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Journal Articles

Hydrogen Loading System for Thin Films for Betavoltaics

Darrell Cheu, Thomas Adams, Shripad Revankar

ASME J of Nuclear Rad Sci. October 2023, 9(4): 044501.

Paper No: NERS-22-1172

DOI: https://doi.org/10.1115/1.4056974

Published Online: March 13, 2023

View Article titled, Hydrogen Loading System for Thin Films for Betavoltaics

Topics: Hydrogen, Palladium, Temperature, Leakage, Pressure drop, Thin films

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

ASME J of Nuclear Rad Sci. January 2023, 9(1): 014502.

Paper No: NERS-21-1110

DOI: 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

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

ASME J of Nuclear Rad Sci. January 2023, 9(1): 014501.

Paper No: NERS-22-1001

DOI: 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

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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.

Paper No: NERS-20-1206

DOI: 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

Topics: Filters, Pipes, Signals, Stress, Temperature, Monitoring systems, Nuclear power stations

Journal Articles

Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping

Nader M. A. Mohamed, Mosa Osman, Ibrahim Abdelrazek

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034503.

Paper No: NERS-21-1109

DOI: 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

Topics: Irradiation (Radiation exposure), Neutron flux, Neutrons, Silicon

Journal Articles

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

Sal Rodriguez, Nima Fathi, Mahyar Pourghasemi

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034502.

Paper No: NERS-20-1213

DOI: 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

Topics: Flow (Dynamics), Internal flow, Kinematics, Turbulence, Viscosity, Simulation, Eddies (Fluid dynamics)

Journal Articles

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

Ville Valtavirta, Antti Rintala, Unna Lauranto

ASME J of Nuclear Rad Sci. October 2022, 8(4): 044504.

Paper No: NERS-21-1020

DOI: 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

Topics: Boron, Chain, Manufacturing, Errors, Temperature, Fuels, Physics

Journal Articles

Experimental Investigation on the Retention of Soluble Particles by Pool Scrubbing

R. Vennemann, M. Klauck, H.-J. Allelein

ASME J of Nuclear Rad Sci. October 2022, 8(4): 044502.

Paper No: NERS-20-1212

DOI: 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

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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 044503.

Paper No: NERS-21-1019

DOI: 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

Topics: Boiling water reactors, Emissions, Heat, Manufacturing, Nuclear fission, Photons, Probability, Resonance, Spent nuclear fuels, Nuclides

Journal Articles

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

Charles McCombie

ASME J of Nuclear Rad Sci. October 2022, 8(4): 044501.

Paper No: NERS-20-1198

DOI: 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

Topics: Nuclear power, Radioactive wastes, Economics , Waste management

Journal Articles

A Short Inroad to Optimized Compactification of Composite Neutronic Shields

Nassar H. S. Haidar

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024506.

Paper No: NERS-21-1173

DOI: 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

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

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024505.

Paper No: NERS-20-1167

DOI: 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

Topics: Coolants, Currents, Design, Excitation, Liquid metals, Magnetic fields, Pressure, Sodium, Heat exchangers, Pumps

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

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024507.

Paper No: NERS-20-1005

DOI: 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

Topics: Approximation, Cross section (Physics), Electromagnetic scattering, Errors, Neutrons, Radiation scattering, Scattering (Physics), Fuels, Anisotropy

Journal Articles

The Incorporation of Human Performance Improvement into Systems Design

Jonathan K. Corrado

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024504.

Paper No: NERS-21-1062

DOI: https://doi.org/10.1115/1.4051792

Published Online: October 19, 2021

View Article titled, The Incorporation of Human Performance Improvement into Systems Design

Topics: Design, Errors

Journal Articles

Thermal Soil Radon Mitigation

Francisco J. Arias, Salvador De Las Heras

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024503.

Paper No: NERS-20-1215

DOI: https://doi.org/10.1115/1.4050832

Published Online: October 19, 2021

View Article titled, Thermal Soil Radon Mitigation

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

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024501.

Paper No: NERS-19-1159

DOI: 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

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

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024502.

Paper No: NERS-20-1015

DOI: https://doi.org/10.1115/1.4051362

Published Online: October 19, 2021

View Article titled, Proactive Human Error Reduction Using the Systems Engineering Process

Topics: Design, Errors, Systems engineering

Journal Articles

Small Modular Reactors: Learning From the Past

Esam M. A. Hussein

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034508.

Paper No: NERS-20-1152

DOI: https://doi.org/10.1115/1.4050478

Published Online: May 26, 2021

View Article titled, Small Modular Reactors: Learning From the Past

Topics: Coolants, Fast neutron reactors, Fuels, Gas cooled reactors, High temperature, Liquid metals, Molten salt reactors, Pressurized water reactors, Small modular reactors, Licensing

Journal Articles

CANDU-Like Features in Emerging Small Modular Reactor Designs

Esam M. A. Hussein

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034507.

Paper No: NERS-20-1151

DOI: https://doi.org/10.1115/1.4050477

Published Online: May 26, 2021

View Article titled, CANDU-Like Features in Emerging Small Modular Reactor Designs

Topics: Fuels, Small modular reactors, Water, Coolants, Drainage, Heat sinks, Design, Construction, Lithium, Heat

Journal Articles

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

L. C. Juárez, J. I. Torres, J. L. François

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034505.

Paper No: NERS-20-1068

DOI: https://doi.org/10.1115/1.4049714

Published Online: April 1, 2021

View Article titled, Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

Topics: Coolants, Density, Fast neutron reactors, Fuels, Neutrons, Cycles, Temperature, Modeling

Journal citation

NARROW

Hydrogen Loading System for Thin Films for Betavoltaics

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

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

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping

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

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

Experimental Investigation on the Retention of Soluble Particles by Pool Scrubbing

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

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

A Short Inroad to Optimized Compactification of Composite Neutronic Shields

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

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

The Incorporation of Human Performance Improvement into Systems Design

Thermal Soil Radon Mitigation

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

Proactive Human Error Reduction Using the Systems Engineering Process

Small Modular Reactors: Learning From the Past

CANDU-Like Features in Emerging Small Modular Reactor Designs

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

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