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Journal Articles

TSUNAMI Analyses of the Similarity and Applicability of ZED-2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor (PWR-SMR) Design Concept

Accepted Manuscript
Eugene Masala, Laura Blomeley, David G. Watts, Blair Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1016
https://doi.org/10.1115/1.4066404
Published Online: September 2, 2024
View Article titled, TSUNAMI Analyses of the Similarity and Applicability of ZED-2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor (PWR-SMR) Design Concept
Open the PDF for TSUNAMI Analyses of the Similarity and Applicability of ZED-2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor (PWR-SMR) Design Concept in another window
Topics: Design, Physics, Pressurized water reactors, Small modular reactors, Tsunamis, Fuels, Water, Boron, Gadolinium, Manufacturing
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

Performance of Borated Centrifugally Tensioned Metastable Fluid Detector Versus Ludlum 42-49B, Fuji NSN3 Detectors for Fission Energy Spectrum Neutron Detection With the Source Within Lead/Concrete Shielded Configurations

Yusuke Ota, Rusi P. Taleyarkhan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 042002.
Paper No: NERS-24-1036
https://doi.org/10.1115/1.4065853
Published Online: July 16, 2024
View Article titled, Performance of Borated Centrifugally Tensioned Metastable Fluid Detector Versus Ludlum 42-49B, Fuji NSN3 Detectors for Fission Energy Spectrum Neutron Detection With the Source Within Lead/Concrete Shielded Configurations
Open the PDF for Performance of Borated Centrifugally Tensioned Metastable Fluid Detector Versus Ludlum 42-49B, Fuji NSN3 Detectors for Fission Energy Spectrum Neutron Detection With the Source Within Lead/Concrete Shielded Configurations in another window
Topics: Concretes, Fluids, Neutrons, Sensors, Nuclear fission
Journal Articles

Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations

Yusuke Ota, Stepan Ozerov, Rusi P. Taleyarkhan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 042001.
Paper No: NERS-24-1035
https://doi.org/10.1115/1.4065852
Published Online: July 16, 2024
View Article titled, Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations
Open the PDF for Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations in another window
Topics: Concretes, Fluids, Neutrons, Sensors, Particulate matter, Neutron sources, Nuclear fission, Spectra (Spectroscopy), Simulation
Journal Articles

Practical Approach to Nuclear Shelter Wall Thickness Estimation

Rayna Hristova, Stefan Simovski
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. October 2024, 10(4): 040802.
Paper No: NERS-23-1103
https://doi.org/10.1115/1.4065463
Published Online: June 17, 2024
View Article titled, Practical Approach to Nuclear Shelter Wall Thickness Estimation
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Topics: Concretes, Gamma rays, Neutrons, Nuclear fission, Wall thickness, Bombs
Journal Articles

Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology

C. Harabagiu, R. P. Taleyarkhan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041601.
Paper No: NERS-23-1119
https://doi.org/10.1115/1.4065280
Published Online: May 10, 2024
View Article titled, Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology
Open the PDF for Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology in another window
Topics: Fluids, Neutrons, Sensors, Emissions, Photons, Spent nuclear fuels
Journal Articles

Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

R. Andika Putra Dwijayanto, Harun Ardiansyah, Andang Widi Harto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031301.
Paper No: NERS-23-1088
https://doi.org/10.1115/1.4064465
Published Online: April 17, 2024
View Article titled, Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
Open the PDF for Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume in another window
Topics: Fluids, Fuels, Geometry, Molten salt reactors, Neutrons, Optimization, Temperature
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
Open the PDF for Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor in another window
Topics: Control systems, Design, Fast neutron reactors, Fuels, Neutrons, Rods, Coolants, Boron, Absorption, Safety
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
Open the PDF for Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly in another window
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
Open the PDF for A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset in another window
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
Open the PDF for Special Experimental Environment for Generation IV Reactors With Graphite Reflector in another window
Topics: Graphite, Neutron flux, Neutrons, Fuels
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

9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors

Nathan Boyle, Stepan Ozerov, Catalin Harabagiu, Rusi P. Taleyarkhan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 042001.
Paper No: NERS-23-1033
https://doi.org/10.1115/1.4062951
Published Online: September 15, 2023
View Article titled, 9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors
Open the PDF for 9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors in another window
Topics: Acoustics, Fluids, Neutrons, Photons, Sensors, Vacuum, Uranium, X-rays
Journal Articles

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041103.
Paper No: NERS-22-1137
https://doi.org/10.1115/1.4056772
Published Online: May 31, 2023
View Article titled, Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
Open the PDF for Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code in another window
Topics: Coolants, Design, Diluents, Fuels, Leakage, Neutrons, Supercritical carbon dioxide, Nuclear fission, Nuclides, Feedback
Journal Articles

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104.
Paper No: NERS-22-1145
https://doi.org/10.1115/1.4062119
Published Online: April 17, 2023
View Article titled, Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
Open the PDF for Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel in another window
Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter, Temperature, Coolants, Neutrons, Heat transfer, Computer software
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
Open the PDF for Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors in another window
Topics: Diffusion (Physics), Finite element methods, Neutron flux, Neutrons, Computation, Finite element model
Journal Articles

Theoretical Investigation of the Gamma and Neutron Interaction Parameters of Some Inorganic Scintillators Using Phy-X/PSD and NGCal Software

G. B. Hiremath, M. M. Hosamani, V. P. Singh, N. H. Ayachit, N. M. Badiger
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032004.
Paper No: NERS-22-1046
https://doi.org/10.1115/1.4056835
Published Online: February 22, 2023
View Article titled, Theoretical Investigation of the Gamma and Neutron Interaction Parameters of Some Inorganic Scintillators Using Phy-X/PSD and NGCal Software
Open the PDF for Theoretical Investigation of the Gamma and Neutron Interaction Parameters of Some Inorganic Scintillators Using Phy-X/PSD and NGCal Software in another window
Topics: Absorption, Atomic number, Computer software, Neutrons, Photons, Radiation (Physics)
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

Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor

Xiaolin Wang, Youqing Shi, Grant Bickel, DeAbreu Robert
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2023, 9(3): 034501.
Paper No: NERS-22-1039
https://doi.org/10.1115/1.4055931
Published Online: February 8, 2023
View Article titled, Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor
Open the PDF for Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor in another window
Topics: Fluence (Radiation measurement), Irradiation (Radiation exposure), Isotopes, Neutrons, Zirconium