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Journal Articles

Validation of the Moody and Henry–Fauske Critical Flow Models in apros Against Marviken Critical Flow Experiments

Milan Tesinsky

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041102.

Paper No: NERS-19-1120

DOI: https://doi.org/10.1115/1.4046432

Published Online: September 4, 2020

View Article titled, Validation of the Moody and Henry–Fauske Critical Flow Models in apros Against Marviken Critical Flow Experiments

Topics: Flow (Dynamics), Discharge coefficient

Journal Articles

A Novel Assessment of Delayed Neutron Detector Data in CANDU Reactors

Will Aylward, Christopher Wallace, Graeme West, Curtis McEwan

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041107.

Paper No: NERS-19-1163

DOI: https://doi.org/10.1115/1.4046824

Published Online: September 4, 2020

View Article titled, A Novel Assessment of Delayed Neutron Detector Data in CANDU Reactors

Topics: Fuels, Neutrons, Sensors, Noise control, Monitoring systems

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

View Article titled, Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

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

Journal Articles

The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition

ZhiGang Li, Wei Liu, PingZhou Ming, Ping An, Wei Lu, JunJie Pan

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041103.

Paper No: NERS-19-1153

DOI: https://doi.org/10.1115/1.4047093

Published Online: September 4, 2020

View Article titled, The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition

Topics: Sensitivity analysis

Journal Articles

Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

María Freiría López, Michael Buck, Jörg Starflinger

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041110.

Paper No: NERS-19-1166

DOI: https://doi.org/10.1115/1.4047094

Published Online: September 4, 2020

View Article titled, Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

Topics: Concretes, Water, Fukushima nuclear disaster, Japan, 2011, Vessels, Sensitivity analysis

Journal Articles

ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

Robert B. Keating, Suzanne P. McKillop, Todd Allen, Mark Anderson

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041106.

Paper No: NERS-19-1161

DOI: https://doi.org/10.1115/1.4047113

Published Online: September 4, 2020

View Article titled, ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

Topics: Design, Diffusion (Physics), Heat exchangers, High temperature, Reliability, Testing, Construction, ASME Standards, ASME Boiler and Pressure Vessel Code, Stress

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

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

Topics: Fuels, Manufacturing, Simulation, Transients (Dynamics), Temperature, Uncertainty, Pressure

Journal Articles

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Marwan Charrouf, Storm Kauffman, Jin-Kyoo Yoon, Sang-Gyu Lee, Taejoon Kim

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041112.

Paper No: NERS-19-1168

DOI: https://doi.org/10.1115/1.4047441

Published Online: September 4, 2020

View Article titled, Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Topics: Computational fluid dynamics, Flow (Dynamics), Jets, Nozzles, Nuclear power stations, Pipes, Pressure, Reflection, Resonance, Waves

Journal Articles

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Sergey Galushin, Dmitry Grishchenko, Pavel Kudinov

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113.

Paper No: NERS-19-1170

DOI: https://doi.org/10.1115/1.4047552

Published Online: September 4, 2020

View Article titled, Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Topics: Boiling water reactors, Containment, Explosions, Failure, Steam, Vessels, Risk, Accidents, Uncertainty

Journal Articles

Noncontact Displacement Measurement of Nuclear Waste Canisters in a Geological Disposal by Using an Electromagnetic-Wave Approach

Mauro Cappelli, Vincenzo Surrenti

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041104.

Paper No: NERS-19-1157

DOI: https://doi.org/10.1115/1.4047719

Published Online: September 4, 2020

View Article titled, Noncontact Displacement Measurement of Nuclear Waste Canisters in a Geological Disposal by Using an Electromagnetic-Wave Approach

Topics: Cables, Displacement measurement, Radioactive wastes, Resolution (Optics), Resonance, Sensors, Signals, Water, Wavelength, Waves

Journal Articles

Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

Sai Raja Gopal Vadlamudi, Arun K. Nayak

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041109.

Paper No: NERS-19-1165

DOI: https://doi.org/10.1115/1.4048124

Published Online: September 4, 2020

View Article titled, Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

Topics: Boiling, Bubbles, Flow (Dynamics), Lift (Fluid dynamics), Lubrication, Porosity, Subcooling, Turbulence, Heat flux

Journal Articles

Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants

Xiaocheng Fu, Fenglei Du, Xiang Pu, Xuan Wang, Fengze Han

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041101.

Paper No: NERS-19-1110

DOI: https://doi.org/10.1115/1.4048112

Published Online: September 4, 2020

View Article titled, Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants

Topics: Filters, Nuclear power stations, Tides, Water, Cooling, Safety, Design, Seas

Journal Articles

Organ Dose Calculations Using ICRP Adult Voxel Phantoms and TRIPOLI-4 Monte Carlo Code

Yi-Kang Lee

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041105.

