Science and Technology of Nuclear Installations
| 短名 | Sci. Technol. Nucl. Install. |
| Journal Impact | 1.07 |
| 国际分区 | NUCLEAR SCIENCE & TECHNOLOGY(Q3) |
| 期刊索引 | SCI Q3中科院 4 区 |
| ISSN | 1687-6075, 1687-6083 |
| h-index | 29 |
| 国内分区 | 工程技术(4区)工程技术核科学技术(4区) |
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 是一本国际科学期刊，旨在提供有关核工业相关问题的知识并促进核科学和技术领域的发展。与该杂志的建立和发展相关的努力预计将为世界核技术的复兴提供支持，特别是在那些尚未制定核计划的国家。
期刊主页投稿网址| 涉及主题 | 工程类物理量子力学核物理学热力学计算机科学核工程材料科学化学数学机械工程机械复合材料生物有机化学地理环境科学地质学程序设计语言航空航天工程操作系统传热废物管理统计 |
| 出版信息 | 出版商: Hindawi Limited，出版周期: ，期刊类型: journal |
| 基本数据 | 创刊年份: 2008，原创研究文献占比: 98.15%，自引率:10.00%， Gold OA占比: 98.52% |
| 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
Assessment of Radiation Dose Associated with the Atmospheric Release of 41Ar from the TRIGA Mark-II Research Reactor in Bangladesh
2024-5-30
Design Change and Operational Consideration of the HVAC System during Nuclear Power Plant Decommissioning
2024-4-30
Accuracy Evaluation of Monte Carlo Simulation Results Using ENDF/B-VIII.0 and JENDL-5 Libraries for 10 MWth Micro Heat Pipe-Cooled Reactor
2024-4-8
Effect of Photomultiplier Tube Voltage on the Performance of Sealed NaI (Tl) Scintillator Detectors
2024-4-3
Overview on Radiation Damage Effects and Protection Techniques in Microelectronic Devices
2024-3-30
An Association Rule Mining-Based Method for Revealing the Impact of Operational Sequence on Nuclear Power Plants Operating
2024-3-25
Quantitative Assessment of Gaseous Effluents during Routine Operation: A Comparative Study of Planned Nuclear Power Plants at Lubiatowo-Kopalino and Pątnów Sites in Poland
2024-3-12
Time-Series Forecasting of a Typical PWR Undergoing Large Break LOCA
2024-3-8
Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site
2024-2-13
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process
2024-1-30
Nuclear Waste Management: A Mini Review on Waste Package Characterization Approaches
2024-1-1
Proposal and Validation of a Diagnosis Method of Fuel Failures in Pressurized Water Reactor Nuclear Power Plants
2024-1-1
Count Loss Evaluation for Accuracy Enhancement of a FPGA‐Based Gamma Spectroscopy
2024-1-1
Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library
2024-1-1
Exponential Response Matrix Spectral Nodal Method for the Discrete Ordinates Neutral Particle Transport Model
2024-1-1
Assessment of Computational Technicalities for 2D/1D Coupling Method and Its Comparison with 3D MOC
2024-1-1
Cenosphere‐Based <sup>177</sup>Lu‐Aluminosilicate Microspheres as a Theranostic <i>β</i>‐Emitter for Selective Internal Radiation Therapy of Hepatic Tumors
2024-1-1
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model
2023-12-18
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger
2023-12-14
Shaking Table Testing of a Scaled Nuclear Power Plant Structure with Base Isolation
2023-10-31
Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland
2023-10-21
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints
2023-8-9
A Digital Controller for Reactivity Monitoring and Power Control
2023-8-7
A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem
2023-7-10
Design of a Nanosecond Voltage Comparator with PECL Logic for a Photon-Counting Radiation Imaging System Application
2023-7-8
Methods for Predicting the Minimum Temperature of the Outage Loop and the Maximum Power Caused by the Low-Temperature Coolant
2023-6-19
Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment
2023-6-7
A New Experimental Method for the Nonlinear Modal Parameter Identification of a Pressurized Water Reactor Fuel Assembly
2023-5-25
Analysis of the Effect of Applied Load on Crevice Corrosion Behavior
2023-5-3
Acceptable Level of Acceptance and the Affecting Factors: What Is the Acceptable Public Acceptance of Building a Nuclear Power Plant
2023-3-11
Modelling and Validation of CANDU Shim Operation Using Coupled TRACE/PARCS with Regulating System Response
2023-3-8
Steam-Jet Evaluation for Predicting Leakage Behavior and Interpretation of Experimental Verification
2023-3-7
Assessing the Impact of Common Cause Failures on Site Risk within Level 1 Multi-Unit PSA
2023-3-3
Prediction of Automatic Scram during Abnormal Conditions of Nuclear Power Plants Based on Long Short-Term Memory (LSTM) and Dropout
2023-3-3
Simulations of Core Damage Progression for TMI-2 Severe Accident Using CINEMA Computer Code
2023-2-27
Effectiveness of Serpentine Concrete as Shielding Material for Neutron Source Facility Using Monte Carlo Code
2023-2-18
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities
2023-1-12
Application of EDG AOT Extension Based on the Risk-Informed Method in NPPs
2023-1-5
High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment
2022-12-16
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material
2022-12-15
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework
2022-11-29
Nuclear Power Sustainability Path for China from the Perspective of Operations
2022-11-28
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method
2022-11-17
Development of an MPS Code for Corium Behavior Analysis: 3D Alloy Melting
2022-11-3
Feasibility Study on the Initial Kartini Reactor Core Using Plate Type Fuel Elements
2022-10-14
The Study of Dosimetric Characteristics of the XHA600D Medical Linear Accelerator Based on a Monte Carlo Code
2022-9-29
Research on Radionuclide Diffusion Mechanism in the Ocean and Emergency Response under Oceanic Radioactive Events
2022-9-24
Research and Analysis on Assembly Methodology for the Fusion Blanket System
2022-9-21
Science and Technology of Nuclear Installations
2022-9-19
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