Works matching DE "NUCLEAR pressure vessels"
Results: 53
Determination of stress intensity factors for semielliptical surface cracks in the WWER-1000 reactor pressure vessel from the results of solving thermoelasticity boundary value problems based on the mixed mesh-projection scheme of the finite element method
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- Strength of Materials, 2007, v. 39, n. 2, p. 138, doi. 10.1007/s11223-007-0019-z
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- Article
Вплив зміни температури на початку та наприкінці опромінення в науково-дослідному реакторі на нейтронну крихкість α-заліза
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- Metallophysics & Advanced Technologies / Metallofizika i Novejsie Tehnologii, 2019, v. 41, n. 6, p. 717, doi. 10.15407/mfint.41.06.0717
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- Article
A statistical model of cleavage fracture in structural steels with power-law distribution of microcrack size.
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- Philosophical Magazine Letters, 2016, v. 96, n. 3, p. 101, doi. 10.1080/09500839.2016.1158425
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- Article
Manitowoc Excavators and Cranes, Part III: America's Top Crane Builder, and a Look at Other Products.
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- Equipment Echoes, 2023, n. 149, p. 16
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- Article
Contribution of multiscale materials modelling for underwriting nuclear pressure vessel integrity.
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- Materials Science & Technology, 2004, v. 20, n. 5, p. 553, doi. 10.1179/026708304225016707
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- Article
Tool failure mechanisms and cutting performance analysis during high-feed milling of 508-III steel.
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- International Journal of Advanced Manufacturing Technology, 2023, v. 128, n. 9/10, p. 3921, doi. 10.1007/s00170-023-12045-1
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- Article
Measurement of Fracture Parameters in Three-Dimensional Cracked-Body Problems.
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- International Applied Mechanics, 2003, v. 39, n. 5, p. 503, doi. 10.1023/A:1025131424074
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- Article
Effect of Precipitation Control on Strength and Impact Toughness in Advanced Pressure Vessel Steel.
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- Metallurgical & Materials Transactions. Part A, 2019, v. 50, n. 11, p. 5015, doi. 10.1007/s11661-019-05416-5
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- Article
Measurement and Prediction of Phase Transformation Kinetics in a Nuclear Steel During Rapid Thermal Cycles.
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- Metallurgical & Materials Transactions. Part A, 2019, v. 50, n. 4, p. 1715, doi. 10.1007/s11661-018-05102-y
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- Article
Understanding thermally induced embrittlement in low copper RPV steels utilising atom probe tomography.
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- Materials Science & Technology, 2015, v. 31, n. 8, p. 981, doi. 10.1179/1743284714Y.0000000718
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- Article
Nondestructive materials characterization of irradiated nuclear pressure-vessel steel samples by the use of micromagnetic techniques and in terms of mechanical properties.
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- Russian Journal of Nondestructive Testing, 2006, v. 42, n. 4, p. 272, doi. 10.1134/S1061830906040085
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- Article
A Quasi Time-Domain Method for Fatigue Analysis of Reactor Pressure Vessels in Floating Nuclear Power Plants in Marine Environments.
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- Journal of Marine Science & Engineering, 2024, v. 12, n. 11, p. 2085, doi. 10.3390/jmse12112085
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- Article
A unified creep and fatigue life prediction approach for 316 austenitic stainless steel using machine and deep learning.
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- Fatigue & Fracture of Engineering Materials & Structures, 2024, v. 47, n. 9, p. 3444, doi. 10.1111/ffe.14379
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- Article
Creep behavior and life prediction of a reactor pressure vessel steel above phase‐transformation temperature via a deformation mechanism‐based creep model.
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- Fatigue & Fracture of Engineering Materials & Structures, 2023, v. 46, n. 9, p. 3342, doi. 10.1111/ffe.14081
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- Article
Research Progress of Steels for Nuclear Reactor Pressure Vessels.
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- Materials (1996-1944), 2022, v. 15, n. 24, p. 8761, doi. 10.3390/ma15248761
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- Article
Magnetic Investigation of Cladded Nuclear Reactor Blocks.
