330 results on '"Sabharwall, Piyush"'
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2. Coupled neutronics, thermochemistry, corrosion modeling and sensitivity analyses for isotopic evolution in molten salt reactors
3. Design of experimental facility for helium gas component testing
4. Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors
5. In situ embedment of type K sheathed thermocouples with directed energy deposition
6. Flow Instabilities in boiling channels and their suppression methodologies—A review
7. Technical and economic evaluation of heat transfer fluids for a TES system integrated to an advanced nuclear reactor
8. A comparative study on deep learning models for condition monitoring of advanced reactor piping systems
9. Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review
10. Global energy policy analysis to achieve near-term climate goals in the United States
11. A review on the sizing and selection of control valves for thermal hydraulics for reactor system applications
12. Integral and Separate Effects Test Facilities To Support Water Cooled Small Modular Reactors: A Review
13. Linear and Non-linear Optical Characterization of Glass and Sapphire for Optical Instrumentation of Advanced Fission Reactors
14. Passive heat removal in horizontally oriented micro-HTGRs
15. Molten salt for advanced energy applications: A review
16. Numerical study of multi-component flow and mixing in a scaled fission product venting system
17. Adsorption of Radioactive Iodine Using Nanocarbon on ETS-10 as Adsorbent.
18. A two-phase three-field modeling framework for heat pipe application in nuclear reactors
19. Kinetics of Ca(OH)2 decomposition in pure Ca(OH)2 and Ca(OH)2-CaTiO3 composite pellets for application in thermochemical energy storage system
20. Energy and exergy analysis of Ca(OH)2/CaO dehydration-hydration chemical heat pump system: Effect of reaction temperature
21. Thermodynamics of Ca(OH)2/CaO reversible reaction: Refinement of reaction equilibrium and implications for operation of chemical heat pump
22. A hybrid porous model for full reactor core scale CFD investigation of a prismatic HTGR
23. Preliminary Design Needs for High-Temperature Heat Pipe Imaging System
24. Leveraging Optimal Sparse Sensor Placement to Aggregate a Network of Digital Twins for Nuclear Subsystems.
25. Photodecomposition of methyl iodide as pretreatment for adsorption of radioiodine species in used nuclear fuel recycling operations
26. Sizing and Selection of Pressure Relief Valves for High-Pressure Thermal–Hydraulic Systems
27. Advanced Measurement and Visualization Techniques for High-Temperature Heat Pipe Experiments
28. Preliminary Pilot-scale Study and Techno-economic Analysis of Chemical Heat Pump with Conventional Nuclear Reactors
29. Mass transport analysis for tritium removal in FHRs
30. Dynamic behavior of a high-temperature printed circuit heat exchanger: Numerical modeling and experimental investigation
31. Digital Engineering Sensor Architectures for Future Microreactor Builds
32. Economic comparison of current electricity generating technologies and advanced nuclear options
33. Structural Health Monitoring of Microreactor Safety Systems Using Convolutional Neural Networks
34. Understanding Melting and Freezing/Solidification and the Associated Effects on Heat Transfer
35. DOE Microreactor Program: Summary of Experimental Capabilities Development and Activities
36. Development and validation of Nusselt number and friction factor correlations for laminar flow in semi-circular zigzag channel of printed circuit heat exchanger
37. Sizing and Selection of Pressure Relief Valves for High-Pressure Thermal–Hydraulic Systems.
38. Heat transfer and computational fluid dynamics for molten salt reactor technologies
39. Contributors
40. Test Article and Test Plan for Heat-Pipe Gap-Conductance Testing
41. Control of Advanced Reactor-Coupled Heat Exchanger System: Incorporation of Reactor Dynamics in System Response to Load Disturbances
42. Monte Carlo Analysis of Coolant Stream Impurity Gamma Emissions in Gas-Cooled Fast Reactors
43. Special issue on Advanced Reactor Thermal Hydraulics Experiments and Modeling Supporting Verification and Validation Needs
44. Advanced Manufacturing and Instrumentation for Neutron Chopper Design
45. SPHERE Assembly and Operation Demonstration
46. Experimental and numerical study of a printed circuit heat exchanger
47. Exergy analysis of thermal energy storage options with nuclear power plants
48. Pressure drop and heat transfer characteristics of a high-temperature printed circuit heat exchanger
49. Fales Hot Springs: A case study in renewable augmented net zero energy
50. A phase-field approach to model multi-axial and microstructure dependent fracture in nuclear grade graphite
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