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Saurindranath Majumdar
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Proceedings Papers

Tensile Behavior of 82/182 Filler, Butter and Heat-Affected-Zones in a 508 LAS - 316 SS Dissimilar Weld: Tensile Test, Material Model and Finite Element Model Validation

Subhasish Mohanty, Joseph Listwan, Saurindranath Majumdar, Krishnamurti Natesan
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A024, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93952
https://doi.org/10.1115/PVP2019-93952
View Paper titled, Tensile Behavior of 82/182 Filler, Butter and Heat-Affected-Zones in a 508 LAS - 316 SS Dissimilar Weld: Tensile Test, Material Model and Finite Element Model Validation
Open the PDF for Tensile Behavior of 82/182 Filler, Butter and Heat-Affected-Zones in a 508 LAS - 316 SS Dissimilar Weld: Tensile Test, Material Model and Finite Element Model Validation in another window
Topics: Fillers (Materials), Finite element model, Heat, Testing equipment, Modeling, Damage, Finite element analysis, Hardening, Low cycle fatigue, Plasticity
Proceedings Papers

Implementation and Validation of a Fully Mechanistic Fatigue Modeling Approach in a High Performance Computing Framework

Bipul Barua, Subhasish Mohanty, Saurindranath Majumdar, Krishnamurti Natesan
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A025, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93954
https://doi.org/10.1115/PVP2019-93954
View Paper titled, Implementation and Validation of a Fully Mechanistic Fatigue Modeling Approach in a High Performance Computing Framework
Open the PDF for Implementation and Validation of a Fully Mechanistic Fatigue Modeling Approach in a High Performance Computing Framework in another window
Topics: Fatigue, Modeling, Cycles, Fatigue life, Uncertainty, Computer software, Finite element analysis, Nuclear reactors, Pipes, Pressurized water reactors
Journal Articles

Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading

Bipul Barua, Subhasish Mohanty, Joseph T. Listwan, Saurindranath Majumdar, Krishnamurti Natesan
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2018, 140(5): 051403.
Paper No: PVT-18-1061
https://doi.org/10.1115/1.4040790
Published Online: August 2, 2018
View Articletitled, Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading
Open the PDF for Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading in another window
Topics: Fatigue, Fatigue life, Finite element analysis, Modeling, Stress, Hardening, Nuclear reactors, Stainless steel, Stress analysis (Engineering), Pressurized water reactors
Journal Articles

Methodology for Stress-Controlled Fatigue Test Under In-Air and Pressurized Water Reactor Coolant Water Condition and to Evaluate the Effect of Pressurized Water Reactor Water and Loading Rate on Ratcheting

Bipul Barua, Subhasish Mohanty, Joseph T. Listwan, Saurindranath Majumdar, Krishnamurti Natesan
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2018, 140(3): 031403.
Paper No: PVT-17-1236
https://doi.org/10.1115/1.4039345
Published Online: April 4, 2018
View Articletitled, Methodology for Stress-Controlled Fatigue Test Under In-Air and Pressurized Water Reactor Coolant Water Condition and to Evaluate the Effect of Pressurized Water Reactor Water and Loading Rate on Ratcheting
Open the PDF for Methodology for Stress-Controlled Fatigue Test Under In-Air and Pressurized Water Reactor Coolant Water Condition and to Evaluate the Effect of Pressurized Water Reactor Water and Loading Rate on Ratcheting in another window
Topics: Fatigue, Fatigue testing, Pressurized water reactors, Stress, Water, Coolants, Cycles
Journal Articles

A Cyclic-Plasticity-Based Mechanistic Approach for Fatigue Evaluation of 316 Stainless Steel Under Arbitrary Loading

Bipul Barua, Subhasish Mohanty, Joseph T. Listwan, Saurindranath Majumdar, Krishnamurti Natesan
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2018, 140(1): 011403.
Paper No: PVT-17-1117
https://doi.org/10.1115/1.4038525
Published Online: December 5, 2017
View Articletitled, A Cyclic-Plasticity-Based Mechanistic Approach for Fatigue Evaluation of 316 Stainless Steel Under Arbitrary Loading
Open the PDF for A Cyclic-Plasticity-Based Mechanistic Approach for Fatigue Evaluation of 316 Stainless Steel Under Arbitrary Loading in another window
Topics: Cycles, Fatigue, Hardening, Modeling, Plasticity, Stress, Fatigue testing, Fatigue life, Stainless steel
Proceedings Papers

Fatigue Modeling of 508 LAS Under Variable Amplitude Loading: A Mechanistic Based Analytical Approach

