22 results on '"Jalaldeen, S."'
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2. Fatigue crack growth material parameters- based on prototype pipe bend test and comparison with conventional parameters
3. Creep–Fatigue Assessment for Interaction Between IHX Seal Holder and Inner Vessel Stand Pipe in a Pool-Type Fast Reactor as Per RCC-MR
4. Implications of large scale sodium water reactions in an LMFBR
5. Ballooning in fuel clad: The first of its kind approach for its investigation in fast reactors
6. Thermo-mechanical behaviour of primary system components of future FBR during crash Cooling: A numerical simulation
7. Specimen Level and Component Level Simulations of Fatigue Crack Growth Behavior under Cyclic Bending
8. Creep–Fatigue Assessment for Interaction Between IHX Seal Holder and Inner Vessel Stand Pipe in a Pool-Type Fast Reactor as Per RCC-MR
9. Design and Life Assessment of Inner Vessel for FBR-1&2
10. Creep-fatigue Damage Analysis of Lower Stay Plate in Control Plug
11. Evaluation of Speed Lowering of Primary Sodium Pump into Sodium Pool for 500 MWe PFBR Based on Creep Damage
12. Stress Indices for Non-Radial Branch Connections for Piping
13. Qualification by Prototype Component Test: An Engineering Solution to Address Manufacturing Deviation
14. Life prediction of reprocessing (CORAL) components
15. Comparison of life of two types of decay heat exchangers used in prototype fast breeder reactor
16. Specimen Level and Component Level Simulations of Fatigue Crack Growth Behavior under Cyclic Bending
17. Vibration of core subassemblies due to large sodium–water reaction in the steam generator of a Liquid Metal Fast Breeder Reactor
18. Experimental and Numerical Investigation of Vibration Transmission Between Two Parallel Plate Partially Immersed in a Fluid
19. Specimen Level and Component Level Simulations of Fatigue Crack Growth Behavior under Cyclic Bending.
20. Yield behavior of porous nuclear fuel (UO2)
21. Design and Life Assessment of Inner Vessel for FBR-1&2
22. Design and Development of Diverse Safety Rod and Its Drive Mechanism for PFBR
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