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S. P. Saraswat
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Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
Paper No: NERS-21-1073
https://doi.org/10.1115/1.4052014
Published Online: May 26, 2022
View Article titled, Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
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Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics
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

Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)

S. P. Saraswat, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011402.
Paper No: NERS-19-1022
https://doi.org/10.1115/1.4047161
Published Online: October 2, 2020
View Article titled, Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)
Open the PDF for Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis) in another window
Topics: Accidents, Boiling water reactors, Eigenvalues, Fluids, Porosity, Pressure, Pressurized water reactors, Light water reactors, Water, Stability
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

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
Open the PDF for Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code in another window
Topics: Accidents, Coolants, Heat, Helium, Pressure, Vessels, Water, Safety, Temperature, Vacuum
Journal Articles

Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

S. P. Saraswat, P. Munshi, A. Khanna, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041009.
Paper No: NERS-17-1021
https://doi.org/10.1115/1.4037188
Published Online: July 31, 2017
View Article titled, Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0
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Topics: Accidents, Coolants, Flow (Dynamics), Vessels, Temperature, Heat, Pressure, Cooling systems, Water, Tungsten
Journal Articles

Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code

S. P. Saraswat, P. Munshi, A. Khanna, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014503.
Paper No: NERS-16-1012
https://doi.org/10.1115/1.4034680
Published Online: December 20, 2016
View Article titled, Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code
Open the PDF for Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code in another window
Topics: Accidents, Coolants, Flow (Dynamics), Heat, Helium, Vessels, Safety, Cooling systems, Design, Temperature