Works matching DE "PRESSURIZED water reactors"
Results: 621
Virtual sensing-enabled digital twin framework for real-time monitoring of nuclear systems leveraging deep neural operators.
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- NPJ Materials Degradation, 2025, v. 9, n. 1, p. 1, doi. 10.1038/s41529-025-00557-y
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Analysis of the Cobalt-60 Production in the AP1000-Like Pressurized Water Reactor Using SERPENT2.
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- Arabian Journal for Science & Engineering (Springer Science & Business Media B.V. ), 2025, v. 50, n. 5, p. 3203, doi. 10.1007/s13369-023-08646-3
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压水堆控制棒导向筒与堆芯上板间隙 对控制棒落棒时间的影响研究.
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- Nuclear Safety, 2025, v. 24, n. 1, p. 53
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Influence of composition and temperature on oxide film formation for Fe-Cr-Ni alloys in simulated PWR primary water.
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- Journal of Nuclear Science & Technology, 2025, v. 62, n. 3, p. 250, doi. 10.1080/00223131.2024.2417784
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Simulations and modeling of radioactivity buildup due to corrosion products in ion exchanger and filters of a typical PWR.
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- Radiochemistry, 2009, v. 51, n. 1, p. 47, doi. 10.1134/S1066362209010111
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Analysis of reactivity control coefficients and the stability of an AP1000 reactor assembly fueled with (Th-<sup>233</sup>U)O<sub>2</sub> using DRAGON code.
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- Annals of the University of Craiova, Physics, 2022, v. 32, p. 88
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Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels.
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- Mathematics (2227-7390), 2022, v. 10, n. 10, p. 1779, doi. 10.3390/math10101779
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Neutronic and Thermalhydraulic Evaluation of Annular Fuel in PWR with Three Different Nanofluids.
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- Sakarya University Journal of Science (SAUJS) / Sakarya Üniversitesi Fen Bilimleri Enstitüsü Dergisi, 2022, v. 26, n. 4, p. 643, doi. 10.16984/saufenbilder.1080287
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PWR effect on crack initiation under equi-biaxial loading development of the experiment.
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- Mechanics & Industry, 2019, v. 20, n. 6, p. 1, doi. 10.1051/meca/2019060
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Effects of Advanced Amines on Magnetite Deposition of Steam Generator Tubes in Secondary System.
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- Coatings (2079-6412), 2021, v. 11, n. 5, p. 514, doi. 10.3390/coatings11050514
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Corrosion Behavior and Surface Treatment of Cladding Materials Used in High-Temperature Lead-Bismuth Eutectic Alloy: A Review.
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- Coatings (2079-6412), 2021, v. 11, n. 3, p. 364, doi. 10.3390/coatings11030364
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Magnetite-Accelerated Corrosion of SA508 Tubesheet Material and Its Effect on Steam Generator Tube Denting.
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- Coatings (2079-6412), 2019, v. 9, n. 9, p. 575, doi. 10.3390/coatings9090575
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A graph theory approach to predicting functional failure propagation during conceptual systems design.
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- Systems Engineering, 2021, v. 24, n. 2, p. 100, doi. 10.1002/sys.21569
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Gas Cooled Graphite Moderated and Pressurized Water Reactor the Optimal Choice for Nuclear Power Plants Based on a New Group Decision-Making Technique.
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- Symmetry (20738994), 2022, v. 14, n. 12, p. 2621, doi. 10.3390/sym14122621
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A Method to Determine Core Design Problems and a Corresponding Solution Strategy.
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- Symmetry (20738994), 2019, v. 11, n. 4, p. 576, doi. 10.3390/sym11040576
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Creep deformation and permeability evolution of the K<sub>1</sub>/J<sub>2</sub> paleoweathered rocks in the bending zone under triaxial unloading–loading confining pressure.
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- Environmental Earth Sciences, 2023, v. 82, n. 7, p. 1, doi. 10.1007/s12665-023-10867-6
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Energy and Exergy Analyses of a PWR-Type Nuclear Power Plant Coupled with an ME-TVC-MED Desalination System.
