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Journal Articles

Spatial Distribution Assay of Active Neutron Counting

Yuqi Zhang, Xiaoming Xu, Yimei Cheng, Lixia He, Xiao Fan, Haocheng Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2025, 11(2): 024501.
Paper No: NERS-24-1011
https://doi.org/10.1115/1.4066883
Published Online: November 22, 2024
View Article titled, Spatial Distribution Assay of Active Neutron Counting
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Topics: Neutrons, Nuclear fission, Simulation, Cavities, Fittings
Journal Articles

Development of Risk Informed Aging Management Program in Decommissioning

Masao Uesaka, Kenta Murakami
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2025, 11(1): 014501.
Paper No: NERS-23-1063
https://doi.org/10.1115/1.4065139
Published Online: May 10, 2024
View Article titled, Development of Risk Informed Aging Management Program in Decommissioning
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Topics: Maintenance, Nuclear decommissioning, Nuclear power stations, Safety, Fire, Risk
Journal Articles

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

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 Article titled, 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

Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor

Tomas Korinek, Radek Skoda, Martin Lovecky, Ondrej Burian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014501.
Paper No: NERS-23-1015
https://doi.org/10.1115/1.4063007
Published Online: October 20, 2023
View Article titled, Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor
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Topics: Computational fluid dynamics, Cooling systems, Flow (Dynamics), Fluid dynamics, Heat, Heavy water reactors, Inertia (Mechanics), Pressure, Temperature, Vessels
Journal Articles

Characterization of the Degradation of HEPA Filters Protected by Different Spark Arrestors for Various Cutting Means and Cutting Conditions

Bourrous Soleiman, Barrault Mathieu, Ricciardi Laurent
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2023, 9(1): 014502.
Paper No: NERS-21-1110
https://doi.org/10.1115/1.4054942
Published Online: July 19, 2022
View Article titled, Characterization of the Degradation of HEPA Filters Protected by Different Spark Arrestors for Various Cutting Means and Cutting Conditions
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Topics: Cutting, Filters, Filtration, Plasmas (Ionized gases), Particle size, HEPA filters, Particulate matter, Tool grinders, Aerosols, Cutting tools
Journal Articles

Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector

Basim Khalaf Rejah
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2023, 9(1): 014501.
Paper No: NERS-22-1001
https://doi.org/10.1115/1.4054619
Published Online: June 7, 2022
View Article titled, Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector
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Topics: Sensors, Soil, Uranium, Nuclear track detectors, Bridges (Structures), Rocks, Radiation (Physics), Water
Journal Articles

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

S. A. Cancemi, R. Lo Frano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.
Paper No: NERS-20-1206
https://doi.org/10.1115/1.4053689
Published Online: May 26, 2022
View Article titled, Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance
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Topics: Filters, Pipes, Signals, Stress, Temperature, Monitoring systems, Nuclear power stations
Journal Articles

Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows

Sal Rodriguez, Nima Fathi, Mahyar Pourghasemi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034502.
Paper No: NERS-20-1213
https://doi.org/10.1115/1.4054342
Published Online: May 26, 2022
View Article titled, Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows
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Topics: Flow (Dynamics), Internal flow, Kinematics, Turbulence, Viscosity, Simulation, Eddies (Fluid dynamics)
Journal Articles

Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping

Nader M. A. Mohamed, Mosa Osman, Ibrahim Abdelrazek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034503.
Paper No: NERS-21-1109
https://doi.org/10.1115/1.4054005
Published Online: May 26, 2022
View Article titled, Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping
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Topics: Irradiation (Radiation exposure), Neutron flux, Neutrons, Silicon
Journal Articles

Validating the serpent-ants Calculation Chain Using BEAVRS Fresh Core Hot Zero Power Data

Ville Valtavirta, Antti Rintala, Unna Lauranto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044504.
Paper No: NERS-21-1020
https://doi.org/10.1115/1.4052731
Published Online: March 16, 2022
View Article titled, Validating the serpent-ants Calculation Chain Using BEAVRS Fresh Core Hot Zero Power Data
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Topics: Boron, Chain, Manufacturing, Errors, Temperature, Fuels, Physics
Journal Articles

Nuclear Power and Nuclear Technologies Can Benefit From Regional Implementation of Multinational Approaches

