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Journal Articles

Experimental Investigation of Control Rod Drops Into Perturbed Fuel Assemblies

Namgyu Park, Ohjoon Kwon, Youngik Yoo, Taesoon Kim
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
Publisher: ASME
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041801.
Paper No: NERS-23-1003
https://doi.org/10.1115/1.4062275
Published Online: September 15, 2023
View Article titled, Experimental Investigation of Control Rod Drops Into Perturbed Fuel Assemblies
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Topics: Deformation, Fuels, Manufacturing, Impact testing, Buckling
Journal Articles

Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates with Zircaloy Cladding

Accepted Manuscript
Hakan Ozaltun, James I. Cole, Barry H. Rabin
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1048
https://doi.org/10.1115/1.4063163
Published Online: August 11, 2023
View Article titled, Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates with Zircaloy Cladding
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Topics: Cladding systems (Building), Fuels, Plates (structures), Thermomechanics, Stress, Aluminum alloys, Irradiation (Radiation exposure), Aluminum, Deformation, Engineering simulation
Journal Articles

Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications

Accepted Manuscript
Abhishek Saraswat, Rajendraprasad Bhattacharyay, Paritosh Chaudhuri, Sateesh Gedupudi
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-23-1007
https://doi.org/10.1115/1.4062646
Published Online: May 27, 2023
View Article titled, Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications
Open the PDF for Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications in another window
Topics: Coatings, Flow (Dynamics), High temperature, Liquid metals, Manufacturing, Performance characterization, Insulation, Coolants, Corrosion, Fusion reactors
Journal Articles

Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution

Ben Lindley, Francisco Álvarez Velarde, Una Baker, Janos Bodi, Paul Cosgrove, Alan Charles, Carlo Fiorina, Emil Fridman, Jiri Krepel, Jean Lavarenne, Konstantin Mikityuk, Evgeny Nikitin, Alexander Ponomarev, Stefan Radman, Eugene Shwageraus, Brendan Tollit
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031301.
Paper No: NERS-22-1119
https://doi.org/10.1115/1.4056930
Published Online: March 13, 2023
View Article titled, Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
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Topics: Coolants, Density, Feedback, Fuels, Sodium fast reactors, Temperature, Thermal expansion, Manufacturing, Electrical conductance, Heat
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
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
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Topics: Fuels, Cycles, Neutron flux, Neutrons, Manufacturing
Journal Articles

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.
Paper No: NERS-21-1158
https://doi.org/10.1115/1.4056463
Published Online: February 8, 2023
View Article titled, Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor
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Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium fast reactors, Temperature, Temperature distribution, Thermal hydraulics, Wire, Fuel rods
Journal Articles

Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels

Chenguang Li, Krishna Podila, Blair P. Bromley, Yanfei Rao
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011402.
Paper No: NERS-22-1028
https://doi.org/10.1115/1.4054943
Published Online: July 19, 2022
View Article titled, Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels
Open the PDF for Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels in another window
Topics: Computational fluid dynamics, Fuels, Modeling, Pressure, Pressurized water reactors, Manufacturing, Flow (Dynamics), Small modular reactors
Journal Articles

Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels

Ayman M. Bayomy, Blair P. Bromley, Armando Nava Dominguez, Samuel Kelly
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031601.
Paper No: NERS-21-1184
https://doi.org/10.1115/1.4053829
Published Online: June 1, 2022
View Article titled, Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels
Open the PDF for Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels in another window
Topics: Fuels, Manufacturing, Temperature, Water
Journal Articles

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Filip Osuský, Branislav Vrban, Štefan Čerba, Jakub Lüley, Vladimír Nečas
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041401.
Paper No: NERS-21-1012
https://doi.org/10.1115/1.4051515
Published Online: March 22, 2022
View Article titled, Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code
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Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)
Journal Articles

Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS

B. Mikuž, F. Roelofs
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041402.
Paper No: NERS-21-1021
https://doi.org/10.1115/1.4051446
Published Online: March 22, 2022
View Article titled, Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS
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Topics: Flow (Dynamics), Fuel rods, Fuels, Manufacturing, Pressure drop, Pressurized water reactors, Temperature, Simulation, Reynolds-averaged Navier–Stokes equations, Turbulence
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
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

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
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
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Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing
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
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
Open the 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 in another window
Topics: Boron, Cycles, Fuels, Manufacturing, Neutrons, Nuclear design, Nuclear power stations, Nuclear fission, Cross section (Physics), Rods
Journal Articles

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

Silja Häkkinen
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.
Paper No: NERS-21-1015
https://doi.org/10.1115/1.4051444
Published Online: March 15, 2022
View Article titled, Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2
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Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons
Journal Articles

The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term

Riku Tuominen, Ville Valtavirta
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044503.
Paper No: NERS-21-1019
https://doi.org/10.1115/1.4051445
Published Online: March 15, 2022
View Article titled, The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term
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Topics: Boiling water reactors, Emissions, Heat, Manufacturing, Nuclear fission, Photons, Probability, Resonance, Spent nuclear fuels, Nuclides
Journal Articles

A Collaborative Experience: Implementation of an Optimized Tc-99m Generator Assembly Process

Rijata Sharma, Bronte Sial, Henry Lake, Prashant Maharaj, Joshua Reus-Smit, Andrew Popp
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 042008.
Paper No: NERS-20-1105
https://doi.org/10.1115/1.4051874
Published Online: August 20, 2021
View Article titled, A Collaborative Experience: Implementation of an Optimized Tc-99m Generator Assembly Process
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Topics: Contamination, Generators, Manufacturing, Risk, Skin
Journal Articles

Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

Janos Bodi, Alexander Ponomarev, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011307.
Paper No: NERS-20-1183
https://doi.org/10.1115/1.4050417
Published Online: August 3, 2021
View Article titled, Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor
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Topics: Deformation, Displacement, Finite element analysis, Geometry, Manufacturing, Sodium fast reactors, Fuels, Simulation, Absorption
Journal Articles

Backfill of Radioactive Waste Disposal: Feasibility Study of Argillite/Bentonite (COx/MX80) Pellets

Danai Tyri, Bui Quoc Huy Ly, François Nader, Irini Djeran-Maigre, Jean-Claude Robinet, Jad Zghondi
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041901.
Paper No: NERS-20-1091
https://doi.org/10.1115/1.4050296
Published Online: April 22, 2021
View Article titled, Backfill of Radioactive Waste Disposal: Feasibility Study of Argillite/Bentonite (COx/MX80) Pellets
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Topics: Density, Pelletizing, Water, Machinery, Manufacturing, Stress, Optimization
Journal Articles

Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES

Muhammad Imron, Donny Hartanto
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031603.
Paper No: NERS-20-1064
https://doi.org/10.1115/1.4048764
Published Online: March 16, 2021
View Article titled, Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES
Open the PDF for Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES in another window
Topics: Boron, Coordinate measuring machines, Cross section (Physics), Fuels, Manufacturing, Pressurized water reactors, Transients (Dynamics), Temperature, Diffusion (Physics), Geometry
Journal Articles

Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data

Jason J. Song, Paul K. Chan, Hugues W. Bonin, Mahesh Pandey
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041111.
Paper No: NERS-19-1167
https://doi.org/10.1115/1.4047162
Published Online: September 4, 2020
View Article titled, Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data
Open the PDF for Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data in another window
Topics: Fuels, Manufacturing, Simulation, Transients (Dynamics), Temperature, Uncertainty, Pressure