Volume 1 Issue 4 | ASME J. of Nuclear Rad Sci.

Topics: Containment , Coolants , Design , Emergency core cooling systems , Fuels , Safety , Small modular reactors , Water , Heat , Nuclear power stations

Measured Biaxial Residual Stress Maps in a Stainless Steel Weld

Mitchell D. Olson, Michael R. Hill, Vipul I. Patel, Ondrej Muránsky, Thomas Sisneros

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041002. doi: https://doi.org/10.1115/1.4029927

Abstract

View articletitled, Measured Biaxial Residual Stress Maps in a Stainless Steel Weld

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Topics: Stress , Neutron diffraction

Effects of the Foil Flatness on Irradiation Performance of U10Mo Monolithic Mini-Plates

Hakan Ozaltun, Pavel G. Medvedev, Barry H. Rabin

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041003. doi: https://doi.org/10.1115/1.4030982

Abstract

View articletitled, Effects of the Foil Flatness on Irradiation Performance of U10Mo Monolithic Mini-Plates

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Topics: Cladding systems (Building) , Fuels , Irradiation (Radiation exposure) , Plates (structures) , Stress , Temperature , Displacement , Density

Characterization and Optimization of a Tensioned Metastable Fluid Nuclear Particle Sensor Using Laser-Based Profilometry

Alexander R. Hagen, Thomas F. Grimes, Brian C. Archambault, Trevor N. Harris, Rusi P. Taleyarkhan

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041004. doi: https://doi.org/10.1115/1.4029918

Abstract

View articletitled, Characterization and Optimization of a Tensioned Metastable Fluid Nuclear Particle Sensor Using Laser-Based Profilometry

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Topics: Cavitation , Fluids , Lasers , Pressure , Sensors , Simulation , Neutrons , Particulate matter , Glass , Optimization

Validation Facility and Model Development for Nuclear Fuel Assembly Response to Seismic Loading

Noah A. Weichselbaum, Morteza Rahimi Abkenar, Marcos Vanella, Majid T. Manzari, Elias Balaras, Philippe M. Bardet

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041005. doi: https://doi.org/10.1115/1.4031031

Abstract

View articletitled, Validation Facility and Model Development for Nuclear Fuel Assembly Response to Seismic Loading

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Topics: Computation , Engineering prototypes , Engineering simulation , Flow (Dynamics) , Fluids , Fuel rods , Fuels , Geometry , Manufacturing , Nuclear fuels

Numerical Study of High-Temperature and High-Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core

Kazim M. Akyuzlu

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041006. doi: https://doi.org/10.1115/1.4030833

Abstract

View articletitled, Numerical Study of High-Temperature and High-Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core

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Topics: Computational fluid dynamics , Cooling , Engines , Flow (Dynamics) , Fluids , Fuels , Heat flux , Hydrogen , Pressure , Temperature

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

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041007. doi: https://doi.org/10.1115/1.4031033

Abstract

View articletitled, Fully Coupled Simulation of Oxygen and Heat Diffusion for <math xmlns="http://www.w3.org/1998/Math/MathML"><mrow xmlns=""><mo mathvariant="normal" stretchy="false">(</mo><mi mathvariant="normal">U</mi><mo>,</mo><mi>Pu</mi><mo mathvariant="normal" stretchy="false">)</mo><msub><mrow><mi mathvariant="normal">O</mi></mrow><mrow><mn mathvariant="normal">2</mn></mrow></msub></mrow></math> Fuel in Both Fast-Breeder Reactor and Light-Water Reactor

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Topics: Fuels , Light water reactors , Oxygen , Simulation , Temperature , Fast neutron reactors , Diffusion (Physics) , Heat , Boundary-value problems , Thermal diffusion

Influence of Sump on Containment Thermal Hydraulics: Synthesis of the TOSQAN Tests

Emmanuel Porcheron, Pascal Lemaitre, Amandine Nuboer

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041008. doi: https://doi.org/10.1115/1.4030961