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- Sustainability (2071-1050), 2023, v. 15, n. 10, p. 8358, doi. 10.3390/su15108358
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Detection of Numerical Power Shift Anomalies in Burnup Modeling of a PWR Reactor.
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- Sustainability (2071-1050), 2023, v. 15, n. 4, p. 3373, doi. 10.3390/su15043373
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Techno-Economic Assessment of Fuel Cycle Facility of System Integrated Modular Advanced Reactor (SMART).
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- Sustainability (2071-1050), 2021, v. 13, n. 21, p. 11815, doi. 10.3390/su132111815
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Analysis of Release Model Effect in the Transport of Fission Products Simulating the FPT3 Test Using MELCOR 2.1 and MELCOR 2.2.
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- Sustainability (2071-1050), 2021, v. 13, n. 14, p. 7964, doi. 10.3390/su13147964
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Analysis of the Technological Evolution of Materials Requirements Included in Reactor Pressure Vessel Manufacturing Codes.
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- Sustainability (2071-1050), 2021, v. 13, n. 10, p. 5498, doi. 10.3390/su13105498
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Calculation of Potential Radiation Doses Associated with Predisposal Management of Dismantled Steam Generators from Nuclear Power Plants.
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- Sustainability (2071-1050), 2020, v. 12, n. 12, p. 5149, doi. 10.3390/su12125149
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Genotoxicity of polar fractions from a herbicide-contaminated soil does not correspond to parent contaminants.
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- Environmental Toxicology & Chemistry, 2006, v. 25, n. 7, p. 1742
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- Article
Development of the technology of diffusion bonding of guide channels of the water–water energy reactor.
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- Welding International, 2012, v. 26, n. 10, p. 782, doi. 10.1080/09507116.2011.653161
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Stress corrosion cracking of the AISI 316L stainless steel HAZ in a PWR nuclear reactor environment.
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- Welding International, 2011, v. 25, n. 1, p. 15, doi. 10.1080/09507110903569073
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Time-Series Forecasting of a Typical PWR Undergoing Large Break LOCA.
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- Science & Technology of Nuclear Installations, 2024, v. 2024, p. 1, doi. 10.1155/2024/6162232
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A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem.
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- Science & Technology of Nuclear Installations, 2023, p. 1, doi. 10.1155/2023/9385756
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A New Experimental Method for the Nonlinear Modal Parameter Identification of a Pressurized Water Reactor Fuel Assembly.
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- Science & Technology of Nuclear Installations, 2023, p. 1, doi. 10.1155/2023/8892196
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Assessing the Impact of Common Cause Failures on Site Risk within Level 1 Multi-Unit PSA.
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- Science & Technology of Nuclear Installations, 2023, p. 1, doi. 10.1155/2023/5889803
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Neutronic Analysis of the AP1000 Fuel Assembly with Accident Tolerant Cladding Materials.
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- Gazi University Journal of Science, 2024, v. 37, n. 4, p. 2012, doi. 10.35378/gujs.1332751
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A Modified Strain Softening–Hardening Constitutive Model for Plastic Concrete Cut-off Wall.
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- Geotechnical & Geological Engineering, 2024, v. 42, n. 1, p. 389, doi. 10.1007/s10706-023-02579-2
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Actinides induced irradiation damage and swelling effect in irradiated Zircaloy-4 after 30 years of storage.
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- Safety of Nuclear Waste Disposal, 2021, v. 1, p. 7, doi. 10.5194/sand-1-7-2021
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Self‐supervised multimodal fusion transformer for passive activity recognition.
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- IET Wireless Sensor Systems (Wiley-Blackwell), 2022, v. 12, n. 5/6, p. 149, doi. 10.1049/wss2.12044
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Corrosion Properties Characterization of 06Cr18Ni10Ti, 08Cr18Ni10Ti Steels and 42CrNiMo Alloy under Conditions Simulating Primary Coolant of Pressurized Water Reactor.
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- Metallophysics & Advanced Technologies / Metallofizika i Novejsie Tehnologii, 2023, v. 45, n. 4, p. 481, doi. 10.15407/mfint.45.04.0481
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Influence of Liquid Fill Level on The Blast Created by a Water BLEVE in a Tubular Geometry.
