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Proceedings Papers

Design Data for Alloy 740H High Temperature Concentrating Solar Power Components

B. Barua, M. C. Messner, R. E. Bass, M. D. McMurtrey
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A021, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107318
https://doi.org/10.1115/PVP2023-107318
View Paper titled, Design Data for Alloy 740H High Temperature Concentrating Solar Power Components
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Topics: Alloys, Concentrating solar power, Design, High temperature, Fatigue, Stress, Creep, Elastic analysis, Inelastic analysis, Boilers
Journal Articles

Designing Cladded Components for High Temperature Nuclear Service: Part I—Analysis Methods

M. C. Messner, B. Barua, R. I. Jetter, T.-L. Sham
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2023, 145(2): 021301.
Paper No: PVT-21-1146
https://doi.org/10.1115/1.4055437
Published Online: December 2, 2022
View Article titled, Designing Cladded Components for High Temperature Nuclear Service: Part I—Analysis Methods
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Journal Articles

Designing Cladded Components for High Temperature Nuclear Service: Part II—Design Rules

B. Barua, M. C. Messner, R. I. Jetter, T.-L. Sham
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2023, 145(2): 021302.
Paper No: PVT-21-1147
https://doi.org/10.1115/1.4056151
Published Online: December 2, 2022
View Article titled, Designing Cladded Components for High Temperature Nuclear Service: Part II—Design Rules
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Proceedings Papers

Nickel Cladded Structural Components for Advanced Reactors

B. Barua, M. C. Messner, T.-L. Sham
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A063, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84811
https://doi.org/10.1115/PVP2022-84811
View Paper titled, Nickel Cladded Structural Components for Advanced Reactors
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Topics: Nickel, Structural elements (Construction), Design, Creep, Fatigue, High temperature, ASME Standards, Corrosion, Molten salt reactors, Base metals
Proceedings Papers

Design Charts for an Integrated Creep-Fatigue Damage Evaluation Approach

B. Barua, M. C. Messner, T.-L. Sham
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A062, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84807
https://doi.org/10.1115/PVP2022-84807
View Paper titled, Design Charts for an Integrated Creep-Fatigue Damage Evaluation Approach
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Topics: Creep, Damage, Design, Fatigue, High temperature, Alloys, Design methodology, Failure data, Fatigue damage, Nuclear reactors
Proceedings Papers

Simplified Criteria With Reduced Testing Effort for Selecting Clad Materials for High Temperature Reactor Structural Components

B. Barua, R. I. Jetter, M. C. Messner, T.-L. Sham
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A037, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61858
https://doi.org/10.1115/PVP2021-61858
View Paper titled, Simplified Criteria With Reduced Testing Effort for Selecting Clad Materials for High Temperature Reactor Structural Components
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Topics: High temperature, Structural elements (Construction), Testing, Creep, Design, Temperature, Alloys, Corrosion, Corrosion resistant materials, Design methodology
Proceedings Papers

Development of Design Method for High Temperature Nuclear Reactor Cladded Components

B. Barua, M. C. Messner, R. I. Jetter, T.-L. Sham
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A067, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21469
https://doi.org/10.1115/PVP2020-21469
View Paper titled, Development of Design Method for High Temperature Nuclear Reactor Cladded Components
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Topics: Design methodology, High temperature, Nuclear reactors, Design, Coolants, Corrosion resistant materials, Corrosion, Creep, Failure, Finite element analysis
Proceedings Papers

Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components

B. Barua, M. C. Messner, R. I. Jetter, T.-L. Sham
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A070, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21493
https://doi.org/10.1115/PVP2020-21493
View Paper titled, Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components
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Topics: High temperature, Nuclear reactors, Creep, Design, Alloys, Temperature, Cladding systems (Building), Design methodology, Elastic moduli, Failure
Proceedings Papers

Acceptance Criteria for the Mechanical Integrity of Clad/Base Metal Interface for High Temperature Nuclear Reactor Cladded Components

B. Barua, M. C. Messner, A. Rovinelli, T.-L. Sham
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A071, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21494
https://doi.org/10.1115/PVP2020-21494
View Paper titled, Acceptance Criteria for the Mechanical Integrity of Clad/Base Metal Interface for High Temperature Nuclear Reactor Cladded Components
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Topics: Acceptance criteria, Base metals, High temperature, Nuclear reactors, Design, Shear stress, Temperature, Design methodology, Bonding, Corrosion resistance
Proceedings Papers

Comparison and Assessment of the Creep-Fatigue and Ratcheting Design Methods for a Reference Gen3 Molten Salt Concentrated Solar Power Receiver

B. Barua, M. C. Messner, M. D. McMurtrey
Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A100, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93572
https://doi.org/10.1115/PVP2019-93572
View Paper titled, Comparison and Assessment of the Creep-Fatigue and Ratcheting Design Methods for a Reference Gen3 Molten Salt Concentrated Solar Power Receiver
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Topics: Concentrating solar power, Creep, Design methodology, Fatigue, Design, Temperature, Thermodynamic power cycles, ASME Boiler and Pressure Vessel Code, Brayton cycle, Constitutive equations
Proceedings Papers

Design Methodologies for High Temperature Reactor Structural Components Cladded With Noncompliant Materials

B. Barua, V.-T. Phan, M. C. Messner, B. Jetter, T.-L. Sham, Y. Wang
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A063, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93643
https://doi.org/10.1115/PVP2019-93643
View Paper titled, Design Methodologies for High Temperature Reactor Structural Components Cladded With Noncompliant Materials
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Topics: Design, High temperature, Structural elements (Construction), Corrosion resistant materials, Creep, Corrosion resistance, Deformation, Fatigue, Finite element analysis, Heat exchangers