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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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041501.
Paper No: NERS-22-1145
DOI: 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
Click here to open pdf in another window PDF for Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031503.
Paper No: NERS-21-1114
DOI: 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
Click here to open pdf in another window PDF for Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032004.
Paper No: NERS-22-1046
DOI: 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
Click here to open pdf in another window PDF for Theoretical Investigation of the Gamma and Neutron Interaction Parameters of Some Inorganic Scintillators Using Phy-X/PSD and NGCal Software
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031501.
Paper No: NERS-22-1022
DOI: 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
Click here to open pdf in another window PDF for Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000
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
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2023, 9(3): 034501.
Paper No: NERS-22-1039
DOI: 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
Click here to open pdf in another window PDF for Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor
Topics: Fluence (Radiation measurement), Irradiation (Radiation exposure), Isotopes, Neutrons, Zirconium
Journal Articles

Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252 Cf Source in Center

Tomáš Czakoj, Michal Košťál, Martin Schulc, Vojtěch Rypar, Evžen Novák, Evžen Losa
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032001.
Paper No: NERS-22-1038
DOI: https://doi.org/10.1115/1.4056508
Published Online: February 8, 2023
View Article titled, Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252 Cf Source in Center
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Topics: Copper, Leakage, Neutrons, Uncertainty, Spectra (Spectroscopy), Neutron sources
Journal Articles

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC

Accepted Manuscript
Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-22-1137
DOI: https://doi.org/10.1115/1.4056772
Published Online: January 1, 2023
View Article titled, Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC
Click here to open pdf in another window PDF for Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC
Topics: Design, Supercritical carbon dioxide, Coolants, Feedback, Diluents, Fuels, Leakage, Neutrons, Cross section (Physics), Nuclear fission
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011504.
Paper No: NERS-22-1009
DOI: 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
Click here to open pdf in another window PDF for Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors
Topics: Fuels, Uranium, Neutrons
Journal Articles

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

Rofida Hamad Khlifa, Nicolay N. Nikitenkov
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012003.
Paper No: NERS-22-1044
DOI: https://doi.org/10.1115/1.4055012
Published Online: September 1, 2022
View Article titled, Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating
Click here to open pdf in another window PDF for Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating
Topics: Boron, Coatings, Fuels, Temperature, Cladding systems (Building), Neutrons, Accidents
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041505.
Paper No: NERS-21-1013
DOI: 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
Click here to open pdf in another window PDF for Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector
Topics: Graphite, Neutron flux, Neutrons, Sensors, Spent nuclear fuels, Water, Fuels
Journal Articles

Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites

A. M. Osman
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012002.
Paper No: NERS-21-1171
DOI: https://doi.org/10.1115/1.4054547
Published Online: June 7, 2022
View Article titled, Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites
Click here to open pdf in another window PDF for Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites
Topics: Composite materials, Density, Neutrons, Polymer composites, Relaxation (Physics), Photons, Cross section (Physics), Aluminum, Boron
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
Article Type: Technical Briefs
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
Click here to open pdf in another window PDF for Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping
Topics: Irradiation (Radiation exposure), Neutron flux, Neutrons, Silicon
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031501.
Paper No: NERS-21-1118
DOI: 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
Click here to open pdf in another window 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
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041504.
Paper No: NERS-21-1007
DOI: 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
Click here to open pdf in another window PDF for Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor
Topics: Flux (Metallurgy), Irradiation (Radiation exposure), Neutrons, Neutron activation analysis, Uncertainty
Journal Articles

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Davor Grgić, Mario Matijević, Paulina Dučkić, Radomir Ječmenica
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041902.
Paper No: NERS-21-1029
DOI: https://doi.org/10.1115/1.4051447
Published Online: March 16, 2022
View Article titled, Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One
Click here to open pdf in another window PDF for Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One
Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041502.
Paper No: NERS-21-1010
DOI: 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
Click here to open pdf in another window PDF for Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation
Topics: Fuels, Nuclear fission, Uncertainty, Water, Nuclides, Neutrons
Journal Articles

Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System

Marjan Kromar, Bojan Kurinčič
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041501.
Paper No: NERS-21-1014
DOI: https://doi.org/10.1115/1.4050991
Published Online: March 15, 2022
View Article titled, Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System
Click here to open pdf in another window PDF for Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System
Topics: Boron, Cycles, Fuels, Manufacturing, Neutrons, Nuclear design, Nuclear power stations, Nuclear fission, Cross section (Physics), Rods
Journal Articles

serpent 2 Validation for Radiation Shielding Applications

Silja Häkkinen
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 042001.
Paper No: NERS-21-1009
DOI: https://doi.org/10.1115/1.4051614
Published Online: March 15, 2022
View Article titled, serpent 2 Validation for Radiation Shielding Applications
Click here to open pdf in another window PDF for serpent 2 Validation for Radiation Shielding Applications
Topics: Iron, Neutrons, Photons, Spectra (Spectroscopy)
Journal Articles

A Short Inroad to Optimized Compactification of Composite Neutronic Shields

Nassar H. S. Haidar
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
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
Click here to open pdf in another window PDF for A Short Inroad to Optimized Compactification of Composite Neutronic Shields
Topics: Composite materials, Design, Neutrons, Optimization, Neutron beams, Diffusion (Physics), Weight (Mass)
Journal Articles

Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium

D. Ray, S. P. Saraswat, M. Kumar, O. P. Singh, P. Munshi
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021501.
Paper No: NERS-20-1150
DOI: https://doi.org/10.1115/1.4049727
Published Online: October 19, 2021
View Article titled, Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium
Click here to open pdf in another window PDF for Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium
Topics: Density, Neutrons, Steady state, Transients (Dynamics), Waves