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- CET Journal - Chemical Engineering Transactions, 2022, v. 91, p. 547, doi. 10.3303/CET2291092
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刚性截面族附加质量系数的面元计算方法 及其在燃料组件中的应用.
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- Applied Mathematics & Mechanics (1000-0887), 2023, v. 44, n. 2, p. 133, doi. 10.21656/1000-0887.430292
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Application of artificial neural networks for predicting the isotopic composition of high burn-up solid plutonium sample using the 90–105 keV gamma-spectrum region.
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- Radiochimica Acta, 2022, v. 110, n. 5, p. 323, doi. 10.1515/ract-2021-1129
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MATHEMATICAL MODELING OF TUBE-SUPPORT FOULING IN NUCLEAR STEAM GENERATORS.
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- i-Manager's Journal on Mechanical Engineering, 2014, v. 4, n. 3, p. 1, doi. 10.26634/jme.4.3.2724
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Deposition of hematite particles on alumina seal faceplates of nuclear reactor coolant pumps - laboratory experiments and industrial feedback.
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- Chemical Industry / Hemijska Industrija, 2012, v. 66, n. 3, p. 291, doi. 10.2298/HEMIND110922101L
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LOCAL ZOOM COMPUTATION OF TWO-PHASE FLOWS IN STEAM GENERATORS USING A LOCAL DEFECT CORRECTION METHOD.
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- Numerical Heat Transfer: Part A -- Applications, 2003, v. 43, n. 2, p. 111, doi. 10.1080/10407780307329
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IMPLEMENTATION AND PERFORMANCE EVALUATION OF INTELLIGENT TECHNIQUES FOR CONTROLLING A PRESSURIZED WATER REACTOR.
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- Journal of Automation, Mobile Robotics & Intelligent Systems, 2024, v. 18, n. 4, p. 71, doi. 10.14313/JAMRIS/4-2024/32
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- Article
Influence of Concrete Properties on Molten Core-Concrete Interaction: A Simulation Study.
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- Advances in Materials Science & Engineering, 2016, p. 1, doi. 10.1155/2016/5380835
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- Article
Fretting Wear Characteristics of Nuclear Fuel Cladding in High-Temperature Pressurized Water.
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- Chinese Journal of Mechanical Engineering, 2023, v. 36, n. 1, p. 1, doi. 10.1186/s10033-023-00931-4
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Measurements of Liquid AISI 304L Steel Density and Surface Tension, and Influence of Surface‐Active Elements at High Temperatures.
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- Steel Research International, 2022, v. 93, n. 6, p. 1, doi. 10.1002/srin.202100624
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Investigation of Photovoltaic Assisted Misting System Application for Arbor Refreshment.
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- International Journal of Photoenergy, 2015, v. 2015, p. 1, doi. 10.1155/2015/748219
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A Review of Advances in Pressurizer Response Research for Pressurized Water Reactor Systems.
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- International Journal of Simulation: Systems, Science & Technology, 2018, v. 19, n. 2, p. 1, doi. 10.5013/IJSSST.a.19.02.03
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Genetic Algorithms to Estimate the Pressure Deviations in Dynamic Transients of the Pressurizer Response in PWRs.
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- International Journal of Simulation: Systems, Science & Technology, 2018, v. 19, n. 1, p. 1, doi. 10.5013/IJSSST.a.19.01.03
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Mathematical Analysis of the Transient Dynamic of Surge-In or/and Surge-Out of the Pressurizer of PWR.
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- International Journal of Simulation: Systems, Science & Technology, 2017, v. 18, n. 4, p. 5.1, doi. 10.5013/IJSSST.a.18.04.05
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Visit KKNPP - an initiative for public understanding of nuclear power.
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- Current Science (00113891), 2016, v. 111, n. 2, p. 246
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- Article
High-radiation-exposure tasks in Korean pressurized heavy-water reactors.
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- Radiation Protection Dosimetry, 2024, v. 200, n. 8, p. 745, doi. 10.1093/rpd/ncae100
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- Article