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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

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 Article titled, 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
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Topics: Diffusion (Physics), Fuels, Geometry, Neutron flux, Neutrons, Scalars, Waves, Nuclear fuels, Design, Transients (Dynamics)
Journal Articles

Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly

Md. Tanvir Ahmed, Afroza Shelley, Md. Nobir Hosen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021602.
Paper No: NERS-23-1069
https://doi.org/10.1115/1.4063757
Published Online: January 29, 2024
View Article titled, Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly
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Topics: Cycles, Fuel rods, Fuels, Manufacturing, Neutron flux, Neutrons, Nuclear fission, Nuclear fuel cycle, Rods, Safety
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

Special Experimental Environment for Generation IV Reactors With Graphite Reflector

Eva Vilímová, Tomáš Peltan, Radek Škoda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011501.
Paper No: NERS-23-1017
https://doi.org/10.1115/1.4064124
Published Online: December 19, 2023
View Article titled, Special Experimental Environment for Generation IV Reactors With Graphite Reflector
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Topics: Graphite, Neutron flux, Neutrons, Fuels
Journal Articles

Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors

Li Wanai, Gong Helin, Zhang Chunyu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031503.
Paper No: NERS-21-1114
https://doi.org/10.1115/1.4055379
Published Online: February 22, 2023
View Article titled, Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors
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Topics: Diffusion (Physics), Finite element methods, Neutron flux, Neutrons, Computation, Finite element model
Journal Articles

Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000

Md. Tanvir Ahmed, Md. Hossain Sahadath, Md. Ashraful Islam
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031501.
Paper No: NERS-22-1022
https://doi.org/10.1115/1.4055522
Published Online: February 8, 2023
View Article titled, Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000
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Topics: Fuels, Cycles, Neutron flux, Neutrons, Manufacturing
Journal Articles

Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector

Eva Vilímová, Tomáš Peltan, Jana Jiřičková
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041505.
Paper No: NERS-21-1013
https://doi.org/10.1115/1.4050990
Published Online: June 15, 2022
View Article titled, Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector
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Topics: Graphite, Neutron flux, Neutrons, Sensors, Spent nuclear fuels, Water, Fuels
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

Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO 2 Pin Target at Power Ramp Test Facility

Octaviana Erawati Fadli, Azizul Khakim, S. Suharyana, A. Suparmi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 032002.
Paper No: NERS-20-1013
https://doi.org/10.1115/1.4048904
Published Online: April 1, 2021
View Article titled, Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO 2 Pin Target at Power Ramp Test Facility
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Topics: Irradiation (Radiation exposure), Safety, Neutron flux, Fuels, Test facilities
Journal Articles

The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

Vlastimil Juříček, Michal Košťál, Evžen Losa, Tomáš Czakoj, Zdeněk Matěj, František Cvachovec, Martin Schulc, Jan Šimon, Filip Mravec, Václav Přenosil, Vojtěch Rypar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 022005.
Paper No: NERS-20-1153
https://doi.org/10.1115/1.4049726
Published Online: February 19, 2021
View Article titled, The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments
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Topics: Filters, Iron, Neutrons, Silicon, Spectra (Spectroscopy), Neutron flux, Steel
Journal Articles

Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions

Zbyněk Hlaváč, Jaroslava Zatloukalová, Michal Košťál, Evžen Losa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 022001.
Paper No: NERS-20-1116
https://doi.org/10.1115/1.4048768
Published Online: October 30, 2020
View Article titled, Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions
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Topics: Concretes, Irradiation (Radiation exposure), Neutrons, Accidents, Neutron flux, Gamma rays, Radiation (Physics)
Journal Articles

Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

Petra Pónya, Gyula Csom, Sándor Fehér
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031110.
Paper No: NERS-19-1079
https://doi.org/10.1115/1.4046354
Published Online: June 5, 2020
View Article titled, Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel
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Topics: Coolants, Flow (Dynamics), Irradiation (Radiation exposure), Neutron flux, Neutrons, Reactor vessels, Supercritical water reactors, Design, Fuels, Temperature
Journal Articles

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021108.
Paper No: NERS-19-1059
https://doi.org/10.1115/1.4044910
Published Online: February 5, 2020
View Article titled, Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM
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Topics: Cross section (Physics), Fuels, Simulation, Temperature, Graphite, Neutron flux, Nuclear fission, Neutrons, High temperature, Flow (Dynamics)
Journal Articles

Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

I. K. Baidoo, J. Zou, B. Li, J. Song, B. Wu, Q. Yang, Z. Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041402.
Paper No: NERS-18-1123
https://doi.org/10.1115/1.4043100
Published Online: July 19, 2019
View Article titled, Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments
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Topics: Atoms, Displacement, Dosimetry, Fluence (Radiation measurement), Fuels, Geometry, Iron, Manufacturing, Modeling, Neutron flux
Journal Articles

The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations

Pan Qingquan, Lu Haoliang, Li Dongsheng, Wang Kan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021008.
Paper No: NERS-17-1079
https://doi.org/10.1115/1.4038653
Published Online: March 5, 2018
View Article titled, The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations
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Topics: Deformation, Diffusion (Physics), Eigenvalues, Neutron flux, Neutrons, Polynomials, Currents, Computational methods, Physics, Nuclear engineering
Journal Articles

Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs

Luigi Lepore, Romolo Remetti
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041018.
Paper No: NERS-17-1017
https://doi.org/10.1115/1.4037262
Published Online: July 31, 2017
View Article titled, Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs
Open the PDF for Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs in another window
Topics: Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Neutrons, Sensors, Signals, Simulation, Instrumentation
Journal Articles

Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Yuki Honda, Nozomu Fujimoto, Hiroaki Sawahata, Shoji Takada, Kazuhiro Sawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011005.
Paper No: NERS-15-1226
https://doi.org/10.1115/1.4033813
Published Online: December 20, 2016
View Article titled, Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor
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Topics: High temperature, Neutron flux, Rods, Fuels, Design, Temperature, Computational methods
Journal Articles

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Sanjeev Kumar, K. Obaidurrahman, Om Pal Singh, Prabhat Munshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011015.
Paper No: NERS-16-1007
https://doi.org/10.1115/1.4034478
Published Online: December 20, 2016
View Article titled, A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor
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Topics: Heat flux, Nucleate boiling, Pressurized water reactors, Rods, Safety, Scram, Spacetime, Thermal hydraulics, Transients (Dynamics), Temperature profiles
Journal Articles

On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED

Luigi Lepore, Romolo Remetti, Mauro Cappelli
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041002.
Paper No: NERS-15-1205
https://doi.org/10.1115/1.4033697
Published Online: October 12, 2016
View Article titled, On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED
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Topics: Instrumentation, Neutron flux, Neutrons, Sensors
Journal Articles

A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods

Alberto Sartori, Antonio Cammi, Lelio Luzzi, Gianluigi Rozza
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021019.
Paper No: NERS-14-1062
https://doi.org/10.1115/1.4031945
Published Online: February 29, 2016
View Article titled, A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods
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Topics: Eigenvalues, Errors, Modeling, Neutron flux, Nuclear reactors, Rods, Shapes, Approximation, Neutrons, Diffusion (Physics)