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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

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031301.

Paper No: NERS-22-1119

DOI: https://doi.org/10.1115/1.4056930

Published Online: March 13, 2023

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Topics: Coolants, Density, Feedback, Fuels, Sodium fast reactors, Temperature, Thermal expansion, Manufacturing, Electrical conductance, Heat

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

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.

Paper No: NERS-21-1158

DOI: https://doi.org/10.1115/1.4056463

Published Online: February 8, 2023

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Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium fast reactors, Temperature, Temperature distribution, Thermal hydraulics, Wire, Fuel rods

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

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

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Topics: Fuels, Cycles, Neutron flux, Neutrons, Manufacturing

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

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011402.

Paper No: NERS-22-1028

DOI: https://doi.org/10.1115/1.4054943

Published Online: July 19, 2022

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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031601.

Paper No: NERS-21-1184

DOI: https://doi.org/10.1115/1.4053829

Published Online: June 1, 2022

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Topics: Fuels, Manufacturing, Temperature, Water

Journal Articles

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

B. Mikuž, F. Roelofs

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041402.

Paper No: NERS-21-1021

DOI: https://doi.org/10.1115/1.4051446

Published Online: March 22, 2022

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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

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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041401.

Paper No: NERS-21-1012

DOI: https://doi.org/10.1115/1.4051515

Published Online: March 22, 2022

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Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)

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

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

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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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 044504.

Paper No: NERS-21-1020

DOI: https://doi.org/10.1115/1.4052731

Published Online: March 16, 2022

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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

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

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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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.

Paper No: NERS-21-1015

DOI: https://doi.org/10.1115/1.4051444

Published Online: March 15, 2022

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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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 044503.

Paper No: NERS-21-1019

DOI: https://doi.org/10.1115/1.4051445

Published Online: March 15, 2022

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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

ASME J of Nuclear Rad Sci. October 2021, 7(4): 042008.

Paper No: NERS-20-1105

DOI: https://doi.org/10.1115/1.4051874

Published Online: August 20, 2021

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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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011307.

Paper No: NERS-20-1183

DOI: https://doi.org/10.1115/1.4050417

Published Online: August 3, 2021

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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

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041901.

Paper No: NERS-20-1091

DOI: https://doi.org/10.1115/1.4050296

Published Online: April 22, 2021

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031603.

Paper No: NERS-20-1064

DOI: https://doi.org/10.1115/1.4048764

Published Online: March 16, 2021

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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

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041111.

Paper No: NERS-19-1167

DOI: https://doi.org/10.1115/1.4047162

Published Online: September 4, 2020

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Topics: Fuels, Manufacturing, Simulation, Transients (Dynamics), Temperature, Uncertainty, Pressure

Journal Articles

Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR

A. Nava-Dominguez

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031113.

Paper No: NERS-19-1082

DOI: https://doi.org/10.1115/1.4046783

Published Online: June 5, 2020

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Topics: Flow (Dynamics), Friction, Pressure drop, Wire, Fuels, Water, Supercritical water reactors, Manufacturing, Pipes

Journal Articles

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

A. Nava Domínguez, Y. F. Rao, T. Beuthe

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031114.

Paper No: NERS-19-1083

DOI: https://doi.org/10.1115/1.4046843

Published Online: June 5, 2020

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Topics: Cladding systems (Building), Coolants, Flow (Dynamics), Fuels, Heat losses, Heat transfer, Manufacturing, Supercritical water reactors, Temperature, Modeling

Journal Articles

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

Attila Kiss, Béla Hegyesi, Patrik Richárd Ujváry, András Szabolcs Ványi, Gyula Csom

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031108.

Paper No: NERS-19-1070

DOI: https://doi.org/10.1115/1.4046904

Published Online: June 5, 2020

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Topics: Computational fluid dynamics, Flow (Dynamics), Fluids, Fuels, Manufacturing, Supercritical water reactors, Temperature, Fuel rods, Boundary-value problems, Wire

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Journal citation

NARROW

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

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

Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

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