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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

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 Article titled, 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

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
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

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

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 Article titled, 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

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

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 Article titled, 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

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

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

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 Article titled, 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
Journal Articles

On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave

Nassar H. S. Haidar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021501.
Paper No: NERS-23-1061
https://doi.org/10.1115/1.4063291
Published Online: October 20, 2023
View Article titled, On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave
Open the PDF for On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave in another window
Topics: Density, Neutrons, Transfer functions, Waves
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
Open the PDF for Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000 in another window
Topics: Fuels, Cycles, Neutron flux, Neutrons, Manufacturing
Journal Articles

Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL

Surian Pinem, Donny Hartanto, Peng Hong Liem, Wahid Luthfi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031502.
Paper No: NERS-22-1040
https://doi.org/10.1115/1.4056603
Published Online: February 8, 2023
View Article titled, Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL
Open the PDF for Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL in another window
Topics: Fuel management, Fuels, Cross section (Physics), Cycles
Journal Articles

Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors

Daniel T. Wojtaszek, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011504.
Paper No: NERS-22-1009
https://doi.org/10.1115/1.4055009
Published Online: September 13, 2022
View Article titled, Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors
Open the PDF for Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors in another window
Topics: Fuels, Uranium, Neutrons
Journal Articles

Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors

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. January 2023, 9(1): 011503.
Paper No: NERS-21-1179
https://doi.org/10.1115/1.4054841
Published Online: September 1, 2022
View Article titled, Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors
Open the PDF for Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors in another window
Topics: Fuels, Heavy water reactors, Uranium
Journal Articles

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.
Paper No: NERS-21-1135
https://doi.org/10.1115/1.4053827
Published Online: June 15, 2022
View Article titled, Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
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Topics: Design, Vessels, Cycles, Fuels, Temperature, Fast neutron reactors, Small modular reactors
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

Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes

Thanh Mai Vu, Donny Hartanto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011502.
Paper No: NERS-21-1143
https://doi.org/10.1115/1.4054080
Published Online: June 7, 2022
View Article titled, Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes
Open the PDF for Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes in another window
Topics: Cermets, Uncertainty, Ceramics
Journal Articles

Neutronic Evaluation of Light Water Reactor-Based Small Modular Reactor With Transuranic Fuel and Comparison With Different Core Configuration of UO 2 and Mixed Oxide Fuel

Sushanta Biswas, Md. Hossain Sahadath, Nazia Rahim Ananya
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011501.
Paper No: NERS-21-1139
https://doi.org/10.1115/1.4054208
Published Online: June 7, 2022
View Article titled, Neutronic Evaluation of Light Water Reactor-Based Small Modular Reactor With Transuranic Fuel and Comparison With Different Core Configuration of UO 2 and Mixed Oxide Fuel
Open the PDF for Neutronic Evaluation of Light Water Reactor-Based Small Modular Reactor With Transuranic Fuel and Comparison With Different Core Configuration of UO 2 and Mixed Oxide Fuel in another window
Topics: Atoms, Fuels, Nuclear fission
Journal Articles

Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor

T. Sinh Nguyen, Xiaolin Wang, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031502.
Paper No: NERS-21-1117
https://doi.org/10.1115/1.4053691
Published Online: June 1, 2022
View Article titled, Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor
Open the PDF for Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor in another window
Topics: Fuels, Physics, Irradiation (Radiation exposure)
Journal Articles

Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

D. G. Watts, F. P. Adams, E. Masala, L. Blomeley, B. P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031501.
Paper No: NERS-21-1118
https://doi.org/10.1115/1.4054079
Published Online: May 26, 2022
View Article titled, Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels
Open the PDF for Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels in another window
Topics: Fuels, Modeling, Physics, Pressurized water reactors, Water, Neutrons, High temperature
Journal Articles

Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor

Radojko Jaćimović, Maria Ângela de Barros Correia Menezes
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041504.
Paper No: NERS-21-1007
https://doi.org/10.1115/1.4051249
Published Online: March 22, 2022
View Article titled, Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor
Open the PDF for Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor in another window
Topics: Flux (Metallurgy), Irradiation (Radiation exposure), Neutrons, Neutron activation analysis, Uncertainty
Journal Articles

Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation

Branislav Vrban, Štefan Čerba, Jakub Lüley, Filip Osuský, Vladimír Nečas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041502.
Paper No: NERS-21-1010
https://doi.org/10.1115/1.4051613
Published Online: March 16, 2022
View Article titled, Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation
Open the PDF for Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation in another window
Topics: Fuels, Nuclear fission, Uncertainty, Water, Nuclides, Neutrons