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Journal Articles

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Accepted Manuscript
Zhenyu Wang, Xian Zhang, Shichang Liu, Rui Che, Yixue Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1095
https://doi.org/10.1115/1.4068167
Published Online: March 13, 2025
View Article titled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC
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Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety
Journal Articles

Mechanical Properties and Radon Gas Emanation Analysis of Composite Bricks Reinforced with Cellulose Nanofibrils and Graphene Oxide

Accepted Manuscript
Nur Atiqah Syahirah Shari, Mohammad Khairul Azhar Abdul Razab, An'amt Mohamed Noor, Mohd Zahri Abdul Aziz, Nor Hakimin Abdullah
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1102
https://doi.org/10.1115/1.4068121
Published Online: March 7, 2025
View Article titled, Mechanical Properties and Radon Gas Emanation Analysis of Composite Bricks Reinforced with Cellulose Nanofibrils and Graphene Oxide
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Topics: Bricks, Cellulose, Composite materials, Graphene, Mechanical properties, Bagasse, Compression, Compressive strength, Concretes, Electron field emission
Journal Articles

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

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 Article titled, 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

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 Article titled, 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

Evaluation of Radiation Shielding Effectiveness of Some Metallic Alloys Used in the Nuclear Facilities

A. M. Ali, A. M. Osman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031001.
Paper No: NERS-24-1084
https://doi.org/10.1115/1.4067629
Published Online: February 26, 2025
View Article titled, Evaluation of Radiation Shielding Effectiveness of Some Metallic Alloys Used in the Nuclear Facilities
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Topics: Alloys, Electrons, Neutrons, Particulate matter, Photons, Stainless steel, Radiation (Physics), Density, Atomic number, Gamma rays
Journal Articles

Study of TRICO II reactor start-up and shutdown operations using the OpenMC calculation code

Accepted Manuscript
Elie Mweze, Jeremie Muswema, Gracien Ekoko, Dieudonné Kom'bele
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1090
https://doi.org/10.1115/1.4067996
Published Online: February 22, 2025
View Article titled, Study of TRICO II reactor start-up and shutdown operations using the OpenMC calculation code
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Topics: Errors, Nuclear reactors, Rods, Safety, Testing, Transients (Dynamics)
Journal Articles

Impact of the Abrasive Solution Heating Process With Different Techniques on the Etching Parameters for the SSNTD (CN-85)

Manar Dheyaa Salim, Hyam Nazmy Badr Khalaf, Awsam Abdulsattar Marzaali, Mostafa Y. A. Mostafa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021002.
Paper No: NERS-24-1052
https://doi.org/10.1115/1.4066805
Published Online: November 4, 2024
View Article titled, Impact of the Abrasive Solution Heating Process With Different Techniques on the Etching Parameters for the SSNTD (CN-85)
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Topics: Etching, Sensors, Heating, Irradiation (Radiation exposure)
Journal Articles

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation

Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021101.
Paper No: NERS-24-1037
https://doi.org/10.1115/1.4066344
Published Online: October 22, 2024
View Article titled, An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation
Open the PDF for An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation in another window
Topics: Energy budget (Physics), Errors, Flow (Dynamics), Instrumentation, Temperature measurement, Measurement uncertainty, Uncertainty, Sensors, Temperature, Nuclear power stations
Journal Articles

Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in Pressurized Water Reactor Sub Channel by Direct Numerical Simulation

R. K. Singh, Deb Mukhopadhyay, D. Khakhar, J. B. Joshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021001.
Paper No: NERS-24-1004
https://doi.org/10.1115/1.4066001
Published Online: October 8, 2024
View Article titled, Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in Pressurized Water Reactor Sub Channel by Direct Numerical Simulation
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Topics: Computer simulation, Flow (Dynamics), Turbulence, Momentum, Pressurized water reactors
Journal Articles

Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy

Emmanuel O. Osigwe, Arnold Gad-Briggs, Dodeye Igbong, Theoklis Nikolaidis, Pericles Pilidis
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021201.
Paper No: NERS-19-1042
https://doi.org/10.1115/1.4044260
Published Online: February 24, 2020
View Article titled, Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy
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Topics: Cycles, Pressure, Stress, Temperature, Flow (Dynamics), Compressors, Power stations, Heat, Modeling, Closed-cycle gas turbines
Journal Articles

Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor

Hai Quan Ho, Yuki Honda, Shimpei Hamamoto, Toshiaki Ishii, Shoji Takada, Nozomu Fujimoto, Etsuo Ishitsuka
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021902.
Paper No: NERS-19-1040
https://doi.org/10.1115/1.4044529
Published Online: February 24, 2020
View Article titled, Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor
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Topics: Irradiation (Radiation exposure), Neutrons, Silicon, Solar cells, High temperature, Particulate matter
Journal Articles