Paper No: NERS-19-1160

DOI: https://doi.org/10.1115/1.4046213

Published Online: September 4, 2020

View Article titled, Organ Dose Calculations Using ICRP Adult Voxel Phantoms and TRIPOLI-4 Monte Carlo Code

Topics: Phantoms, Photons, Biological tissues, Electrons, Neutrons, Radiation (Physics)

Journal Articles

A New Approach to Generalization of Experimental Data on Heat Transfer to Fluids in Supercritical Region

V. I. Deev, V. S. Kharitonov, A. M. Baisov, A. N. Churkin

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021109.

Paper No: NERS-19-1064

DOI: https://doi.org/10.1115/1.4046112

Published Online: February 24, 2020

View Article titled, A New Approach to Generalization of Experimental Data on Heat Transfer to Fluids in Supercritical Region

Topics: Heat transfer, Fluids, Water

Journal Articles

Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code

Michele Andreani, Ralf Kapulla, Stephan Kelm, Domenico Paladino, Sidharth Paranjape

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021110.

Paper No: NERS-19-1072

DOI: https://doi.org/10.1115/1.4046296

Published Online: February 24, 2020

View Article titled, Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code

Topics: Elevations (Drawings), Erosion, Flow (Dynamics), Helium, Pipes, Simulation, Steam, Temperature, Turbulence, Vessels

Journal Articles

Leakage Estimate in Nonuniformly Compressed Packing Rings

Ali Salah Omar Aweimer, Abdel-Hakim Bouzid, Zijian Zhao

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021114.

Paper No: NERS-19-1061

DOI: https://doi.org/10.1115/1.4045225

Published Online: February 5, 2020

View Article titled, Leakage Estimate in Nonuniformly Compressed Packing Rings

Topics: Leakage, Packing (Shipments), Packings (Cushioning), Stress, Compression, Pressure, Valves, Porosity, Helium

Journal Articles

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021108.

Paper No: NERS-19-1059

DOI: https://doi.org/10.1115/1.4044910

Published Online: February 5, 2020

View Article titled, Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Topics: Cross section (Physics), Fuels, Simulation, Temperature, Graphite, Neutron flux, Nuclear fission, Neutrons, High temperature, Flow (Dynamics)

Journal Articles

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

Yuiko Motome, Yoshiya Akiyama, Hiroyuki Murao

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021115.

Paper No: NERS-19-1073

DOI: https://doi.org/10.1115/1.4045075

Published Online: February 3, 2020

View Article titled, Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

Topics: Earthquakes, Fuel rods, Fuel storage, Fuels, Radiation (Physics), Safety, Spent fuel storage, Tsunamis, Nuclear fission, Shapes

Journal Articles

Angular Distribution of Neutrons Around Thick Beryllium Target of Accelerator-Based 9 Be(d, n) Neutron Source

A. M. Shehada, V. M. Golovkov

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021111.

Paper No: NERS-19-1112

DOI: https://doi.org/10.1115/1.4045234

Published Online: February 3, 2020

View Article titled, Angular Distribution of Neutrons Around Thick Beryllium Target of Accelerator-Based 9 Be(d, n) Neutron Source

Topics: Neutrons, Neutron sources, Deuterons

Journal Articles

A Study on Sodium–Concrete Reaction in Presence of Internal Heating

Munemichi Kawaguchi, Shinya Miyahara, Masayoshi Uno

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021106.

Paper No: NERS-19-1119

DOI: https://doi.org/10.1115/1.4045898

Published Online: February 3, 2020

View Article titled, A Study on Sodium–Concrete Reaction in Presence of Internal Heating

Topics: Concretes, Sodium, Temperature, Aerosols, Heating, Ablation (Vaporization technology), Hydrogen

Journal citation

NARROW

Validation of the Moody and Henry–Fauske Critical Flow Models in apros Against Marviken Critical Flow Experiments

A Novel Assessment of Delayed Neutron Detector Data in CANDU Reactors

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

The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition

Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

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

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Noncontact Displacement Measurement of Nuclear Waste Canisters in a Geological Disposal by Using an Electromagnetic-Wave Approach

Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants

Organ Dose Calculations Using ICRP Adult Voxel Phantoms and TRIPOLI-4 Monte Carlo Code

A New Approach to Generalization of Experimental Data on Heat Transfer to Fluids in Supercritical Region

Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code

Leakage Estimate in Nonuniformly Compressed Packing Rings

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

Angular Distribution of Neutrons Around Thick Beryllium Target of Accelerator-Based 9 Be(d, n) Neutron Source

A Study on Sodium–Concrete Reaction in Presence of Internal Heating

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