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- Materials (1996-1944), 2022, v. 15, n. 4, p. 1425, doi. 10.3390/ma15041425
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- Article
An Investigation of a New Parameter Based on the Plastic Strain Gradient to Characterize Composite Constraint around the Crack Front at a Low Temperature.
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- Materials (1996-1944), 2022, v. 15, n. 3, p. 881, doi. 10.3390/ma15030881
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- Article
Analysis of Magnetic Nondestructive Measurement Methods for Determination of the Degradation of Reactor Pressure Vessel Steel.
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- Materials (1996-1944), 2021, v. 14, n. 18, p. 5256, doi. 10.3390/ma14185256
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- Article
Inspection of Reactor Steel Degradation by Magnetic Adaptive Testing.
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- Materials (1996-1944), 2019, v. 12, n. 6, p. 963, doi. 10.3390/ma12060963
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- Article
The effect of simulated microgravity on lumbar spine biomechanics: an in vitro study.
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- 2016
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- Publication type:
- journal article
RPV Sealing Reliability Estimating Using a New Inconsistent Knowledge Fused Bayesian Network and Weighted Loss Function.
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- Processes, 2022, v. 10, n. 6, p. 1099, doi. 10.3390/pr10061099
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- Article
Microstructure Evolution of Reactor Pressure Vessel A508-3 Steel under High-Dose Heavy Ion Irradiation.
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- Crystals (2073-4352), 2022, v. 12, n. 8, p. 1091, doi. 10.3390/cryst12081091
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- Article
Temperature Dependence of Thermophysical Properties of Full-Scale Corium of Fast Energy Reactor.
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- Science & Technology of Nuclear Installations, 2017, p. 1, doi. 10.1155/2017/8294653
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- Article
Failure Analysis in Metallic Materials.
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- Metals (2075-4701), 2023, v. 13, n. 8, p. 1374, doi. 10.3390/met13081374
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- Article
Electroslag Hollow Ingots for Nuclear and Petrochemical Pressure Vessels and Pipes.
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- Metals (2075-4701), 2023, v. 13, n. 7, p. 1290, doi. 10.3390/met13071290
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- Article
Effect of Peak Temperatures on Microstructure and Properties of Welding Coarse Grain Heat-Affected Zone of SA508 Gr.4N Steel.
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- Metals (2075-4701), 2023, v. 13, n. 1, p. 50, doi. 10.3390/met13010050
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- Article
Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding.
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- Metals (2075-4701), 2021, v. 11, n. 11, p. 1676, doi. 10.3390/met11111676
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- Article
Radiation Damage of Reactor Pressure Vessel Steels Studied by Positron Annihilation Spectroscopy—A Review.
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- Metals (2075-4701), 2020, v. 10, n. 10, p. 1378, doi. 10.3390/met10101378
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- Article
Nondestructive Investigation of Neutron Irradiation Generated Structural Changes of Reactor Steel Material by Magnetic Hysteresis Method.
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- Metals (2075-4701), 2020, v. 10, n. 5, p. 642, doi. 10.3390/met10050642
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- Article
Continuous Cooling Transformations in Nuclear Pressure Vessel Steels.
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- Metallurgical & Materials Transactions. Part A, 2014, v. 45, n. 11, p. 4897, doi. 10.1007/s11661-014-2433-8
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- Article
Dynamic Strain Aging in New Generation Cr-Mo-V Steel for Reactor Pressure Vessel Applications.
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- Metallurgical & Materials Transactions. Part A, 2010, v. 41, n. 13, p. 3326, doi. 10.1007/s11661-010-0409-x
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- Article
Nanoindentation creep behavior of RPV's weld joint at room temperature.
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- Mechanics of Time-Dependent Materials, 2020, v. 24, n. 3, p. 253, doi. 10.1007/s11043-019-09419-y
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- Article
Sensor degradation in nuclear reactor pressure vessels: the overlooked factor in remaining useful life prediction.
