1-20 of 58
Manufacturing
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Journal Articles

Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

Accepted Manuscript
Armando Nava Dominguez, Xianmin Huang, Songyu Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1028
https://doi.org/10.1115/1.4066523
Published Online: September 13, 2024
View Article titled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
Open the PDF for Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications in another window
Topics: Computers, Fuels, Manufacturing, Nuclear fuels, Nuclear industry, Supercritical fluids, Water
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

Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods

Daniel T. Wojtaszek, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031302.
Paper No: NERS-23-1090
https://doi.org/10.1115/1.4064581
Published Online: April 17, 2024
View Article titled, Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods
Open the PDF for Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods in another window
Topics: Fuels, Hydrogen, Temperature, Very high temperature reactors, Uranium, Manufacturing
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

Abhishek Saraswat, Rajendraprasad Bhattacharyay, Paritosh Chaudhuri, Sateesh Gedupudi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030902.
Paper No: NERS-23-1007
https://doi.org/10.1115/1.4062646
Published Online: March 8, 2024
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, Engineering prototypes, Flow (Dynamics), High temperature, Insulation, Liquid metals, Magnetohydrodynamics, Manufacturing, Pressure, Welding
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

NED Chair's Message

Asif Arastu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2024, 10(1): 010301.
Paper No: NERS-23-1108
https://doi.org/10.1115/1.4063844
Published Online: December 8, 2023
View Article titled, NED Chair's Message
Open the PDF for NED Chair's Message in another window
Topics: Nuclear engineering, Radiation (Physics), Safety, Radioactive wastes, Environmental remediation, Nuclear decommissioning, Carbon neutrality, Computer security, Decontamination, Education
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
Publisher: ASME
Article Type: Research-Article
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
Open the PDF for Experimental Investigation of Control Rod Drops Into Perturbed Fuel Assemblies in another window
Topics: Deformation, Fuels, Manufacturing, Impact testing, Buckling
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
Publisher: ASME
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
Open the PDF for Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution in another window
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
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

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
Publisher: ASME
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
Open the PDF for Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor in another window
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
Publisher: ASME
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
Publisher: ASME
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
Publisher: ASME
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
Open the PDF for Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code in another window
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
Publisher: ASME
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
Open the PDF for Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS in another window
Topics: Flow (Dynamics), Fuel rods, Fuels, Manufacturing, Pressure drop, Pressurized water reactors, Temperature, Simulation, Reynolds-averaged Navier–Stokes equations, Turbulence
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
Publisher: ASME
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
Open the 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 in another window
Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing
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
Open the PDF for Validating the serpent-ants Calculation Chain Using BEAVRS Fresh Core Hot Zero Power Data in another window
Topics: Boron, Chain, Manufacturing, Errors, Temperature, Fuels, Physics
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
Publisher: ASME
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

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
Publisher: ASME
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
Open the PDF for The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term in another window
Topics: Boiling water reactors, Emissions, Heat, Manufacturing, Nuclear fission, Photons, Probability, Resonance, Spent nuclear fuels, Nuclides
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
Publisher: ASME
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
Open the PDF for Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2 in another window
Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons