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Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.

Paper No: NERS-22-1136

DOI: https://doi.org/10.1115/1.4056854

Published Online: March 14, 2023

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Topics: Coolants, Flow (Dynamics), Fuels, Sodium, Temperature, Accidents, Transients (Dynamics), Pins (Engineering)

Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021301.

Paper No: NERS-21-1161

DOI: https://doi.org/10.1115/1.4056834

Published Online: March 2, 2023

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Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)

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

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

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Zefeng Wang, Jian Deng, Zhifang Qiu, Xiaoyu Wang, Lei Zhong, Mingjun Zhong

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403.

Paper No: NERS-20-1202

DOI: https://doi.org/10.1115/1.4051875

Published Online: October 19, 2021

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Topics: Film boiling, Heat flux, Heat transfer, Pool boiling, Quenching (Metalworking), Temperature, Transients (Dynamics), Water, Heat conduction, Heat transfer coefficients

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

Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium

D. Ray, S. P. Saraswat, M. Kumar, O. P. Singh, P. Munshi

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021501.

Paper No: NERS-20-1150

DOI: https://doi.org/10.1115/1.4049727

Published Online: October 19, 2021

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Topics: Density, Neutrons, Steady state, Transients (Dynamics), Waves

Journal Articles

Superphénix Benchmark Part II: Transient Results

A. Ponomarev, K. Mikityuk, E. Fridman, V. A. Di Nora, E. Bubelis, M. Schikorr

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011321.

Paper No: NERS-21-1052

DOI: https://doi.org/10.1115/1.4051877

Published Online: October 8, 2021

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Topics: Flow (Dynamics), Fuels, Sodium, Temperature, Transients (Dynamics), Modeling

Journal Articles

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

Alexander Ponomarev, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011313.

Paper No: NERS-20-1186

DOI: https://doi.org/10.1115/1.4051514

Published Online: September 13, 2021

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Topics: Flow (Dynamics), Fuels, Modeling, Rods, Sodium, Sodium fast reactors, Temperature, Transients (Dynamics), Electrical conductance, Heat

Journal Articles

Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor

Evaldas Bubelis, Michael Schikorr, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011309.

Paper No: NERS-21-1048

DOI: https://doi.org/10.1115/1.4050563

Published Online: August 3, 2021

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Topics: Rods, Sodium fast reactors, Transients (Dynamics), Cooling, Circuits, Flow (Dynamics)

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

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

Fidelma G. Di Lemma, Colby B. Jensen, Joshua J. Kane, Wei-Ying Chen, Xiang Liu, Luca Capriotti, Cynthia A. Adkins, Boopathy Kombaiah, Alexander J. Winston, Lingfeng He, Daniel Wachs

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041602.

Paper No: NERS-20-1097

DOI: https://doi.org/10.1115/1.4049721

Published Online: April 22, 2021

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Topics: Bubbles, Fuels, Instrumentation, Irradiation (Radiation exposure), Nuclear fission, Safety, Transients (Dynamics), Sodium fast reactors, Testing, Fast neutron reactors

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

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

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Guido Mazzini, Alis Musa, Rostilav Fukac

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.

Paper No: NERS-20-1157

DOI: https://doi.org/10.1115/1.4050207

Published Online: March 10, 2021

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Topics: Flow (Dynamics), Pressure, Safety, Simulation, Temperature, Transients (Dynamics), Water, Heat transfer, Pumps, Light water reactors

Journal Articles

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro

ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301.

Paper No: NERS-19-1156

DOI: https://doi.org/10.1115/1.4048007

Published Online: October 5, 2020

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Topics: Accidents, Computational fluid dynamics, Design, Flanges, Insulation, Pressure, Stress, Temperature, Temperature gradient, Thermal analysis

Journal Articles

Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria

R. David

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011703.

Paper No: NERS-19-1184

DOI: https://doi.org/10.1115/1.4048008

Published Online: October 5, 2020

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Topics: Accidents, Finite element model, Heat, Melting, Porosity, Temperature, Transients (Dynamics), Uranium, Materials properties

Journal Articles

A Simplified Two-Group Multipoint Kinetics Model

Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.

Paper No: NERS-19-1155

DOI: https://doi.org/10.1115/1.4046254

Published Online: October 1, 2020

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Topics: Eigenvalues, Heat flux, Neutrons, Steady state, Transients (Dynamics), Thermal hydraulics, Diffusion (Physics), Simulation, Circuits, Fluid dynamics

Journal Articles

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.

Paper No: NERS-19-1164

DOI: https://doi.org/10.1115/1.4046910

Published Online: September 4, 2020

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Topics: Accidents, Condensation, Heat flux, Heat transfer, Pressure, Steady state, Steam, Temperature, Transients (Dynamics), Containment

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

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Journal citation

NARROW

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

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

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

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

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

Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium

Superphénix Benchmark Part II: Transient Results

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor

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

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

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

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

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria

A Simplified Two-Group Multipoint Kinetics Model

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

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

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