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Journal Articles

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

Thomas Schulenberg, Ivan Otic
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031104.
Paper No: NERS-21-1074
https://doi.org/10.1115/1.4052191
Published Online: March 15, 2022
View Article titled, Concept of a Small Modular SCWR With Horizontal Fuel Assemblies
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Topics: Coolants, Design, Fuels, Heat, Supercritical water reactors, Water, Temperature, Light water reactors, Cladding systems (Building), Natural convection
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034504.
Paper No: NERS-20-1038
https://doi.org/10.1115/1.4048027
Published Online: March 16, 2021
View Article titled, Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core
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Topics: Dynamics (Mechanics), Fuels, Neutrons, Pressurized water reactors, Spacetime, Temperature, Transients (Dynamics), Water, Cylinders, Computational methods
Journal Articles

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

Guido Mazzini, Alis Musa, Rostilav Fukac
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.
Paper No: NERS-20-1157
https://doi.org/10.1115/1.4050207
Published Online: March 10, 2021
View Article titled, Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario
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Topics: Flow (Dynamics), Pressure, Safety, Simulation, Temperature, Transients (Dynamics), Water, Heat transfer, Pumps, Light water reactors
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)
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Topics: Accidents, Boiling water reactors, Eigenvalues, Fluids, Porosity, Pressure, Pressurized water reactors, Light water reactors, Water, Stability
Journal Articles

A Study of Superhomogenization Applied to PHWR Lattices

Thomas A. Ferguson, Eleodor M. Nichita
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011109.
Paper No: NERS-19-1049
https://doi.org/10.1115/1.4044748
Published Online: November 8, 2019
View Article titled, A Study of Superhomogenization Applied to PHWR Lattices
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Topics: Fuels, Heavy water reactors, Light water reactors, Water, Diffusion (Physics), Cross section (Physics)
Journal Articles

Miniature Autoclave and Double Bellows Loading Device for Material Testing in Future Reactor Concept Conditions—Case Supercritical Water

Sami Penttilä, Pekka Moilanen, Wade Karlsen, Aki Toivonen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011016.
Paper No: NERS-17-1028
https://doi.org/10.1115/1.4037897
Published Online: December 4, 2017
View Article titled, Miniature Autoclave and Double Bellows Loading Device for Material Testing in Future Reactor Concept Conditions—Case Supercritical Water
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Topics: Bellows (Equipment), Pressure, Stress, Water, Temperature, Materials testing, Light water reactors, Testing
Journal Articles

Phenomenological Analysis of Melt Progression in LWRS: Proposal of an In-Vessel Corium Progression Scenario in the Unit 1 of Fukushima Dai-ichi Nuclear Power Plant

Payot Frédéric, Seiler Jean-Marie
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041005.
Paper No: NERS-15-1151
https://doi.org/10.1115/1.4033397
Published Online: October 12, 2016
View Article titled, Phenomenological Analysis of Melt Progression in LWRS: Proposal of an In-Vessel Corium Progression Scenario in the Unit 1 of Fukushima Dai-ichi Nuclear Power Plant
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Topics: Failure, Fukushima nuclear disaster, Japan, 2011, Heat flux, Jet pumps, Nuclear power stations, Seas, Vessels, Water, Light water reactors, Melting
Journal Articles

COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Vefa N. Kucukboyaci, Liping Cao, Yixing Sung
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031002.
Paper No: NERS-15-1018
https://doi.org/10.1115/1.4032594
Published Online: June 17, 2016
View Article titled, COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
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Topics: Accidents, Coolants, Critical heat flux, Fuel rods, Fuels, Heat transfer, Irradiation (Radiation exposure), Pressurized water reactors, Simulation, Transients (Dynamics)
Journal Articles

Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor

Wenzhong Zhou, Rong Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041007.
Paper No: NERS-15-1020
https://doi.org/10.1115/1.4031033
Published Online: September 3, 2015
View Article titled, Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor
Open the PDF for Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor in another window
Topics: Fuels, Light water reactors, Oxygen, Simulation, Temperature, Fast neutron reactors, Diffusion (Physics), Heat, Boundary-value problems, Thermal diffusion
Journal Articles

A Review on Analysis of LWR Severe Accident

Y. P. Zhang, S. P. Niu, L. T. Zhang, S. Z. Qiu, G. H. Su, W. X. Tian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041018.
Paper No: NERS-14-1048
https://doi.org/10.1115/1.4030364
Published Online: September 3, 2015
View Article titled, A Review on Analysis of LWR Severe Accident
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Topics: Accidents, Containment, Explosions, Steam, Vessels, Nuclear fission, Water, Cooling, Hydrogen, Light water reactors