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Journal Articles

A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications

Venkata Rajesh Saranam, Peter Carter, Kyle A. Rozman, Ömer N. Doğan, Brian K. Paul
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021302.
Paper No: NERS-20-1185
https://doi.org/10.1115/1.4050421
Published Online: October 19, 2021
View Article titled, A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications
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Topics: Bonding, Creep, Design, Diffusion bonding (Metals), Fatigue, Heat exchangers, Rupture, Temperature, Stress, Pressure
Journal Articles

Basic Microstructural Characterization of Second Phases in Homogeneous Weld Joint Made of X6CrNiNbN25-20 Steel After Long-Term Exposure Time at 973 K

Jakub Řehořek, Hygreeva Kiran Namburi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2021, 7(2): 024505.
Paper No: NERS-20-1113
https://doi.org/10.1115/1.4048900
Published Online: November 16, 2020
View Article titled, Basic Microstructural Characterization of Second Phases in Homogeneous Weld Joint Made of X6CrNiNbN25-20 Steel After Long-Term Exposure Time at 973 K
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Topics: Creep, Rupture, Steel, Particulate matter, Stress, Grain size, Heat treating (Metalworking), Grain boundaries, Etching, Heat
Journal Articles

Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors

S. Majumdar, J. Kishor, A. N. Behera, B. Vishwanadh, A. Borgohain, R. Kapoor, R. Tewari, V. Kain, Madangopal Krishnan, G. K. Dey, S. Banerjee
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011603.
Paper No: NERS-19-1177
https://doi.org/10.1115/1.4047919
Published Online: October 2, 2020
View Article titled, Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors
Open the PDF for Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors in another window
Topics: Alloys, Creep, Errors, Cathode ray oscilloscopes, Electron beams, High temperature, Corrosion, Melting
Journal Articles

From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials

Petra Gávelová, Patricie Halodová, Hygreeva Kiran Namburi, Iveta Adéla Prokůpková, Marek Mikloš, Jakub Krejčí
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030917.
Paper No: NERS-18-1017
https://doi.org/10.1115/1.4043462
Published Online: May 3, 2019
View Article titled, From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials
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Topics: Alloys, High temperature, Oxidation, Testing, Transparency, Zirconium, Creep, Microscopy, Electron backscatter diffraction, Cladding systems (Building)
Journal Articles

Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver

Hiroshi Madokoro, Alexei Miassoedov, Thomas Schulenberg
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011017.
Paper No: NERS-18-1035
https://doi.org/10.1115/1.4041278
Published Online: January 24, 2019
View Article titled, Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver
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Topics: Cooling, Heat, Heat transfer, Temperature, Thermal analysis, Vessels, Heating, Accidents, Water, Heat flux
Journal Articles

The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident

Jianfeng Mao, Shiyi Bao, Zhiming Lu, Lijia Luo, Zengliang Gao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041015.
Paper No: NERS-17-1254
https://doi.org/10.1115/1.4040494
Published Online: September 10, 2018
View Article titled, The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident
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Topics: Accidents, Creep, Damage, Failure, Finite element analysis, Reactor vessels, Safety, Temperature, Wall thickness, Stress
Journal Articles

Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

Shigeru Takaya, Tai Asayama, Yoshio Kamishima, Hideo Machida, Daigo Watanabe, Satoru Nakai, Masaki Morishita
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011004.
Paper No: NERS-14-1020
https://doi.org/10.1115/1.4026392
Published Online: February 9, 2015
View Article titled, Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements
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Topics: Creep, Design, Failure, Fatigue, Fracture (Materials), In-service inspection, Probability, Reliability, Safety, Stress