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Proceedings Papers

Fracture Resistance of Cast Austenitic Stainless Steels

Y. Chen, W-Y. Chen, A. S. Rao, Z. Li, Y. Yang, B. Alexandreanu, K. Natesan
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A022, June 26–30, 2016
Paper No: ICONE24-60736
DOI: https://doi.org/10.1115/ICONE24-60736
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Topics: Fracture (Materials), Stainless steel, Neutrons, Irradiation (Radiation exposure), Ferrites (Magnetic materials), Fracture toughness, Alloys, Embrittlement, Light water reactors, Corrosion resistance
Proceedings Papers

Materials Performance in Advanced Combustion Systems

K. Natesan
Proc. ASME. GT1993, Volume 3A: General, V03AT15A052, May 24–27, 1993
Paper No: 93-GT-201
DOI: https://doi.org/10.1115/93-GT-201
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Topics: Coal, Coal conversion, Combustion, Combustion systems, Energy generation, Feedstock, Fuels, Thermal efficiency
Proceedings Papers

Cyclic Crack Growth Rate of Irradiated Austenitic Stainless Steel Welds in Simulated BWR Environment

Y. Chen, B. Alexandreanu, W. J. Shack, K. Natesan, A. S. Rao
Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 655-661, July 17–21, 2011
Paper No: PVP2011-57728
DOI: https://doi.org/10.1115/PVP2011-57728
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Topics: Boiling water reactors, Fracture (Materials), Stainless steel, Welded joints, Irradiation (Radiation exposure), Cracking (Materials), Fracture (Process), Neutrons, Stress, Corrosion
Proceedings Papers

Design and Development of Diverse Safety Rod and Its Drive Mechanism for PFBR

R. Vijayashree, P. ChellaPandi, K. Natesan, S. Jalaldeen, S. C. Chetal, Baldev Raj
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 969-977, July 12–16, 2009
Paper No: ICONE17-75851
DOI: https://doi.org/10.1115/ICONE17-75851
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Topics: Design, Safety, Engineering prototypes, Rods, Construction, Electromagnets, Fast neutron reactors, Scram, Sodium, Testing
Proceedings Papers

Material Degradation in ACR-700 Fuel Channel Components

V. N. Shah, K. Natesan, C. A. Greene
Proc. ASME. PVP2006-ICPVT-11, Volume 7: Operations, Applications, and Components, 127-139, July 23–27, 2006
Paper No: PVP2006-ICPVT-11-93656
DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93656
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Topics: Fuels, Materials degradation, Pressure, Design, Coolants, Water, Failure, Uranium, Corrosion, Cracking (Materials)
Journal Articles

Materials Performance in Advanced Combustion Systems

K. Natesan
Journal: Journal of Engineering for Gas Turbines and Power
Article Type: Research Papers
J. Eng. Gas Turbines Power. April 1994, 116(2): 331–337.
DOI: https://doi.org/10.1115/1.2906824
Published Online: April 1, 1994
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Topics: Coal, Coal conversion, Combustion, Combustion systems, Energy generation, Feedstock, Fuels, Thermal efficiency
Journal Articles

Representation of Elevated-Temperature Tensile Behavior of Type 304 Stainless Steel in a Sodium Environment

O. K. Chopra, K. Natesan
Journal: Journal of Engineering Materials and Technology
Article Type: Research Papers
J. Eng. Mater. Technol. October 1977, 99(4): 366–371.
DOI: https://doi.org/10.1115/1.3443553
Published Online: October 1, 1977
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Topics: Sodium, Stainless steel, Temperature, Flow (Dynamics), Failure, Stress, Carburization, Ductile fracture, Elongation, Fracture (Materials)