1-20 of 24
R. I. Jetter
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
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
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
Open the PDF for Designing Cladded Components for High Temperature Nuclear Service: Part I—Analysis Methods in another window
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
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
Open the PDF for Designing Cladded Components for High Temperature Nuclear Service: Part II—Design Rules in another window
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
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
Open the PDF for Simplified Criteria With Reduced Testing Effort for Selecting Clad Materials for High Temperature Reactor Structural Components in another window
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
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
Open the PDF for Development of Design Method for High Temperature Nuclear Reactor Cladded Components in another window
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
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
Open the PDF for A High Temperature Primary Load Design Method Based on Elastic Perfectly-Plastic and Simplified Inelastic Analysis in another window
Topics: Design methodology, High temperature, Inelastic analysis, Stress, Creep, Design, Damage, Finite element analysis, ASME Boiler and Pressure Vessel Code, Computer software
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
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
Open the PDF for Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components in another window
Topics: High temperature, Nuclear reactors, Creep, Design, Alloys, Temperature, Cladding systems (Building), Design methodology, Elastic moduli, Failure
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
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
Open the PDF for Evaluation of Mean Stress Correction on Fatigue Curves of Grade 91 and Alloy 617 in ASME Section III Division 5 in another window
Topics: Alloys, Fatigue, Stress, Temperature
Proceedings Papers

Establishing Temperature Upper Limits for the ASME Section III, Division 5 Design by Elastic Analysis Methods

M. C. Messner, R. I. Jetter, T.-L. Sham
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A016, July 15–20, 2018
Paper No: PVP2018-84105
https://doi.org/10.1115/PVP2018-84105
View Paper titled, Establishing Temperature Upper Limits for the ASME Section III, Division 5 Design by Elastic Analysis Methods
Open the PDF for Establishing Temperature Upper Limits for the ASME Section III, Division 5 Design by Elastic Analysis Methods in another window
Topics: Design, Elastic analysis, Temperature, Plasticity, Creep, Operating temperature, ASME Boiler and Pressure Vessel Code, High temperature, Inelastic analysis, Phase transition temperature
Proceedings Papers

Assessment of Passively Actuated In-Situ Cyclic Surveillance Test Specimens for Advanced Non-Light Water Reactors

M. C. Messner, V.-T. Phan, R. I. Jetter, T.-L. Sham
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A018, July 15–20, 2018
Paper No: PVP2018-84793
https://doi.org/10.1115/PVP2018-84793
View Paper titled, Assessment of Passively Actuated In-Situ Cyclic Surveillance Test Specimens for Advanced Non-Light Water Reactors
Open the PDF for Assessment of Passively Actuated In-Situ Cyclic Surveillance Test Specimens for Advanced Non-Light Water Reactors in another window
Topics: Surveillance, Water, Creep, Damage, Fatigue, Design, Mechanical engineers, Mechanical testing, Rupture, Secondary ion mass spectrometry
Proceedings Papers

The Role of Material Modeling on Strain Range Estimation for Elevated Temperature Cyclic Life Evaluation

M. C. Messner, R. I. Jetter, T.-L. Sham, Yanli Wang
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A011, July 15–20, 2018
Paper No: PVP2018-84100
https://doi.org/10.1115/PVP2018-84100
View Paper titled, The Role of Material Modeling on Strain Range Estimation for Elevated Temperature Cyclic Life Evaluation
Open the PDF for The Role of Material Modeling on Strain Range Estimation for Elevated Temperature Cyclic Life Evaluation in another window
Topics: ASME Standards, Creep, Damage, Fatigue, High temperature, Inelastic analysis, Modeling, Nuclear reactors, Plasticity, Steady state
Proceedings Papers

The Mechanical Interaction of Clad and Base Metal for Molten Salt Reactor Structural Components

M. C. Messner, V.-T. Phan, R. I. Jetter, T.-L. Sham
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A012, July 15–20, 2018
Paper No: PVP2018-84101
https://doi.org/10.1115/PVP2018-84101
View Paper titled, The Mechanical Interaction of Clad and Base Metal for Molten Salt Reactor Structural Components
Open the PDF for The Mechanical Interaction of Clad and Base Metal for Molten Salt Reactor Structural Components in another window
Topics: Base metals, Molten salt reactors, Structural elements (Construction), High temperature, Design, Cladding systems (Building), Corrosion resistance, Corrosion resistant materials, Creep, Design methodology
Proceedings Papers

A Basis for Applying Elastic Perfectly-Plastic Design Methods to Cyclic Softening Materials

M. C. Messner, Yanli Wang, R. I. Jetter, T.-L. Sham
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A014, July 15–20, 2018
Paper No: PVP2018-84103
https://doi.org/10.1115/PVP2018-84103
View Paper titled, A Basis for Applying Elastic Perfectly-Plastic Design Methods to Cyclic Softening Materials
Open the PDF for A Basis for Applying Elastic Perfectly-Plastic Design Methods to Cyclic Softening Materials in another window
Topics: Constitutive equations, Creep, Damage, Design, Design methodology, Engineering simulation, Fatigue, Hardening, High temperature, Nuclear reactors
Proceedings Papers