Abstract

View articletitled, Influence of Sump on Containment Thermal Hydraulics: Synthesis of the TOSQAN Tests

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Topics: Condensation , Containment , Pressure , Steam , Temperature , Vessels , Water , Flow (Dynamics) , Evaporation , Heat

Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows

Michio Murase, Ikuo Kinoshita, Takayoshi Kusunoki, Dirk Lucas, Akio Tomiyama

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041009. doi: https://doi.org/10.1115/1.4031032

Abstract

View articletitled, Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows

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Topics: Computation , Flow (Dynamics) , Pipes , Surges , Water , Boundary-value problems , Drag (Fluid dynamics) , Friction , Pressure

Batch-Scale Hydrofluorination of ${}^{7}{Li}_{2} {BeF}_{4}$ to Support Molten Salt Reactor Development

Brian C. Kelleher, Kieran P. Dolan, Paul Brooks, Mark H. Anderson, Kumar Sridharan

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041010. doi: https://doi.org/10.1115/1.4030963

Abstract

View articletitled, Batch-Scale Hydrofluorination of <math xmlns="http://www.w3.org/1998/Math/MathML"><mrow xmlns=""><mmultiscripts><mrow><msub><mrow><mi>Li</mi></mrow><mrow><mn mathvariant="bold-sans-serif">2</mn></mrow></msub></mrow><mprescripts></mprescripts><none></none><mrow><mn mathvariant="bold-sans-serif">7</mn></mrow></mmultiscripts><msub><mrow><mi>BeF</mi></mrow><mrow><mn mathvariant="bold-sans-serif">4</mn></mrow></msub></mrow></math> to Support Molten Salt Reactor Development

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Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor

Goutam Dutta, Chao Zhang, Jin Jiang

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041011. doi: https://doi.org/10.1115/1.4030199

Abstract

View articletitled, Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor

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Topics: Heat transfer , Supercritical water reactors , Thrust , Wall temperature , Buoyancy , Heating , Oscillations , Temperature , Density , Computer simulation

Thermal Predictions of the AGR-3/4 Experiment With Time-Varying Gas Gaps

Grant L. Hawkes, James W. Sterbentz, John T. Maki

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041012. doi: https://doi.org/10.1115/1.4030046

Abstract

View articletitled, Thermal Predictions of the AGR-3/4 Experiment With Time-Varying Gas Gaps

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Topics: Fluence (Radiation measurement) , Fuels , Graphite , Neutrons , Temperature , Thermal conductivity , Heat , Irradiation (Radiation exposure)

Thermal Hydraulics of Accelerator-Driven System Using RELAP5 Code

Indu Kumari, Ashok Khanna

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041013. doi: https://doi.org/10.1115/1.4030799

Abstract

View articletitled, Thermal Hydraulics of Accelerator-Driven System Using RELAP5 Code

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Topics: Flow (Dynamics) , Heat , Water , Temperature , Heat exchangers , Design , Coolants , Steady state , Stress , Waste heat

Investigation of Natural Convection Heat-Transfer Phenomena in Packed Beds: Lead-Way Toward New Nuclear Fuel Design

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041014. doi: https://doi.org/10.1115/1.4030983

Abstract

View articletitled, Investigation of Natural Convection Heat-Transfer Phenomena in Packed Beds: Lead-Way Toward New Nuclear Fuel Design

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Topics: Design , Heat transfer , Particulate matter , Heat , Fuels , Nuclear fuels , Temperature , Cladding systems (Building)

Experimental Study of the Characteristics of Heat Transfer in an HLMC Cross-Flow around Tubes

Aleksei Chernysh, Mikhail Iarmonov, Kirill Makhov, Aleksandr Beznosov

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041015. doi: https://doi.org/10.1115/1.4030365

Abstract

View articletitled, Experimental Study of the Characteristics of Heat Transfer in an HLMC Cross-Flow around Tubes

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Topics: Coolants , Flow (Dynamics) , Heat transfer , Temperature , Oxygen , Liquid metals

