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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

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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031502.
Paper No: NERS-22-1040
DOI: 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
Click here to open pdf in another window PDF for Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL
Topics: Fuel management, Fuels, Cross section (Physics), Cycles
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

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

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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011503.
Paper No: NERS-21-1179
DOI: 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
Click here to open pdf in another window 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
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.
Paper No: NERS-21-1135
DOI: 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
Click here to open pdf in another window PDF for Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
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
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

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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011502.
Paper No: NERS-21-1143
DOI: 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
Click here to open pdf in another window 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
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011501.
Paper No: NERS-21-1139
DOI: 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
Click here to open pdf in another window 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
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
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031502.
Paper No: NERS-21-1117
DOI: 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
Click here to open pdf in another window 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
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
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

On the Self-Shielding in the Unresolved Resonance Range

Daniel Lopez Aldama, Andrej Trkov, Dermott E. Cullen
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041503.
Paper No: NERS-21-1026
DOI: https://doi.org/10.1115/1.4052377
Published Online: March 16, 2022
View Article titled, On the Self-Shielding in the Unresolved Resonance Range
Click here to open pdf in another window PDF for On the Self-Shielding in the Unresolved Resonance Range
Topics: Cross section (Physics), Resonance, Spectra (Spectroscopy), Probability, Leakage
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

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
Journal Articles

Preliminary Evaluation of the LASSO Method for Prediction of the Relative Power Density Distribution in Mixed Oxide (Pu, DU)O 2 Fuel Pellets

C. V. Anghel, B. P. Bromley, A. A. Prudil, M. J. Welland
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021502.
Paper No: NERS-20-1192
DOI: https://doi.org/10.1115/1.4050767
Published Online: October 19, 2021
View Article titled, Preliminary Evaluation of the LASSO Method for Prediction of the Relative Power Density Distribution in Mixed Oxide (Pu, DU)O 2 Fuel Pellets
Click here to open pdf in another window PDF for Preliminary Evaluation of the LASSO Method for Prediction of the Relative Power Density Distribution in Mixed Oxide (Pu, DU)O 2 Fuel Pellets
Topics: Fuels, Machine learning, Physics, Power density, Neutrons, Heavy water reactors
Includes: Supplementary data
Journal Articles

Canonical Implementation of Simplified Spherical Harmonics (SP L ) in the Neutron Diffusion Code AZNHEX

Guillermo Muñoz-Peña, Edmundo del Valle Gallegos, Armando Gomez-Torres
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031502.
Paper No: NERS-20-1114
DOI: https://doi.org/10.1115/1.4049277
Published Online: April 16, 2021
View Article titled, Canonical Implementation of Simplified Spherical Harmonics (SP L ) in the Neutron Diffusion Code AZNHEX
Click here to open pdf in another window PDF for Canonical Implementation of Simplified Spherical Harmonics (SP L ) in the Neutron Diffusion Code AZNHEX
Topics: Approximation, Diffusion (Physics), Neutrons
Journal Articles

Determination of CR-39 and LR-115 Type II Mean Critical Angle of Etching Using a New Monte Carlo Code

H. Harrass, A. Talbi, R. Touti
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031501.
Paper No: NERS-20-1061
DOI: https://doi.org/10.1115/1.4049343
Published Online: March 16, 2021
View Article titled, Determination of CR-39 and LR-115 Type II Mean Critical Angle of Etching Using a New Monte Carlo Code
Click here to open pdf in another window PDF for Determination of CR-39 and LR-115 Type II Mean Critical Angle of Etching Using a New Monte Carlo Code
Topics: Alpha particles, Etching, Sensors