Technical Background for Alloy 617 Time Dependent Allowable Stresses

J. K. Wright, N. J. Lybeck, R. W. Swindeman, R. I. Jetter, T.-L. Sham, R. N. Wright
Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A020, July 16–20, 2017
Paper No: PVP2017-66069
https://doi.org/10.1115/PVP2017-66069
View Paper titled, Technical Background for Alloy 617 Time Dependent Allowable Stresses
Open the PDF for Technical Background for Alloy 617 Time Dependent Allowable Stresses in another window
Topics: Alloys, Stress, Temperature, Creep, Design, Rupture, Very high temperature reactors, ASME Standards, Base metals, Construction
Journal Articles

Two-Bar Thermal Ratcheting for Alloy 617—Part II: Ratcheting Results

Yanli Wang, T.-L. Sham, R. I. Jetter
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. June 2015, 137(3): 031009.
Paper No: PVT-14-1064
https://doi.org/10.1115/1.4028476
Published Online: June 1, 2015
View Article titled, Two-Bar Thermal Ratcheting for Alloy 617—Part II: Ratcheting Results
Open the PDF for Two-Bar Thermal Ratcheting for Alloy 617—Part II: Ratcheting Results in another window
Topics: Alloys, Cooling, Delays, Design, Heating and cooling, Stress, Temperature, Testing, Cycles
Journal Articles

Two-Bar Thermal Ratcheting for Alloy 617—Part I: Scoping Tests

Yanli Wang, T.-L. Sham, R. I. Jetter
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. June 2015, 137(3): 031008.
Paper No: PVT-14-1063
https://doi.org/10.1115/1.4028302
Published Online: June 1, 2015
View Article titled, Two-Bar Thermal Ratcheting for Alloy 617—Part I: Scoping Tests
Open the PDF for Two-Bar Thermal Ratcheting for Alloy 617—Part I: Scoping Tests in another window
Topics: Alloys, Cycles, Stress, Temperature
Proceedings Papers

Verification of Elastic-Perfectly Plastic Methods for Evaluation of Strain Limits: Analytical Comparisons

Peter Carter, R. I. Jetter, T.-L. (Sam) Sham
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A007, July 20–24, 2014
Paper No: PVP2014-28352
https://doi.org/10.1115/PVP2014-28352
View Paper titled, Verification of Elastic-Perfectly Plastic Methods for Evaluation of Strain Limits: Analytical Comparisons
Open the PDF for Verification of Elastic-Perfectly Plastic Methods for Evaluation of Strain Limits: Analytical Comparisons in another window
Topics: Alloys, Creep, Damage, Elastic analysis, Fatigue, High temperature, Inelastic analysis, Plasticity, Plastics, Stainless steel
Proceedings Papers

Thermal Ratcheting Test Results for Alloy 617

Yanli Wang, T.-L. (Sam) Sham, R. I. Jetter
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A009, July 20–24, 2014
Paper No: PVP2014-28444
https://doi.org/10.1115/PVP2014-28444
View Paper titled, Thermal Ratcheting Test Results for Alloy 617
Open the PDF for Thermal Ratcheting Test Results for Alloy 617 in another window
Topics: Alloys, High temperature, Stress, Modeling, Very high temperature reactors, Creep, Cylinders, Design methodology, Displacement, Heating and cooling
Proceedings Papers

Application of Shakedown Analysis to Evaluation of Creep-Fatigue Limits

Peter Carter, R. I. Jetter, T.-L. (Sam) Sham
Proc. ASME. PVP2012, Volume 1: Codes and Standards, 761-770, July 15–19, 2012
Paper No: PVP2012-78083
https://doi.org/10.1115/PVP2012-78083
View Paper titled, Application of Shakedown Analysis to Evaluation of Creep-Fatigue Limits
Open the PDF for Application of Shakedown Analysis to Evaluation of Creep-Fatigue Limits in another window
Topics: Creep, Fatigue, Temperature, Damage, Rupture, Stress, Cycles, Design, Fatigue damage, Plastics
Proceedings Papers

Section III, Division 5: Development and Future Directions

D. K. Morton, R. I. Jetter, James E. Nestell, T. D. Burchell, T.-L. (Sam) Sham
Proc. ASME. PVP2012, Volume 1: Codes and Standards, 729-737, July 15–19, 2012
Paper No: PVP2012-78062
https://doi.org/10.1115/PVP2012-78062
View Paper titled, Section III, Division 5: Development and Future Directions
Open the PDF for Section III, Division 5: Development and Future Directions in another window
Topics: Boilers, Design, High temperature, Inspection, Manufacturing, Nuclear reactors, Pressure vessels, Testing
Proceedings Papers

Elevated Temperature Primary Load Design Method Using Pseudo Elastic-Perfectly Plastic Model

Peter Carter, T.-L. (Sam) Sham, R. I. Jetter
Proc. ASME. PVP2012, Volume 1: Codes and Standards, 739-748, July 15–19, 2012
Paper No: PVP2012-78081
https://doi.org/10.1115/PVP2012-78081
View Paper titled, Elevated Temperature Primary Load Design Method Using Pseudo Elastic-Perfectly Plastic Model
Open the PDF for Elevated Temperature Primary Load Design Method Using Pseudo Elastic-Perfectly Plastic Model in another window
Topics: Design methodology, Stress, Temperature, Creep, Ductility, Rupture, ASME Boiler and Pressure Vessel Code, Design, Steady state