17 results on '"Pressurized water reactor"'
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2. Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors
3. On-Line Monitoring of Flow-Accelerated Corrosion for Nuclear Power Plants: SBIR Phase I Final Report
4. 3D-FE Modeling of 316 SS under Strain-Controlled Fatigue Loading and CFD Simulation of PWR Surge Line
5. Thermal-Mechanical Stress Analysis of PWR Pressure Vessel and Nozzles under Grid Load-Following Mode: Interim Report on the Effect of Cyclic Hardening Material Properties and Pre-existing Cracks on Stress Analysis Results
6. Tensile and Fatigue Testing and Material Hardening Model Development for 508 LAS Base Metal and 316 SS Similar Metal Weld under In-air and PWR Primary Loop Water Conditions
7. Report on Reactor Physics Assessment of Candidate Accident Tolerant Fuel Cladding Materials in LWRs
8. System Study: High-Pressure Safety Injection 1998–2013
9. System Study: Auxiliary Feedwater 1998–2013
10. Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Validation
11. Transmutation Performance Analysis for Inert Matrix Fuels in Light Water Reactors and Computational Neutronics Methods Capabilities at INL
12. Computational Neutronics Methods and Transmutation Performance Analyses for Light Water Reactors
13. Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version)
14. Analysis of Operational and Safety Performance for Candidate Accident Tolerant Fuel and Cladding Concepts
15. Chaboche-based cyclic material hardening models for 316 SS–316 SS weld under in-air and pressurized water reactor water conditions
16. In-air and pressurized water reactor environment fatigue experiments of 316 stainless steel to study the effect of environment on cyclic hardening
17. Spent Nuclear Fuel Structural Response when Subject to an End Impact Accident
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