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Journal Articles

Thermal Analysis of Irradiated Fuel Subassemblies and Fuel Pins During Storage in Concrete Pits of Head-End Facility

M. Rajendrakumar, K. Velusamy, P. Selvaraj, P. Chellapandi
Journal: Journal of Thermal Science and Engineering Applications
Publisher: ASME
Article Type: Research-Article
J. Thermal Sci. Eng. Appl. March 2016, 8(1): 011016.
Paper No: TSEA-14-1120
https://doi.org/10.1115/1.4030733
Published Online: November 11, 2015
View Article titled, Thermal Analysis of Irradiated Fuel Subassemblies and Fuel Pins During Storage in Concrete Pits of Head-End Facility
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Topics: Concretes, Fuels, Pins (Engineering), Storage, Temperature, Transportation systems, Heat, Spent nuclear fuels
Journal Articles

Investigation of Natural Convection in Heat Generating Molten Nuclear Fuel and Assessment of Core Damage Propagation

L. Ravi, K. Velusamy, P. Chellapandi
Journal: Journal of Thermal Science and Engineering Applications
Publisher: ASME
Article Type: Research-Article
J. Thermal Sci. Eng. Appl. September 2015, 7(3): 031009.
Paper No: TSEA-14-1147
https://doi.org/10.1115/1.4030248
Published Online: September 1, 2015
View Article titled, Investigation of Natural Convection in Heat Generating Molten Nuclear Fuel and Assessment of Core Damage Propagation
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Topics: Damage, Fuels, Heat, Heat transfer, Melting, Natural convection, Temperature, Thermal conductivity, Sodium, Heat conduction
Journal Articles

Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor

N. Mani, G. Thanigaiyarasu, P. Chellapandi
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. April 2012, 134(2): 021211.
https://doi.org/10.1115/1.4005385
Published Online: January 25, 2012
View Article titled, Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor
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Topics: Boilers, Finite element methods, Fracture (Materials), Junctions, Leakage, Leak-before-break, Nozzles, Shells, Sodium, Sodium fast reactors
Proceedings Papers

Thermal Hydraulic Analysis Towards a Robust Design of Leak Collection Tray for Pool Type Sodium Cooled Fast Reactors

Anil Kumar Sharma, K. Velusamy, N. Kasinathan, P. Chellapandi, S. C. Chetal, Baldev Raj
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 421-428, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29294
https://doi.org/10.1115/ICONE18-29294
View Paper titled, Thermal Hydraulic Analysis Towards a Robust Design of Leak Collection Tray for Pool Type Sodium Cooled Fast Reactors
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Topics: Design, Fast neutron reactors, Leakage, Sodium, Fusibles (Textiles), Pipelines, Drainage, Fire, Metals, Oxygen
Proceedings Papers

Thermal Hydraulic Analysis of Severe Accident in PFBR

K. Velusamy, P. Chellapandi, G. R. Raviprasan, P. Selvaraj, S. C. Chetal
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 389-399, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29356
https://doi.org/10.1115/ICONE18-29356
View Paper titled, Thermal Hydraulic Analysis of Severe Accident in PFBR
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Topics: Accidents, Pressure, Heat, Sodium, Temperature, Absorption, Accounting, Atmospheric pressure, Breeder reactors, Combustion
Journal Articles

Design, Development, Testing and Qualification of Diverse Safety Rod and Its Drive Mechanism for a Prototype Fast Breeder Reactor

R. Vijayashree, R. Veerasamy, Sudheer Patri, P. Chellapandi, G. Vaidyanathan, S. C. Chetal, Baldev Raj
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Research Papers
J. Eng. Gas Turbines Power. October 2010, 132(10): 102921.
https://doi.org/10.1115/1.4001059
Published Online: July 9, 2010
View Article titled, Design, Development, Testing and Qualification of Diverse Safety Rod and Its Drive Mechanism for a Prototype Fast Breeder Reactor
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Topics: Design, Engineering prototypes, Testing, Electromagnets, Safety, Sodium, Breeder reactors, Water
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75851
https://doi.org/10.1115/ICONE17-75851
View Paper titled, Design and Development of Diverse Safety Rod and Its Drive Mechanism for PFBR
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Topics: Design, Safety, Engineering prototypes, Rods, Construction, Electromagnets, Fast neutron reactors, Scram, Sodium, Testing
Proceedings Papers

Performance Evaluation of Control and Safety Rod and Its Drive Mechanism of Fast Breeder Reactor During Seismic Event

P. Chellapandi, V. Rajan Babu, S. C. Chetal, Raj Baldev
Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 109-117, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89340
https://doi.org/10.1115/ICONE14-89340
View Paper titled, Performance Evaluation of Control and Safety Rod and Its Drive Mechanism of Fast Breeder Reactor During Seismic Event
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Topics: Breeder reactors, Earthquakes, Performance evaluation, Safety, Rods, Stress, Engineering prototypes, Fuels
Proceedings Papers

Design and Qualification of Control and Safety Rod and Its Drive Mechanism of Fast Breeder Reactor

V. Rajan Babu, R. Veerasamy, D. Rangaswamy, K. Narayanan, S. C. S. Pavan Kumar, S. K. Dash, C. Meikandamurthy, K. K. Rajan, M. Rajan, P. Puthiyavinayagam, P. Chellapandi, G. Vaidyanathan, S. C. Chetal
Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 53-62, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89167
https://doi.org/10.1115/ICONE14-89167
View Paper titled, Design and Qualification of Control and Safety Rod and Its Drive Mechanism of Fast Breeder Reactor
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Topics: Breeder reactors, Design, Safety, Sodium, Engineering prototypes, Scram, Electromagnets, Shock absorbers, Temperature, Testing
Journal Articles

Assessment of Life of Inner Vessel for a Pool-Type Fast Breeder Reactor Based on Inelastic and Viscoplastic Deformations

R. S. Alwar, P. Chellapandi, S. B. Bhoje
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1993, 115(2): 185–192.
https://doi.org/10.1115/1.2929514
Published Online: May 1, 1993
View Article titled, Assessment of Life of Inner Vessel for a Pool-Type Fast Breeder Reactor Based on Inelastic and Viscoplastic Deformations
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Topics: Breeder reactors, Deformation, Vessels, Creep, Damage, Fatigue, Inelastic analysis, Computation, Computers, Constitutive equations