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Journal Articles

High-Performance Manufacturing of Canned Main Coolant Pump - Part I: Synergistical Design and Processing Optimization

Available to Purchase
Accepted Manuscript
M.K. Lei, X.P. Zhu, Bao Zhu, Yupeng Li, L. Lin, L.W. Zhang, W.G. Wang, M.Q. Li, Dongjiang Wu, D.M. Guo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1097
https://doi.org/10.1115/1.4068691
Published Online: May 15, 2025
View Articletitled, High-Performance Manufacturing of Canned Main Coolant Pump - Part I: Synergistical Design and Processing Optimization
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Topics: Coolants, Design, Manufacturing, Optimization, Pumps
Journal Articles

Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor

Open Access
A. Nava Dominguez, Xianmin Huang, Michel Gaudet, Kittima Khumsa-Ang, Alberto D'Ansi Mendoza España, Jimmy Chow, Danila Roubtsov, Hygreeva Namburi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031301.
Paper No: NERS-24-1027
https://doi.org/10.1115/1.4068326
Published Online: May 8, 2025
View Articletitled, Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor
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Topics: Cladding systems (Building), Coolants, Design, Fuels, Loss of coolant accidents, Safety, Temperature, Water, Flow (Dynamics), Small modular reactors
Journal Articles

High-Performance Manufacturing of Canned Main Coolant Pump — Part II: Reliability Evaluation

Available to Purchase
Accepted Manuscript
M.K. Lei, H.L. Che, Yupeng Li, Bao Zhu, X.P. Zhu, L. Lin, X.P. Lv, M.Q. Li, G.Y. Ma, D.M. Guo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1098
https://doi.org/10.1115/1.4068596
Published Online: May 3, 2025
View Articletitled, High-Performance Manufacturing of Canned Main Coolant Pump — Part II: Reliability Evaluation
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Topics: Coolants, Manufacturing, Pumps, Reliability, Failure, Density, Engineering prototypes, Cycles, Damage, Design
Journal Articles

Adjuster Absorber Rods Return to Service at PLNGS

Available to Purchase
J. Krishnamoorthy, D. Deveaux, D. Mullin, E. C. Usalp, L. Sun, J. Sharpe, D. Rouben
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2025, 11(3): 034503.
Paper No: NERS-24-1056
https://doi.org/10.1115/1.4067925
Published Online: March 18, 2025
View Articletitled, Adjuster Absorber Rods Return to Service at PLNGS
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Topics: Design, Rods, Shapes, Safety, Fuels
Journal Articles

A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors

Available to Purchase
Jinlei Zhao, Lixia He, Haocheng Zhao, Yuqi Zhang, Wentao Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031002.
Paper No: NERS-24-1087
https://doi.org/10.1115/1.4067824
Published Online: February 26, 2025
View Articletitled, A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors
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Topics: Errors, Fast neutron reactors, Fuels, Liquid metal fast breeder reactors, Neutrons, Regression models, Spent nuclear fuels, Uranium, Cooling, Simulation
Journal Articles

Resolving of Transportation Issue With High Activity Positron Emission Tomography Radiotracer Source to Long Distance Medical Imaging Centers

Available to Purchase
Arup Kumar Hudait, Sumita Chattopadhyay, Subrata Bera
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031003.
Paper No: NERS-24-1099
https://doi.org/10.1115/1.4067877
Published Online: February 26, 2025
View Articletitled, Resolving of Transportation Issue With High Activity Positron Emission Tomography Radiotracer Source to Long Distance Medical Imaging Centers
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Topics: Biomedical imaging, Containers, Emissions, Positrons, Radioactive tracers, Transportation systems, Tungsten, Tungsten alloys, Radiation (Physics), Imaging
Journal Articles

K-Edge Measurement Technology Simulation Model Design

Available to Purchase
Wen-Tao Li, Li-Xia He, Lei Bai, Xiao Zhao, Yu-Qi Zhang, Hao-Cheng Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2025, 11(3): 034502.
Paper No: NERS-24-1081
https://doi.org/10.1115/1.4067724
Published Online: February 14, 2025
View Articletitled, K-Edge Measurement Technology Simulation Model Design
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Topics: Absorption, Calibration, Light sources, Photons, Sensors, Uranium, X-rays, Germanium, Simulation models, Design
Journal Articles

TSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept

Open Access
Eugene Masala, Laura Blomeley, David G. Watts, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021501.
Paper No: NERS-24-1016
https://doi.org/10.1115/1.4066404
Published Online: October 8, 2024
View Articletitled, TSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept
Open the PDF for TSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept in another window
Topics: Design, Fuels, Pressurized water reactors, Water, Boron
Journal Articles

Reviewing Welding Procedures—Checklists for Nuclear Power Systems

Available to Purchase
Zengkui Zhang, Chongzhi Wu, Zhenguo Peng, Mingkai Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. October 2024, 10(4): 040803.
Paper No: NERS-24-1005
https://doi.org/10.1115/1.4065851
Published Online: July 16, 2024
View Articletitled, Reviewing Welding Procedures—Checklists for Nuclear Power Systems
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Topics: Welding, Nuclear power, Design, ASME Boiler and Pressure Vessel Code
Journal Articles

Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach

Available to Purchase
Dipanjan Ray, Satya Prakash Saraswat, Vikesh Singh Bhadouria
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041501.
Paper No: NERS-23-1097
https://doi.org/10.1115/1.4065893
Published Online: July 16, 2024
View Articletitled, Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach
Open the PDF for Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach in another window
Topics: Diffusion (Physics), Fuels, Geometry, Neutron flux, Neutrons, Scalars, Waves, Nuclear fuels, Design, Transients (Dynamics)
Journal Articles

Use of Modeling as an Enabler for Cross-Topic Knowledge Management and Ontologies to Support Return of Experience and Replicability of Large Nuclear Projects

Available to Purchase
Victor Richet, Sarah Piochaud, Mouna El Alaoui, Robert Plana
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2025, 11(1): 012202.
Paper No: NERS-23-1059
https://doi.org/10.1115/1.4064466
Published Online: May 10, 2024
View Articletitled, Use of Modeling as an Enabler for Cross-Topic Knowledge Management and Ontologies to Support Return of Experience and Replicability of Large Nuclear Projects
Open the PDF for Use of Modeling as an Enabler for Cross-Topic Knowledge Management and Ontologies to Support Return of Experience and Replicability of Large Nuclear Projects in another window
Topics: Modeling, Teams, Knowledge management, Workflow, Systems engineering, Design, Engineering disciplines
Journal Articles

Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries

Available to Purchase
Thanh Mai Vu, Le Quang Linh Tran, Thi Hong Bui, Nhu Viet Ha Pham
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031501.
Paper No: NERS-23-1039
https://doi.org/10.1115/1.4064780
Published Online: April 17, 2024
View Articletitled, Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries
Open the PDF for Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries in another window
Topics: Eigenvalues, Fast neutron reactors, Neutrons, Nuclear fission, Nuclear reactors, Uncertainty, Uncertainty analysis, Cross section (Physics), Electromagnetic scattering, Radiation scattering
Journal Articles

Public–Private Partnering in Nuclear Reactor Development—Historical Review and Implications for Today

Available to Purchase
Steven Krahn, Andrew Sowder
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030904.
Paper No: NERS-23-1042
https://doi.org/10.1115/1.4064233
Published Online: March 8, 2024
View Articletitled, Public–Private Partnering in Nuclear Reactor Development—Historical Review and Implications for Today
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Topics: Construction, Governments, Nuclear power, Nuclear reactors, Technology development, Boiling water reactors, Pressurized water reactors, Design
Journal Articles

Design and Analysis of a Free-Piston Stirling Engine for Microreactor Applications

Available to Purchase
Phat Doan, Minghui Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030907.
Paper No: NERS-23-1072
https://doi.org/10.1115/1.4064335
Published Online: March 8, 2024
View Articletitled, Design and Analysis of a Free-Piston Stirling Engine for Microreactor Applications
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Topics: Design, Engines, Pistons, Pressure, Stirling engines, Temperature, Compression, Matlab
Journal Articles

Technical Brief: Safeguardability Analysis of a Molten Salt Sampling System Design

Free
Megan Harkema, Steven Krahn, Paul Marotta
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030903.
Paper No: NERS-23-1041
https://doi.org/10.1115/1.4064343
Published Online: March 8, 2024
View Articletitled, Technical Brief: Safeguardability Analysis of a Molten Salt Sampling System Design
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Topics: Design, Fuels, Molten salt reactors, Engineering prototypes
Journal Articles

Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor

Available to Purchase
Shujun Wang, Xianmin Huang, Yanfei Rao, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021402.
Paper No: NERS-23-1086
https://doi.org/10.1115/1.4063240
Published Online: January 29, 2024
View Articletitled, Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor
Open the PDF for Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor in another window
Topics: Boilers, Design, Flow (Dynamics), Pressure, Pressurized water reactors, Small modular reactors, Temperature, Thermal hydraulics, Oscillations, Junctions
Journal Articles

Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor

Available to Purchase
Thanh Mai Vu, Thi Hong Bui, Le Quang Linh Tran
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021503.
Paper No: NERS-23-1046
https://doi.org/10.1115/1.4063739
Published Online: January 29, 2024
View Articletitled, Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor
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Topics: Control systems, Design, Fast neutron reactors, Fuels, Neutrons, Rods, Coolants, Boron, Absorption, Safety
Journal Articles

Application of Level 3 Probabilistic Safety Analysis in UK HPR1000

Available to Purchase
Jinkai Wang, Qi Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021702.
Paper No: NERS-22-1112
https://doi.org/10.1115/1.4063874
Published Online: January 29, 2024
View Articletitled, Application of Level 3 Probabilistic Safety Analysis in UK HPR1000
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Topics: Accidents, Radiation (Physics), Risk, Probabilistic safety assessment, Design
Journal Articles

A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset

Available to Purchase
Lorenzo Loi, Stefano Lorenzi, Antonio Cammi, Carolina Introini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014502.
Paper No: NERS-23-1029
https://doi.org/10.1115/1.4064308
Published Online: December 22, 2023
View Articletitled, A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset
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Topics: Cycles, Fuels, Irradiation (Radiation exposure), Manufacturing, Nuclides, Simulation, Temperature, Uncertainty, Geometry, Errors
Journal Articles

Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor

Open Access
Huiping V. Yan, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021502.
Paper No: NERS-23-1010
https://doi.org/10.1115/1.4063388
Published Online: November 1, 2023
View Articletitled, Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor
Open the PDF for Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor in another window
Topics: Coolants, Fuels, Temperature, Hydrogen, Graphite, Design, Rods, Physics