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- NPJ Materials Degradation, 2024, v. 8, n. 1, p. 1, doi. 10.1038/s41529-024-00484-4
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- Article
Investigation of Potential Material Inhomogeneity in the Magnetically Detected Neutron-Irradiation-Generated Structural Degradation of Nuclear Reactor Pressure Vessel Steel.
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- Applied Sciences (2076-3417), 2022, v. 12, n. 22, p. 11640, doi. 10.3390/app122211640
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- Article
Investigation of the Influence of Neutron Irradiation on Cladded Nuclear Reactor Pressure Vessel Steel Blocks by Magnetic Adaptive Testing.
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- Applied Sciences (2076-3417), 2022, v. 12, n. 4, p. 2074, doi. 10.3390/app12042074
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- Article
Application of Inelastic Method and Its Comparison with Elastic Method for the Assessment of In-Box LOCA Event on EU DEMO HCPB Breeding Blanket Cap Region.
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- Applied Sciences (2076-3417), 2021, v. 11, n. 19, p. 9104, doi. 10.3390/app11199104
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- Article
Interpretation of Nondestructive Magnetic Measurements on Irradiated Reactor Steel Material.
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- Applied Sciences (2076-3417), 2021, v. 11, n. 8, p. 3650, doi. 10.3390/app11083650
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- Article
Micromagnetic Characterization of Operation-Induced Damage in Charpy Specimens of RPV Steels.
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- Applied Sciences (2076-3417), 2021, v. 11, n. 7, p. 2917, doi. 10.3390/app11072917
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- Article
Analysis of Surface Roughness Influence in Non-Destructive Magnetic Measurements Applied to Reactor Pressure Vessel Steels.
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- Applied Sciences (2076-3417), 2020, v. 10, n. 24, p. 8938, doi. 10.3390/app10248938
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- Article
Investigation of a Coolant Mixing Phenomena within the Reactor Pressure Vessel of a VVER-1000 Reactor with Different Simulation Tools.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/470794
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- Article
Main results of study on the interaction between the corium melt and steel in the VVER-1000 reactor vessel during a severe accident performed under the MASCA project.
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- Physics of Atomic Nuclei, 2010, v. 73, n. 14, p. 2301, doi. 10.1134/S1063778810140085
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- Article
Low cycle fatigue of materials in nuclear industry.
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- Mechanika, 2008, v. 73, n. 5, p. 12
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- Article
SA508Gr. 4N 钢连续冷却组织转变特性.
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- Nonferrous Metals Engineering, 2022, v. 12, n. 8, p. 46, doi. 10.3969/j.issn.2095-1744.2022.08.07
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- Article
局部区域减薄条件下核级压力容器筒壁安全性分析与评价.
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- Nuclear Safety, 2023, v. 22, n. 1, p. 76
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- Article
Pressing forward - use of hot isostatic pressing technology in manufacturing nuclear pressure vessel components.
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- Nuclear Future, 2019, v. 15, n. 1, p. 40
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- Article
Vessel installed at Fangchenggang 2.
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- Nuclear Future, 2014, v. 10, n. 6, p. 13
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- Article
Construction milestone at Taishan 2 EPR.
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- Nuclear Future, 2014, v. 10, n. 6, p. 13
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- Article
Forgemasters to review nuclear press project.
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- Nuclear Future, 2010, v. 6, n. 5, p. 240
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- Article
Experimental study on fatigue crack growth behavior and fracture toughness of SA508-III steel for nuclear reactor pressure vessel.
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- Journal of Materials Science, 2023, v. 58, n. 34, p. 13774, doi. 10.1007/s10853-023-08813-9
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- Article
Effect of multiple passes on Lüders/yield plateaus, microstructure and tensile behaviour of narrow-gap thick-section weld plates.
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- Journal of Materials Science, 2019, v. 54, n. 19, p. 12833, doi. 10.1007/s10853-019-03822-z
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- Article