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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

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

Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment

Abdullah G. Weiss, Laith J. Zaidan, Mohammad T. H. Bani Ahmad, M. Gomaa Abdoelatef, John W. Peterson, Alexander D. Lindsay, Fande Kong, Karim Ahmed, Mark L. Kimber
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021402.
Paper No: NERS-21-1170
https://doi.org/10.1115/1.4054685
Published Online: June 15, 2022
View Article titled, Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment
Open the PDF for Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment in another window
Topics: Computational fluid dynamics, Cylinders, Errors, Finite element analysis, Flow (Dynamics), Pressure, Simulation, Vortex street, Engineering simulation, Physics
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
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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

Validating the serpent-ants Calculation Chain Using BEAVRS Fresh Core Hot Zero Power Data

Ville Valtavirta, Antti Rintala, Unna Lauranto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044504.
Paper No: NERS-21-1020
https://doi.org/10.1115/1.4052731
Published Online: March 16, 2022
View Article titled, Validating the serpent-ants Calculation Chain Using BEAVRS Fresh Core Hot Zero Power Data
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Topics: Boron, Chain, Manufacturing, Errors, Temperature, Fuels, Physics
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
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021502.
Paper No: NERS-20-1192
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
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Topics: Fuels, Machine learning, Physics, Power density, Neutrons, Heavy water reactors
Includes: Supplementary data
Journal Articles

European Research Program on Supercritical Water-Cooled Reactor

M. Kryková, T. Schulenberg, M. Arnoult Růžičková, A. Sáez-Maderuelo, I. Otic, S. Czifrus, L. Cizelj, G. L. Pavel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021301.
Paper No: NERS-20-1090
https://doi.org/10.1115/1.4048901
Published Online: November 16, 2020
View Article titled, European Research Program on Supercritical Water-Cooled Reactor
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Topics: Design, Safety, Small modular reactors, Supercritical water reactors, Water, Corrosion, Thermal hydraulics, Physics
Journal Articles

The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors

M. D. Tucker, D. R. Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031401.
Paper No: NERS-19-1065
https://doi.org/10.1115/1.4045485
Published Online: March 9, 2020
View Article titled, The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors
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Topics: Algorithms, Cross section (Physics), Feedback, Fuels, Simulation, Uncertainty, Uncertainty analysis, Uranium, Physics, Diffusion (Physics)
Journal Articles

Theoretical Development of Cross Section Uncertainty Library for Core Simulators

Dongli Huang, Hany S. Abdel-Khalik
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011103.
Paper No: NERS-18-1133
https://doi.org/10.1115/1.4045031
Published Online: November 8, 2019
View Article titled, Theoretical Development of Cross Section Uncertainty Library for Core Simulators
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Topics: Physics, Uncertainty, Simulation
Journal Articles

Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion

Kevin Schillo, Jason Cassibry, Mitchell Rodriguez, Seth Thompson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 042201.
Paper No: NERS-18-1025
https://doi.org/10.1115/1.4042710
Published Online: July 19, 2019
View Article titled, Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion
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Topics: Heat conduction, Particulate matter, Plasmas (Ionized gases), Pressure, Radiation (Physics), Shock (Mechanics), Simulation, Temperature, Viscosity, Vortices
Journal Articles

Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model

Xiong Wenbin, Cao Jian, Huang Chaoyun, Bie Yewang, Wang Yanqi, Li Jufeng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031018.
Paper No: NERS-17-1132
https://doi.org/10.1115/1.4039596
Published Online: May 16, 2018
View Article titled, Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model
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Topics: Design, Fuels, Rods, Manufacturing, Nuclear power stations, Modeling, Boron, Physics
Journal Articles

Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations

F. Salaun, D. R. Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021003.
Paper No: NERS-17-1010
https://doi.org/10.1115/1.4038557
Published Online: March 5, 2018
View Article titled, Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations
Open the PDF for Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations in another window
Topics: Blades, Cycles, Design, Fuels, Optimization, Physics, Supercritical water reactors, Temperature, Thermal hydraulics, Coolants
Journal Articles

Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

Jian Li, Ding She, Lei Shi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021007.
Paper No: NERS-17-1089
https://doi.org/10.1115/1.4038771
Published Online: March 5, 2018
View Article titled, Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code
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Topics: Algorithms, Chain, Errors, Nuclides, Polynomial approximation, Physics
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

Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria

Andrea Alfonsi, George L. Mesina, Angelo Zoino, Nolan Anderson, Cristian Rabiti
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020906.
Paper No: NERS-16-1120
https://doi.org/10.1115/1.4035851
Published Online: March 1, 2017
View Article titled, Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria
Open the PDF for Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria in another window
Topics: Accidents, Cladding systems (Building), Coolants, Cycles, Design, Flow (Dynamics), Fuels, Nuclear fuel cycle, Oxidation, Safety
Journal Articles

Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the 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): 011013.
Paper No: NERS-15-1220
https://doi.org/10.1115/1.4033812
Published Online: December 20, 2016
View Article titled, Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor
Open the PDF for Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor in another window
Topics: Evaluation methods, High temperature, Temperature, Design, Cycles, Temperature distribution, Physics, Very high temperature reactors
Journal Articles

Global Neutron Calculations, by M. Makai, D. P. Kis, and J. Vegh. Bentham Science Publishers Ltd., UAE, 2015, 552 pp., eISBN 978-1-68108-027-7, ISBN978-1-68108-028-4.

DUMITRU SERGHIUTA
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Book Reviews
ASME J of Nuclear Rad Sci. July 2016, 2(3): 036501.
Paper No: NERS-16-1043
https://doi.org/10.1115/1.4033479
Published Online: June 17, 2016
View Article titled, Global Neutron Calculations, by M. Makai, D. P. Kis, and J. Vegh. Bentham Science Publishers Ltd., UAE, 2015, 552 pp., eISBN 978-1-68108-027-7, ISBN978-1-68108-028-4.
Open the PDF for Global Neutron Calculations, by M. Makai, D. P. Kis, and J. Vegh. Bentham Science Publishers Ltd., UAE, 2015, 552 pp., eISBN 978-1-68108-027-7, ISBN978-1-68108-028-4. in another window
Topics: Neutrons, Nuclear engineering, Physics, Transport theory
Journal Articles

Editorial

Igor L. Pioro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Editorial
ASME J of Nuclear Rad Sci. January 2015, 1(1): 010201.
Paper No: NERS-14-1055
https://doi.org/10.1115/1.4029141
Published Online: February 9, 2015
View Article titled, Editorial
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Topics: China, Design, Nuclear engineering, Nuclear fuel cycle, Nuclear power, Nuclear power stations, Nuclear reactors, Physics, Radiation (Physics), Risk