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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
Article Type: Research-Article
J. Pressure Vessel Technol. April 2023, 145(2): 021301.
Paper No: PVT-21-1146
DOI: 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
Article Type: Research-Article
J. Pressure Vessel Technol. April 2023, 145(2): 021302.
Paper No: PVT-21-1147
DOI: 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
Paper No: PVP2022-84811
DOI: 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
Paper No: PVP2022-84807
DOI: 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

A Viscoplastic Model for Alloy 617 for Use With the ASME Section III, Division 5 Design by Inelastic Analysis Rules

M. C. Messner, T.-L. Sham
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A034, July 13–15, 2021
Paper No: PVP2021-61607
DOI: https://doi.org/10.1115/PVP2021-61607
View Paper titled, A Viscoplastic Model for Alloy 617 for Use With the ASME Section III, Division 5 Design by Inelastic Analysis Rules
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Topics: Alloys, Design, Inelastic analysis, Creep, Deformation, Fatigue, ASME Boiler and Pressure Vessel Code, Computer software, Databases, Elastic analysis
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
Paper No: PVP2021-61858
DOI: 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

Evaluation of Primary-Load Effects on Creep-Fatigue Life of Alloy 617 Using Simplified Model Test Method

Yanli Wang, Peijun Hou, Robert I. Jetter, T.-L. Sham
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A036, July 13–15, 2021
Paper No: PVP2021-61658
DOI: https://doi.org/10.1115/PVP2021-61658
View Paper titled, Evaluation of Primary-Load Effects on Creep-Fatigue Life of Alloy 617 Using Simplified Model Test Method
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Topics: Alloys, Creep, Fatigue, Pressure, Stress
Proceedings Papers

A Probabilistic Margin Assessment of the ASME Section III, Division 5 Primary Load Design Rules for Class A Components

Andrea Nicolas, Mark C. Messner, T.-L. Sham
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A033, July 13–15, 2021
Paper No: PVP2021-61570
DOI: https://doi.org/10.1115/PVP2021-61570
View Paper titled, A Probabilistic Margin Assessment of the ASME Section III, Division 5 Primary Load Design Rules for Class A Components
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Topics: Design, Stress, Steady state, Temperature, ASME Boiler and Pressure Vessel Code, Creep, Creeping flow, Deformation, Geometry, High temperature
Proceedings Papers

A Comprehensive Comparison Between Different Multiaxial Cycle Counting Procedure

Andrea Rovinelli, Mark C. Messner, T.-L. Sham
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A038, July 13–15, 2021
Paper No: PVP2021-62067
DOI: https://doi.org/10.1115/PVP2021-62067
View Paper titled, A Comprehensive Comparison Between Different Multiaxial Cycle Counting Procedure
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Topics: Cycles, High temperature, Fatigue, ASME Boiler and Pressure Vessel Code, ASTM International, Design, Fatigue damage, High cycle fatigue, Low temperature, Nuclear design
Journal Articles

A Minimum Creep Rate for 2-1/4Cr-1Mo Steel Consistent With the ASME Section III, Division 5 Rules

Aritra Chakraborty, Mark C. Messner, T.-L. Sham
Journal: Journal of Pressure Vessel Technology
Article Type: Technical Briefs
J. Pressure Vessel Technol. August 2021, 143(4): 044502.
Paper No: PVT-20-1078
DOI: https://doi.org/10.1115/1.4049705
Published Online: February 11, 2021
View Article titled, A Minimum Creep Rate for 2-1/4Cr-1Mo Steel Consistent With the ASME Section III, Division 5 Rules
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Topics: Creep, Steel
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
Paper No: PVP2020-21469
DOI: 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

A High Temperature Primary Load Design Method Based on Elastic Perfectly-Plastic and Simplified Inelastic Analysis

M. C. Messner, R. I. Jetter, T.-L. Sham
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A068, August 3, 2020
Paper No: PVP2020-21470
DOI: https://doi.org/10.1115/PVP2020-21470
View Paper titled, A High Temperature Primary Load Design Method Based on Elastic Perfectly-Plastic and Simplified Inelastic Analysis
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Topics: Design methodology, High temperature, Inelastic analysis, Stress, Creep, Design, Damage, Finite element analysis, ASME Boiler and Pressure Vessel Code, Computer software
Proceedings Papers

Investigating the Correlation Between Different Effective Stress Measures and the Service Life of Actual High-Temperature Structural Components

Andrea Rovinelli, Mark C. Messner, T.-L. Sham
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A069, August 3, 2020
Paper No: PVP2020-21471
DOI: https://doi.org/10.1115/PVP2020-21471
View Paper titled, Investigating the Correlation Between Different Effective Stress Measures and the Service Life of Actual High-Temperature Structural Components
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Topics: High temperature, Service life (Equipment), Stress, Structural elements (Construction), Creep, Fracture (Materials), Fitness-for-service, Rupture, ASME Boiler and Pressure Vessel Code, Damage
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
Paper No: PVP2020-21493
DOI: 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
Paper No: PVP2020-21494
DOI: 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

Evaluation of Mean Stress Correction on Fatigue Curves of Grade 91 and Alloy 617 in ASME Section III Division 5

Y. Wang, M. D. McMurtrey, R. I. Jetter, T.-L. Sham
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A072, August 3, 2020
Paper No: PVP2020-21572
DOI: https://doi.org/10.1115/PVP2020-21572
View Paper titled, Evaluation of Mean Stress Correction on Fatigue Curves of Grade 91 and Alloy 617 in ASME Section III Division 5
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Topics: Alloys, Fatigue, Stress, Temperature
Proceedings Papers

Uncertainty Quantification of Viscoplastic Parameters for Grade 91 Steel Through Bayesian Analysis

Aritra Chakraborty, M. C. Messner, T.-L. Sham
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A066, August 3, 2020
Paper No: PVP2020-21306
DOI: https://doi.org/10.1115/PVP2020-21306
View Paper titled, Uncertainty Quantification of Viscoplastic Parameters for Grade 91 Steel Through Bayesian Analysis
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Topics: Algorithms, Calibration, Chain, Creep, Deformation, Electromagnetic scattering, Engineering design, Failure, Heat, Heat exchangers
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
Paper No: PVP2019-93643
DOI: 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
Proceedings Papers

A Method for Directly Assessing Elastic Follow Up in 3D Finite Element Calculations

M. C. Messner, B. Jetter, T.-L. Sham
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A064, July 14–19, 2019
Paper No: PVP2019-93644
DOI: https://doi.org/10.1115/PVP2019-93644
View Paper titled, A Method for Directly Assessing Elastic Follow Up in 3D Finite Element Calculations
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Topics: Finite element analysis, High temperature, Creep, Design methodology, Structural elements (Construction), Constitutive equations, Design, Fatigue, Simulation, Temperature
Proceedings Papers

Development of Simplified Model Test Methods for Creep-Fatigue Evaluation

Y. Wang, B. Jetter, M. C. Messner, T.-L. Sham
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A065, July 14–19, 2019
Paper No: PVP2019-93648
DOI: https://doi.org/10.1115/PVP2019-93648
View Paper titled, Development of Simplified Model Test Methods for Creep-Fatigue Evaluation
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Topics: Creep, Fatigue