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Journal Articles

System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

Shujun Wang, Xianmin Huang, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
Paper No: NERS-23-1011
https://doi.org/10.1115/1.4062500
Published Online: September 15, 2023
View Article titled, System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept
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Topics: Coolants, Cycles, Design, Flow (Dynamics), Fuels, High temperature, Modeling, Temperature, Thermal hydraulics, Steady state
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
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Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)
Journal Articles

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

Hong Xu, Aurelian Florin Badea, Xu Cheng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.
Paper No: NERS-21-1036
https://doi.org/10.1115/1.4050770
Published Online: October 19, 2021
View Article titled, Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021501.
Paper No: NERS-20-1150
https://doi.org/10.1115/1.4049727
Published Online: October 19, 2021
View Article titled, Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium
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Topics: Density, Neutrons, Steady state, Transients (Dynamics), Waves
Journal Articles

Investigating Small Modular Reactor's Design Limits for Its Flexible Operation With Photovoltaic Generation in Microcommunities

Kalpesh Joshi, Bikash Poudel, Ramakrishna (Rama) Gokaraju
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031303.
Paper No: NERS-20-1051
https://doi.org/10.1115/1.4048896
Published Online: March 16, 2021
View Article titled, Investigating Small Modular Reactor's Design Limits for Its Flexible Operation With Photovoltaic Generation in Microcommunities
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Topics: Design, Nuclear power stations, Simulation, Small modular reactors, Stress, Turbines, Power systems (Machinery), Governors, Steady state, Flow (Dynamics)
Journal Articles

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301.
Paper No: NERS-19-1156
https://doi.org/10.1115/1.4048007
Published Online: October 5, 2020
View Article titled, Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks
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Topics: Accidents, Computational fluid dynamics, Design, Flanges, Insulation, Pressure, Stress, Temperature, Temperature gradient, Thermal analysis
Journal Articles

A Theory and Model of Molten Salt Reactor Xenon Behavior After the Solubility Limit

Terry J. Price, Ondrej Chvala
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2021, 7(1): 014501.
Paper No: NERS-19-1126
https://doi.org/10.1115/1.4046909
Published Online: October 1, 2020
View Article titled, A Theory and Model of Molten Salt Reactor Xenon Behavior After the Solubility Limit
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Topics: Fuels, Molten salt reactors, Steady state, Bubbles
Journal Articles

A Simplified Two-Group Multipoint Kinetics Model

Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.
Paper No: NERS-19-1155
https://doi.org/10.1115/1.4046254
Published Online: October 1, 2020
View Article titled, A Simplified Two-Group Multipoint Kinetics Model
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.
Paper No: NERS-19-1164
https://doi.org/10.1115/1.4046910
Published Online: September 4, 2020
View Article titled, Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident
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Topics: Accidents, Condensation, Heat flux, Heat transfer, Pressure, Steady state, Steam, Temperature, Transients (Dynamics), Containment
Journal Articles

Study on Calculation Difference of the SCWR Core Steady-State Analysis Code

Lianjie Wang, Lei Yao, Ping Yang, Di Lu, Wenbo Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031103.
Paper No: NERS-19-1054
https://doi.org/10.1115/1.4044408
Published Online: June 5, 2020
View Article titled, Study on Calculation Difference of the SCWR Core Steady-State Analysis Code
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Topics: Density, Feedback, Steady state, Supercritical water reactors, Thermal hydraulics, Water, Flow (Dynamics)
Journal Articles

Gas Turbine Arekret-Cycle Simulation Modeling for Training and Educational Purposes

Emmanuel O. Osigwe, Pericles Pilidis, Theoklis Nikolaidis, Suresh Sampath
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041207.
Paper No: NERS-19-1002
https://doi.org/10.1115/1.4043681
Published Online: August 2, 2019
View Article titled, Gas Turbine Arekret-Cycle Simulation Modeling for Training and Educational Purposes
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Topics: Closed-cycle gas turbines, Compressors, Computer simulation, Cycles, Design, Engines, Flow (Dynamics), Fluids, Gas turbines, Pressure
Journal Articles

Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0

S. P. Saraswat, D. Ray, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 042202.
Paper No: NERS-18-1030
https://doi.org/10.1115/1.4042707
Published Online: July 19, 2019
View Article titled, Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0
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Topics: Accidents, Coolants, Cooling systems, Design, Heat, Heat sinks, Modeling, Plasmas (Ionized gases), Pressure, Sprays
Journal Articles

Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements

Guido Mazzini, Miloš Kynčl, Marek Ruščák, Miroslav Hrehor, Alis Musa, Antonio Dambrosio, Vincenzo Romanello
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030914.
Paper No: NERS-18-1085
https://doi.org/10.1115/1.4043377
Published Online: May 10, 2019
View Article titled, Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements
Open the PDF for Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements in another window
Topics: Helium, Simulation, Steady state, Temperature, Flow (Dynamics), Compressors, Coolants, Pipes
Journal Articles

Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR

Christopher J. Hurt, James D. Freels, Prashant K. Jain, G. Ivan Maldonado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021004.
Paper No: NERS-16-1070
https://doi.org/10.1115/1.4041295
Published Online: March 15, 2019
View Article titled, Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR
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Topics: Cycles, Irradiation (Radiation exposure), Safety, Temperature, Stress, Heat transfer, Electrical conductance, Steady state, Heat, Cladding systems (Building)
Journal Articles

Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code

S. P. Saraswat, P. Munsh, A. Khanna, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021001.
Paper No: NERS-16-1138
https://doi.org/10.1115/1.4038823
Published Online: March 5, 2018
View Article titled, Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code
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Topics: Accidents, Coolants, Heat, Helium, Pressure, Vessels, Water, Safety, Temperature, Vacuum
Journal Articles

Study on Optimization Design for CSR1000 Core

Lianjie Wang, Ping Yang, Di Lu, Wenbo Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011013.
Paper No: NERS-17-1031
https://doi.org/10.1115/1.4037669
Published Online: December 4, 2017
View Article titled, Study on Optimization Design for CSR1000 Core
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Topics: Cycles, Design, Fuels, Optimization, Steady state, Flow (Dynamics), Coolants, Manufacturing
Journal Articles

An Experimental and Numerical Study to Support Development of Molten Salt Breeder Reactor

A. K. Srivastava, R. Chouhan, A. Borgohain, S. S. Jana, N. K. Maheshwari, D. S. Pilkhwal, A. Rama Rao, K. N. Hareendhran, S. Chowdhury, K. B. Modi, S. K. Raut, S. C. Parida
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031007.
Paper No: NERS-16-1154
https://doi.org/10.1115/1.4036027
Published Online: May 25, 2017
View Article titled, An Experimental and Numerical Study to Support Development of Molten Salt Breeder Reactor
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Topics: Boundary-value problems, Breeder reactors, Computational fluid dynamics, Flow (Dynamics), Simulation, Steady state, Temperature, Transients (Dynamics), Fluids, Instrumentation
Journal Articles

Development of SNTA Code System for SCWR Core Steady-State Analysis

Lianjie Wang, Wenbo Zhao, Ping Yang, Yongqiang Ma, Di Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021005.
Paper No: NERS-16-1050
https://doi.org/10.1115/1.4035334
Published Online: March 1, 2017
View Article titled, Development of SNTA Code System for SCWR Core Steady-State Analysis
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Topics: Coolants, Steady state, Supercritical water reactors, Thermal hydraulics, Flow (Dynamics), Water, Density, Relaxation (Physics), Design, Finite difference methods
Journal Articles

Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor

Guido Mazzini, Miloš Kynčl, Marek Ruščák
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044505.
Paper No: NERS-15-1221
https://doi.org/10.1115/1.4034144
Published Online: October 12, 2016
View Article titled, Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
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Topics: Accidents, Design, Feedwater, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Hydrogen production, Leakage, Nuclear engineering, Nuclear power stations, Pressure
Journal Articles

Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model

Andrea Querol, Sergio Gallardo, Gumersindo Verdú
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021020.
Paper No: NERS-15-1029
https://doi.org/10.1115/1.4031016
Published Online: February 29, 2016
View Article titled, Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model
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Topics: Cladding systems (Building), Coolants, Delays, Flow (Dynamics), Pressure, Temperature, Thermocouples, Transients (Dynamics), Steady state, Secondary cells