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Journal Articles

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1137

DOI: https://doi.org/10.1115/1.4056772

Published Online: January 1, 2023

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Topics: Design, Supercritical carbon dioxide, Coolants, Feedback, Diluents, Fuels, Leakage, Neutrons, Cross section (Physics), Nuclear fission

Journal Articles

Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Kazuo Yoshimura, Norihiro Doda, Kennichi Igawa, Masaaki Tanaka, Hidemasa Yamano

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021601.

Paper No: NERS-21-1160

DOI: https://doi.org/10.1115/1.4055328

Published Online: December 14, 2022

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Topics: Feedback, Sodium fast reactors, Temperature, Fuels, Sensitivity analysis, Density, Heat, Heat sinks, Dynamics (Mechanics), Coolants

Journal Articles

Machine Learning Metamodel of a Computationally Intense Accident Simulation Code

Landon A Conner, Clarence Worrell, Jun Liao, James P. Spring, Reza A. Karimi, Jeremy Marquardt, Joseph D. Wieder

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1002

DOI: https://doi.org/10.1115/1.4056465

Published Online: December 13, 2022

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Topics: Accidents, Machine learning, Simulation, Artificial neural networks, Manufacturing, Optimization, Safety, Approximation, Coolants, Decision analysis

Journal Articles

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

Benjamin Blaisot, Emmanuel Porcheron, Olivier Praud, Véronique Roig

ASME J of Nuclear Rad Sci. July 2022, 8(3): 032301.

Paper No: NERS-21-1149

DOI: https://doi.org/10.1115/1.4053828

Published Online: June 1, 2022

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Topics: Boiling, Coolants, Drops, Dust, Ejectors, Flow (Dynamics), Pressure, Sprays, Vacuum, Water

Journal Articles

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

Yue Zou, Brian Derreberry

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.

Paper No: NERS-21-1040

DOI: https://doi.org/10.1115/1.4053013

Published Online: May 26, 2022

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Topics: Chemistry, Coolants, Fatigue, Flow (Dynamics), Outflow, Pipes, Pressurized water reactors, Stress, Temperature, Thermal stratification

Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.

Paper No: NERS-21-1101

DOI: https://doi.org/10.1115/1.4053049

Published Online: March 22, 2022

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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing

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

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

Thomas Schulenberg, Ivan Otic

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031104.

Paper No: NERS-21-1074

DOI: https://doi.org/10.1115/1.4052191

Published Online: March 15, 2022

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Topics: Coolants, Design, Fuels, Heat, Supercritical water reactors, Water, Temperature, Light water reactors, Cladding systems (Building), Natural convection

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

On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

Serguei Podobed

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024505.

Paper No: NERS-20-1167

DOI: https://doi.org/10.1115/1.4052591

Published Online: January 11, 2022

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Topics: Coolants, Currents, Design, Excitation, Liquid metals, Magnetic fields, Pressure, Sodium, Heat exchangers, Pumps

Journal Articles

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Hong Xu, Aurelian Florin Badea, Xu Cheng

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.

Paper No: NERS-21-1036

DOI: https://doi.org/10.1115/1.4050770

Published Online: October 19, 2021

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Topics: Accidents, Coolants, Steady state, Transients (Dynamics), Errors, Flow (Dynamics), Thermal hydraulics, Leakage, Simulation

Journal Articles

Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments

Sara Perez-Martin, Marine Anderhuber, Laurent Laborde, Nathalie Girault, Calogera Lombardo, Luca Ammirabile, Konstantin Mikityuk, Stephane Mimouni, Christophe Péniguel, Werner Pfrang

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011310.

Paper No: NERS-21-1049

DOI: https://doi.org/10.1115/1.4050769

Published Online: August 3, 2021

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Topics: Boiling, Coolants, Flow (Dynamics), Sodium, Sodium fast reactors, Temperature, Temperature profiles, Transients (Dynamics)

Journal Articles

Small Modular Reactors: Learning From the Past

Esam M. A. Hussein

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034508.

Paper No: NERS-20-1152

DOI: https://doi.org/10.1115/1.4050478

Published Online: May 26, 2021

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Topics: Coolants, Fast neutron reactors, Fuels, Gas cooled reactors, High temperature, Liquid metals, Molten salt reactors, Pressurized water reactors, Small modular reactors, Licensing

Journal Articles

CANDU-Like Features in Emerging Small Modular Reactor Designs

Esam M. A. Hussein

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034507.

Paper No: NERS-20-1151

DOI: https://doi.org/10.1115/1.4050477

Published Online: May 26, 2021

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Topics: Fuels, Small modular reactors, Water, Coolants, Drainage, Heat sinks, Design, Construction, Lithium, Heat

Journal Articles

Machine Learning-Based Methodology for Assessment of Doppler Reactivity of Sodium-Cooled Fast Reactor

Đorđe Petrović, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. October 2021, 7(4): 042004.

Paper No: NERS-20-1086

DOI: https://doi.org/10.1115/1.4050216

Published Online: April 16, 2021

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Topics: Artificial neural networks, Databases, Fuels, Sodium fast reactors, Temperature, Machinery, Coolants

Journal Articles

Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant

Zayed Ahmed, Seth Eckels, Steven J. Eckels, Hitesh Bindra

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031405.

Paper No: NERS-20-1111

DOI: https://doi.org/10.1115/1.4049280

Published Online: April 2, 2021

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Topics: Boiling, Bubbles, Heat transfer, Heat transfer coefficients, Seawater, Subcooling, Coolants, Wall temperature, Flow (Dynamics), Temperature

Journal Articles

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

L. C. Juárez, J. I. Torres, J. L. François

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034505.

Paper No: NERS-20-1068

DOI: https://doi.org/10.1115/1.4049714

Published Online: April 1, 2021

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Topics: Coolants, Density, Fast neutron reactors, Fuels, Neutrons, Cycles, Temperature, Modeling

Journal Articles

Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core

Zhigang Li, Ping An, Junjie Pan, Wei Liu, Wei Lu, Shenglong Qiang

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034504.

Paper No: NERS-20-1038

DOI: https://doi.org/10.1115/1.4048027

Published Online: March 16, 2021

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Topics: Dynamics (Mechanics), Fuels, Neutrons, Pressurized water reactors, Spacetime, Temperature, Transients (Dynamics), Water, Cylinders, Computational methods

Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Sandip Ghosh, Samir Kumar Saha

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.

Paper No: NERS-20-1012

DOI: https://doi.org/10.1115/1.4048477

Published Online: March 16, 2021

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Topics: Flow (Dynamics), Leakage, Pipes, Simulation, Subcooling, Flashing, Coolants, Fracture (Materials), Modeling, Vapors

Journal Articles

Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

M. Ruscak, G. Mazzini, A. Dambrosio, A. Musa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021402.

Paper No: NERS-20-1208

DOI: https://doi.org/10.1115/1.4049854

Published Online: February 26, 2021

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Topics: Accidents, Coolants, Flow (Dynamics), Pressure, Safety, Simulation, Water, Nuclear power stations, Feedwater, Design

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Journal citation

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Manuscript

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC

Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Machine Learning Metamodel of a Computationally Intense Accident Simulation Code

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

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

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

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

On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Evaluation of Sodium Boiling Models Using KNS-37 Loss of Flow Experiments

Small Modular Reactors: Learning From the Past

CANDU-Like Features in Emerging Small Modular Reactor Designs

Machine Learning-Based Methodology for Assessment of Doppler Reactivity of Sodium-Cooled Fast Reactor

Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

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