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Pressurized water reactor
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Keyword
keyword
Pressurized water reactor
RIS
0.002
(Research Intensity Score)
Papers
224
Top papers
High-temperature steam corrosion performance of FeCrAl alloys after long-term service in PWR condition: A reliable evaluation and multiscale microstructural characterization
2026 · 29 citations
A review of stress corrosion cracking of austenitic stainless steels in PWR primary water
2023 · 79 citations
Discrete-time sliding mode prescribed performance controller via Kalman filter and disturbance observer for load following of a pressurized water reactor
2024 · 25 citations
Effect of thermal aging on corrosion fatigue crack growth behavior of 316LN stainless steel in simulated PWR primary water
2025 · 10 citations
Corrosion of zirconium fuel cladding inside a boiling water reactor: A post-irradiation study by atom probe tomography
2025 · 9 citations
Deformation band corrosion as a result of applied stress and cold-work in 304 stainless steel in simulated pressurized water reactor primary water conditions
2025 · 9 citations
LQI-based adaptive super-twisting sliding mode controller for a pressurized water reactor in load-following operation
2026 · 1 citations
Reconstructing patterns of missing fuel pins in PWR spent nuclear fuel assemblies via CNNs
2026 · 1 citations
Effect of zirconium fuel cladding oxidation on water boiling in PWR: A molecular dynamics study
2025 · 4 citations
Newest papers
High-temperature steam corrosion performance of FeCrAl alloys after long-term service in PWR condition: A reliable evaluation and multiscale microstructural characterization
2026 · 29 citations
LQI-based adaptive super-twisting sliding mode controller for a pressurized water reactor in load-following operation
2026 · 1 citations
Reconstructing patterns of missing fuel pins in PWR spent nuclear fuel assemblies via CNNs
2026 · 1 citations
Proposal of a Deuterium-Tritium fusion / PWR fission hybrid reactor
2026
Proposal of a Deuterium-Tritium fusion / PWR fission hybrid reactor
2026
Proposal of a Deuterium-Tritium fusion / PWR fission hybrid reactor
2026
Probabilistic failure assessment of spent nuclear fuel cladding based on critical crack depth
2026
Thermomechanical Analysis of UO2 Fuel Rods with SiC_f/SiC Composite Cladding under Normal and Accident Conditions
2026
NEUTRONICS AND THERMAL-HYDRAULICS OF PRESSURIZED WATER REACTOR WITH THORIUM-BASED FUEL
2026
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