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Xinyu Zhou, Zhouyu Liu, Lu Cao, Liangzhi Cao, Hongchun Wu, Yu Han, Chuntao Tang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021901.
Paper No: NERS-19-1024
https://doi.org/10.1115/1.4045035
Published Online: February 24, 2020
View Article titled, Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X
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Topics: Errors, Geometry, Interpolation, Polynomials, Octrees, Sampling methods, Virtual reality
Journal Articles

Measurements of Adhesion Force Between a Single Silver Particle Interacting With Hastelloy X and Inconel 617

Naphtali M. Mokgalapa, Tushar K. Ghosh, Robert V. Tompson, Sudarshan K. Loyalka
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041501.
Paper No: NERS-18-1069
https://doi.org/10.1115/1.4042706
Published Online: September 3, 2019
View Article titled, Measurements of Adhesion Force Between a Single Silver Particle Interacting With Hastelloy X and Inconel 617
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Topics: Adhesion, Particulate matter, Silver
Journal Articles

Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics

David William Hummel, David Raymond Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041403.
Paper No: NERS-18-1008
https://doi.org/10.1115/1.4042597
Published Online: September 3, 2019
View Article titled, Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics
Open the PDF for Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics in another window
Topics: Blades, Coolants, Flow (Dynamics), Fuels, Neutrons, Supercritical water reactors, Thermal hydraulics, Transients (Dynamics), Water, Delays
Journal Articles

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

Milorad B. Dzodzo, Francesco Oriolo, Walter Ambrosini, Marco Ricotti, Davor Grgic, Roberta Ferri, Andrea Achilli, Fosco Bianchi, Paride Meloni
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041208.
Paper No: NERS-18-1027
https://doi.org/10.1115/1.4042496
Published Online: September 3, 2019
View Article titled, Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility
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Topics: Containment vessels, Engineering prototypes, Pressure, Reactor vessels, Test facilities, Transients (Dynamics), Water, Design, Heat, Containment
Journal Articles

Supercritical Carbon Dioxide Centripetal Compressor—Aerodynamic Design and Analysis of Off Design Conditions

Xuefei Du, Dengtao Yu, Dan Luo, Diangui Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041209.
Paper No: NERS-18-1077
https://doi.org/10.1115/1.4043846
Published Online: September 3, 2019
View Article titled, Supercritical Carbon Dioxide Centripetal Compressor—Aerodynamic Design and Analysis of Off Design Conditions
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Topics: Compressors, Design, Flow (Dynamics), Pressure, Supercritical carbon dioxide
Journal Articles

Molten Salt Reactor Xenon Analysis: Review and Decomposition

Terry J. Price, Ondrej Chvala, Zack Taylor
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041210.
Paper No: NERS-18-1087
https://doi.org/10.1115/1.4043813
Published Online: September 3, 2019
View Article titled, Molten Salt Reactor Xenon Analysis: Review and Decomposition
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Topics: Fuels, Graphite, Mass transfer, Molten salt reactors, Bubbles, Diffusion (Physics)
Journal Articles

Calculation of Evaporation From Fukushima Nuclear Power Plant Spent Fuel Pools

Mirza M. Shah
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041602.
Paper No: NERS-18-1126
https://doi.org/10.1115/1.4043847
Published Online: August 2, 2019
View Article titled, Calculation of Evaporation From Fukushima Nuclear Power Plant Spent Fuel Pools
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Topics: Evaporation, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Spent nuclear fuels, Heat, Fuels
Journal Articles

Gas Turbine Arekret-Cycle Simulation Modeling for Training and Educational Purposes

Emmanuel O. Osigwe, Pericles Pilidis, Theoklis Nikolaidis, Suresh Sampath
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041207.
Paper No: NERS-19-1002
https://doi.org/10.1115/1.4043681
Published Online: August 2, 2019
View Article titled, Gas Turbine Arekret-Cycle Simulation Modeling for Training and Educational Purposes
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Topics: Closed-cycle gas turbines, Compressors, Computer simulation, Cycles, Design, Engines, Flow (Dynamics), Fluids, Gas turbines, Pressure
Journal Articles

Analyses of the Associated Technical and Economic Risks of the Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

Arnold Gad-Briggs, Pericles Pilidis, Theoklis Nikolaidis
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041201.
Paper No: NERS-18-1033
https://doi.org/10.1115/1.4042116
Published Online: July 19, 2019
View Article titled, Analyses of the Associated Technical and Economic Risks of the Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants
Open the PDF for Analyses of the Associated Technical and Economic Risks of the Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants in another window
Topics: Cycles, Helium, Nuclear power stations, Temperature, Pressure, Financial risk, Design, Risk, Compressors