Bipul Barua, Subhasish Mohanty, William K. Soppet, Saurindranath Majumdar, Krishnamurti Natesan
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A026, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65876
https://doi.org/10.1115/PVP2017-65876
View Paper titled, Fatigue Modeling of 508 LAS Under Variable Amplitude Loading: A Mechanistic Based Analytical Approach
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Topics: Fatigue, Modeling, Fatigue testing, Light water reactors, Pressurized water reactors, Alloy steel, Coolants, Parameter estimation, Plasticity, Safety
Proceedings Papers

Is it Possible to Get-Rid of S-N Curve for Fatigue Evaluation?: A Fully Mechanistic Model of 316SS Reactor Steel for Fatigue Life Evaluation

Bipul Barua, Subhasish Mohanty, William K. Soppet, Saurindranath Majumdar, Krishnamurti Natesan
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A027, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65890
https://doi.org/10.1115/PVP2017-65890
View Paper titled, Is it Possible to Get-Rid of S-N Curve for Fatigue Evaluation?: A Fully Mechanistic Model of 316SS Reactor Steel for Fatigue Life Evaluation
Open the PDF for Is it Possible to Get-Rid of S-N Curve for Fatigue Evaluation?: A Fully Mechanistic Model of 316SS Reactor Steel for Fatigue Life Evaluation in another window
Topics: Fatigue, Fatigue life, Steel, Stress, Hardening, Modeling, Plasticity, Uncertainty, Computer software, Cycles
Proceedings Papers

Pressurized Water Reactor Environment Effect on 316 Stainless Steel Stress Hardening/Softening: An Experimental Study

Subhasish Mohanty, William K. Soppet, Saurindranath Majumdar, Krishnamurti Natesan
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A038, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45694
https://doi.org/10.1115/PVP2015-45694
View Paper titled, Pressurized Water Reactor Environment Effect on 316 Stainless Steel Stress Hardening/Softening: An Experimental Study
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Topics: Hardening, Pressurized water reactors, Stainless steel, Stress, Light water reactors, Fatigue, Boiling water reactors, Fatigue life, Licensing, Modeling
Proceedings Papers

A Bayesian-Probabilistic Framework for Real-Time Fatigue Usage Factor Monitoring of Nuclear Reactor Components

Subhasish Mohanty, William Iverson, William K. Soppet, Saurindranath Majumdar, Krishnamurti Natesan
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A043, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45848
https://doi.org/10.1115/PVP2015-45848
View Paper titled, A Bayesian-Probabilistic Framework for Real-Time Fatigue Usage Factor Monitoring of Nuclear Reactor Components
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Topics: Fatigue, Nuclear reactors, Pressurized water reactors, Stress, Fatigue life, Stainless steel, Temperature, Water chemistry
Proceedings Papers

Effect of Pressurized Water Reactor Environment on Material Parameters of 316 Stainless Steel: A Cyclic Plasticity Based Evolutionary Material Modeling Approach

Subhasish Mohanty, William K. Soppet, Saurindranath Majumdar, Krishnamurti Natesan
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A039, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45701
https://doi.org/10.1115/PVP2015-45701
View Paper titled, Effect of Pressurized Water Reactor Environment on Material Parameters of 316 Stainless Steel: A Cyclic Plasticity Based Evolutionary Material Modeling Approach
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Topics: Modeling, Plasticity, Pressurized water reactors, Stainless steel, Stress, Fatigue life, Nuclear reactors, Coolants, Fatigue testing, Finite element model
Proceedings Papers

Online Stress Corrosion Crack Monitoring in Nuclear Reactor Components Using Active Ultrasonic Sensor Networks and Nonlinear System Identification: Data Fusion Based Big Data Analytics Approach

Subhasish Mohanty, Bryan Jagielo, Chi Bum Bahn, Saurindranath Majumdar, Krishnamurti Natesan
Proc. ASME. PVP2015, Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Competition and 23rd Annual Student Paper Competition; ASME NDE Division, V005T10A005, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45849
https://doi.org/10.1115/PVP2015-45849
View Paper titled, Online Stress Corrosion Crack Monitoring in Nuclear Reactor Components Using Active Ultrasonic Sensor Networks and Nonlinear System Identification: Data Fusion Based Big Data Analytics Approach
Open the PDF for Online Stress Corrosion Crack Monitoring in Nuclear Reactor Components Using Active Ultrasonic Sensor Networks and Nonlinear System Identification: Data Fusion Based Big Data Analytics Approach in another window
Topics: Data fusion, Nonlinear systems, Nuclear reactors, Stress corrosion cracking, Ultrasonic transducers, Inspection, Damage, Nondestructive evaluation, Sensors, Failure mechanisms