RELAP5/MOD3.3 Analyses for Prevention Strategy of Extended Station Blackout

Andrej Prošek, Andrija Volkanovski

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041016. doi: https://doi.org/10.1115/1.4030834

Abstract

View articletitled, RELAP5/MOD3.3 Analyses for Prevention Strategy of Extended Station Blackout

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Topics: Flow (Dynamics) , Pumps , Safety , Computers , Delays , Pressurized water reactors , Probability , Failure , Pressure , Water

Theoretical Investigations on Laser-Assisted Depletion of ${}^{152}{Gd}$ Isotope From Natural Gadolinium

M. Sankari, M. V. Suryanarayana

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041017. doi: https://doi.org/10.1115/1.4030504

Abstract

View articletitled, Theoretical Investigations on Laser-Assisted Depletion of <math xmlns="http://www.w3.org/1998/Math/MathML"><mrow xmlns=""><mmultiscripts><mrow><mi>Gd</mi></mrow><mprescripts></mprescripts><none></none><mrow><mn mathvariant="bold">152</mn></mrow></mmultiscripts></mrow></math> Isotope From Natural Gadolinium

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Topics: Excitation , Gadolinium , Ionization , Isotope shift , Isotopes , Lasers , Photoionization , Resonance , Atoms

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

ASME J of Nuclear Rad Sci. October 2015, 1(4): 041018. doi: https://doi.org/10.1115/1.4030364

Abstract

View articletitled, 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

Erratum

Erratum: “Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant” [Journal of Nuclear Engineering and Radiation Science, 2015, 1(1), p. 011002-4-011002-8, DOI: 10.1115/1.4026389]

ASME J of Nuclear Rad Sci. October 2015, 1(4): 047001. doi: https://doi.org/10.1115/1.4031143

Extract

View articletitled, Erratum: “Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant” [Journal of Nuclear Engineering and Radiation Science, 2015, 1(1), p. 011002-4-011002-8, DOI: 10.1115/1.4026389]

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Topics: Computer simulation , Containment vessels , Nuclear engineering , Pressurized water reactors , Radiation (Physics) , Temperature distribution

Guest Editorial

Special Section: Selected Papers from the 2014 ASME IMECE in Montreal

Research Papers

Quantitative and Qualitative Comparison of Light Water and Advanced Small Modular Reactors

Measured Biaxial Residual Stress Maps in a Stainless Steel Weld

Effects of the Foil Flatness on Irradiation Performance of U10Mo Monolithic Mini-Plates

Characterization and Optimization of a Tensioned Metastable Fluid Nuclear Particle Sensor Using Laser-Based Profilometry

Validation Facility and Model Development for Nuclear Fuel Assembly Response to Seismic Loading

Numerical Study of High-Temperature and High-Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core

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

Influence of Sump on Containment Thermal Hydraulics: Synthesis of the TOSQAN Tests

Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows

Batch-Scale Hydrofluorination of ${}^{7}{Li}_{2} {BeF}_{4}$ to Support Molten Salt Reactor Development

Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor

Thermal Predictions of the AGR-3/4 Experiment With Time-Varying Gas Gaps

Thermal Hydraulics of Accelerator-Driven System Using RELAP5 Code

Investigation of Natural Convection Heat-Transfer Phenomena in Packed Beds: Lead-Way Toward New Nuclear Fuel Design

Experimental Study of the Characteristics of Heat Transfer in an HLMC Cross-Flow around Tubes

RELAP5/MOD3.3 Analyses for Prevention Strategy of Extended Station Blackout

Theoretical Investigations on Laser-Assisted Depletion of ${}^{152}{Gd}$ Isotope From Natural Gadolinium

A Review on Analysis of LWR Severe Accident

Erratum

Erratum: “Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant” [Journal of Nuclear Engineering and Radiation Science, 2015, 1(1), p. 011002-4-011002-8, DOI: 10.1115/1.4026389]

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