11-1

Conceptual design and optimization of heat rejection system for nuclear reactor coupled with supercritical carbon dioxide Brayton cycle used on Mars

2024-11-1

Assessing the benefit of thorium fuel in a once through molten salt reactor

2024-11-1

Research on dynamicflow rate self-sensing in control valves

2024-11-1

Study on non-uniform circumferential temperature distribution of annular fuel in the tight lattice configuration of a lead-bismuth cooled fast reactor

2024-11-1

Analysis on thermal hydraulic characteristics for PHENIX natural circulation system using “1D system code + 3D CFD” simulation method

2024-11-1

Review of researches on flow blockage accident in liquid-metal-cooled reactor

2024-11-1

A novel correlation for bubble size variation in the swarm region under pool scrubbing conditions

2024-11-1

Influence of solid electrolyte material selection on electromotive force characteristics of oxygen sensor for lead-cooled fast reactor

2024-11-1

A comprehensive investigation on lanthanum ions doped borate-tellurite-germinate glass for radiation shielding and optical application

2024-11-1

The instability marsh phenomenon and marginal stability boundary distortion of density wave oscillation in parallel channels

2024-11-1

Application of Lie symmetry to find an analytical solution for reactor point kinetics equation with prompt jump approximation and power feedback

2024-11-1

Numerical analysis of duct wall failure in a prototype FAIDUS design-based generation IV SFR fuel subassembly under flow blockage accident

2024-11-1

Stochastic differential equations for non-analog Monte Carlo model of point kinetics equations

2024-11-1

An enhanced mathematical model for evaluating grid-to-rod fretting wear under complex boundary

2024-11-1

Probabilistic typhoon hazard and sensitivity analysis for nuclear power plant sites in Korea using logic tree

2024-11-1

Research progress on LBE corrosion-resistant coatings: A review

2024-11-1

Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model

2024-11-1

Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement

2024-11-1

Gamma-ray attenuation properties of some heavy metal ferroalloys for potential applications

2024-11-1

Extended development of the Monte Carlo code MCNP for effective delayed neutron fraction calculation in molten salt reactors

2024-11-1

Experimental validation of the 3-D neutron kinetics algorithm of RAPID using the JSI TRIGA Mark-II reactor

2024-11-1

A hybrid model based on complementary ensemble empirical mode decomposition, sample entropy and long short-term memory neural network for the prediction of time series signals in NPPs

2024-11-1

Experimental testing and process simulation of flowsheets for the co-separation of uranium and plutonium using acetohydroxamic acid as a complexing agent

2024-11-1

Research on condensation induced water hammer with one-dimensional simulation code

2024-11-1

Development of higher order deterministic approaches of forward and inverse uncertainty quantification for nonlinear engineering systems

2024-11-1

Design and optimization of space nuclear power system with sCO2 Brayton cycle on Mars

2024-11-1

Concurrent fault diagnosis of small pressurized water reactors based on long-short term memory networks

2024-11-1

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Progress in Nuclear Energy

期刊引文格式

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最新文章

Reaction of uranium with poly-hydroxy-aromatic groups on particles through mono- and multi-dentate surface complexes on the basis of pH and redox potential: A modelling approach

Load-Follow Operation in LEU+ loaded very-low soluble boron APR1400

Investigation of the dynamics of transverse oscillations of a vertical rod under gravity, friction, and thermal expansion

Thermo-neutronic integrated coupling effects on nuclear reactor core calculations

Adaptive center constraint for joint release rate estimation and model correction: Multi-scenario validation against wind tunnel experiments

Establishing machine-learning approach for predicting outer-diametral strains in ferritic/martensitic (F/M) steel tubes during in-reactor neutron-irradiation creep experiments

Experiments on fluid-structure interaction dynamic response of multiple free-standing spent fuel storage baskets

Management of the SBLOCA sequences with HPIS failure in VVER-1000/V320 reactors; comparison with Westinghouse PWR strategies

Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids

Implementation of one-phonon correction method to calculate inelastic scattering law data in nuclear data processing code NECP-Atlas

An optimal plate-fin heat exchanger design using opposition-based Orthogonal Learning Kho-Kho Optimization algorithm

An ethical analysis of the impact of reversibility and retrievability provisions on well-being

Stochastic implications of Monte Carlo cross section generation on utilization in advanced nodal simulators

A review of supercritical fluid flow instability

A comprehensive dosimetry analysis of barakah nuclear power plant: Integrating gaseous and liquid radionuclide dispersion across multiple units

Decay heat generation of VVER-1200 reactor spent fuel during the pool period

Development of 16N monitoring system for real-time detection of small leakage in reactor coolant systems

Effect of cationic substitution in the oxidative decontamination processes of nickel chromium ferrites

Parameters of exothermic processes in nitric acid solutions containing reducing agents

Influence of temperature and dry density coupled effects on HTO, 36Cl, 85Sr and 133Ba diffusion through compacted bentonite

A multi-objective decision-making method for small modular reactor operation based on A3C algorithm

Editorial Board

Thaumasite formation in cementitious composites used in underground repositories – Conditions and impact on composite's properties: A review

Conceptual design and optimization of heat rejection system for nuclear reactor coupled with supercritical carbon dioxide Brayton cycle used on Mars

Assessing the benefit of thorium fuel in a once through molten salt reactor

Research on dynamicflow rate self-sensing in control valves

Study on non-uniform circumferential temperature distribution of annular fuel in the tight lattice configuration of a lead-bismuth cooled fast reactor

Analysis on thermal hydraulic characteristics for PHENIX natural circulation system using “1D system code + 3D CFD” simulation method

Review of researches on flow blockage accident in liquid-metal-cooled reactor

A novel correlation for bubble size variation in the swarm region under pool scrubbing conditions

Influence of solid electrolyte material selection on electromotive force characteristics of oxygen sensor for lead-cooled fast reactor

A comprehensive investigation on lanthanum ions doped borate-tellurite-germinate glass for radiation shielding and optical application

The instability marsh phenomenon and marginal stability boundary distortion of density wave oscillation in parallel channels

Application of Lie symmetry to find an analytical solution for reactor point kinetics equation with prompt jump approximation and power feedback

Numerical analysis of duct wall failure in a prototype FAIDUS design-based generation IV SFR fuel subassembly under flow blockage accident

Stochastic differential equations for non-analog Monte Carlo model of point kinetics equations

An enhanced mathematical model for evaluating grid-to-rod fretting wear under complex boundary

Probabilistic typhoon hazard and sensitivity analysis for nuclear power plant sites in Korea using logic tree

Research progress on LBE corrosion-resistant coatings: A review

Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model

Significant improvement in the gamma ray attenuation properties of bismuth tellurite glass using molybdenum oxide reinforcement

Gamma-ray attenuation properties of some heavy metal ferroalloys for potential applications

Extended development of the Monte Carlo code MCNP for effective delayed neutron fraction calculation in molten salt reactors

Experimental validation of the 3-D neutron kinetics algorithm of RAPID using the JSI TRIGA Mark-II reactor

A hybrid model based on complementary ensemble empirical mode decomposition, sample entropy and long short-term memory neural network for the prediction of time series signals in NPPs

Experimental testing and process simulation of flowsheets for the co-separation of uranium and plutonium using acetohydroxamic acid as a complexing agent

Research on condensation induced water hammer with one-dimensional simulation code

Development of higher order deterministic approaches of forward and inverse uncertainty quantification for nonlinear engineering systems

Design and optimization of space nuclear power system with sCO2 Brayton cycle on Mars

Concurrent fault diagnosis of small pressurized water reactors based on long-short term memory networks

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