Charles McCombie
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044501.
Paper No: NERS-20-1198
https://doi.org/10.1115/1.4049756
Published Online: March 15, 2022
View Article titled, Nuclear Power and Nuclear Technologies Can Benefit From Regional Implementation of Multinational Approaches
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Topics: Nuclear power, Radioactive wastes, Economics , Waste management
Journal Articles

Experimental Investigation on the Retention of Soluble Particles by Pool Scrubbing

R. Vennemann, M. Klauck, H.-J. Allelein
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044502.
Paper No: NERS-20-1212
https://doi.org/10.1115/1.4051250
Published Online: March 15, 2022
View Article titled, Experimental Investigation on the Retention of Soluble Particles by Pool Scrubbing
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Topics: Aerosols, Particulate matter, Water, Accidents, Bubbles
Journal Articles

The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term

Riku Tuominen, Ville Valtavirta
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044503.
Paper No: NERS-21-1019
https://doi.org/10.1115/1.4051445
Published Online: March 15, 2022
View Article titled, The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term
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Topics: Boiling water reactors, Emissions, Heat, Manufacturing, Nuclear fission, Photons, Probability, Resonance, Spent nuclear fuels, Nuclides
Journal Articles

A Short Inroad to Optimized Compactification of Composite Neutronic Shields

Nassar H. S. Haidar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024506.
Paper No: NERS-21-1173
https://doi.org/10.1115/1.4053334
Published Online: February 7, 2022
View Article titled, A Short Inroad to Optimized Compactification of Composite Neutronic Shields
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Topics: Composite materials, Design, Neutrons, Optimization, Neutron beams, Diffusion (Physics), Weight (Mass)
Journal Articles

On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

Serguei Podobed
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024505.
Paper No: NERS-20-1167
https://doi.org/10.1115/1.4052591
Published Online: January 11, 2022
View Article titled, On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix
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Topics: Coolants, Currents, Design, Excitation, Liquid metals, Magnetic fields, Pressure, Sodium, Heat exchangers, Pumps
Journal Articles

The Incorporation of Human Performance Improvement into Systems Design

Jonathan K. Corrado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024504.
Paper No: NERS-21-1062
https://doi.org/10.1115/1.4051792
Published Online: October 19, 2021
View Article titled, The Incorporation of Human Performance Improvement into Systems Design
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Topics: Design, Errors
Journal Articles

Thermal Soil Radon Mitigation

Francisco J. Arias, Salvador De Las Heras
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024503.
Paper No: NERS-20-1215
https://doi.org/10.1115/1.4050832
Published Online: October 19, 2021
View Article titled, Thermal Soil Radon Mitigation
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Topics: Diffusion (Physics), Soil, Temperature, Rocks, Temperature gradient
Journal Articles

Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability

Boris Haranki, Ufuk Dilek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024501.
Paper No: NERS-19-1159
https://doi.org/10.1115/1.4051363
Published Online: October 19, 2021
View Article titled, Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability
Open the PDF for Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability in another window
Topics: ASTM International, Concretes, Design, Flow (Dynamics), Nuclear construction, Pumps, Stability
Journal Articles

Proactive Human Error Reduction Using the Systems Engineering Process

Jonathan K. Corrado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024502.
Paper No: NERS-20-1015
https://doi.org/10.1115/1.4051362
Published Online: October 19, 2021
View Article titled, Proactive Human Error Reduction Using the Systems Engineering Process
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Topics: Design, Errors, Systems engineering
Journal Articles

Using the Few-Group Approximation for Calculating Some Neutron-Physical Characteristics of VVER-1000 Core by Means of the Monte Carlo Universal Code

A. S. Bikeev, Yu. S. Daichenkova, M. A. Kalugin, D. A. Shkarovsky, V. V. Shkityr
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024507.
Paper No: NERS-20-1005
https://doi.org/10.1115/1.4052340
Published Online: October 19, 2021
View Article titled, Using the Few-Group Approximation for Calculating Some Neutron-Physical Characteristics of VVER-1000 Core by Means of the Monte Carlo Universal Code
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Topics: Approximation, Cross section (Physics), Electromagnetic scattering, Errors, Neutrons, Radiation scattering, Scattering (Physics), Fuels, Anisotropy