Volume 8 Issue 3 | ASME J. of Nuclear Rad Sci.

SPECIAL SECTION: ISSCWR-10

Editorial

Dr. Romney B. Duffey on His 80th Birthday

Igor Pioro, Richard R. Schultz, Dr. Hideki Kamide, Dr. Sama Bilbao y Leon, Dr. Nils Diaz, Alexander V. Bychkov, Dr. Leon Cizelj, Francesco D'Auria, Dr. Yanping Huang, Dr. Yasuo Koizumi, Tomio Okawa, Dr. Robert Walker, Dr. Robert Youngblood, Enrico Zio

ASME J of Nuclear Rad Sci. July 2022, 8(3): 030201. doi: https://doi.org/10.1115/1.4054329

Extract

View articletitled, Dr. Romney B. Duffey on His 80th Birthday

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Topics: Accidents , Design , Electricity (Physics) , Governments , Innovation , Japan Society of Mechanical Engineers , Nuclear engineering , Nuclear power , Risk , Safety

Special Papers

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101. doi: https://doi.org/10.1115/1.4053049

Abstract

View articletitled, Testing the Modified Subchannel <span class="small-caps">tempa</span>-<span class="small-caps">sc</span> Code in Comparison With Experiments and Other Computer Codes

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Topics: Coolants , Fluids , Fuel rods , Heat transfer , Momentum , Temperature , Water , Wall temperature , Flow (Dynamics) , Testing

Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction

K. Khumsa-Ang, S. Rousseau, O. Shiman

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031102. doi: https://doi.org/10.1115/1.4052520

Abstract

View articletitled, Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction

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Topics: Alloys , Coatings , Corrosion , Hydrogen , Water , Weight (Mass) , Zirconium , Absorption , Coating processes , Zirconium alloys

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Sami Penttilä, Juha-Matti Autio, Jari Lydman, Aki Toivonen, Seppo Peltonen, Johanna Lukin

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031103. doi: https://doi.org/10.1115/1.4052974

Abstract

View articletitled, Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

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Topics: Cladding systems (Building) , Coatings , Fracture (Materials) , Fuels , High temperature steam , Pressurized water reactors , Steam , Zirconium , Temperature , Weight (Mass)

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

Thomas Schulenberg, Ivan Otic

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031104. doi: https://doi.org/10.1115/1.4052191

Abstract

View articletitled, 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

Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles

Y. Dubyk, V. Filonov, Y. Filonova, O. Kovalenko

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105. doi: https://doi.org/10.1115/1.4052590

Abstract

View articletitled, Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles

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Topics: Computational fluid dynamics , Heat transfer , Stress , Supercritical water reactors , Temperature , Fuels , Small modular reactors

Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components

Michel Gaudet, Anne McLellan, Adrian Gerlich, Bruce Williams

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031106. doi: https://doi.org/10.1115/1.4054557

Abstract

View articletitled, Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components

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Topics: Alloys , Extruding , Friction welding , Zirconium alloys , Stainless steel , Bearings , Zirconium , Friction , Nickel , Supercritical water reactors

Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions

German Cota-Sanchez, Lin Xiao, Stephane Rousseau

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031107. doi: https://doi.org/10.1115/1.4054637

Abstract

View articletitled, Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions

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Topics: Corrosion , Welding , Phase diagrams , Water , Welded joints , Testing

Next Generation/Advanced Reactors

Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code

Alain Flores y Flores, Guido Mazzini

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031201. doi: https://doi.org/10.1115/1.4048006

Abstract

View articletitled, Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code

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Topics: Explosions , Hydrogen , Aerosols , Thermal hydraulics , Pressure , Flames , Test facilities

Thermal Hydraulics and CFD

Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant

Adam Lipchitz, Glenn Harvel, T. Sunagawa

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031301. doi: https://doi.org/10.1115/1.4053632

Abstract

View articletitled, Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant

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Topics: Density , Liquid metals , Metals , Temperature , Thermal conductivity , Viscosity , Specific heat , Alloys

Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

Glenn Harvel

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031302. doi: https://doi.org/10.1115/1.4052808

Abstract

View articletitled, Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

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Topics: Fuels , Heat , Nuclear power stations , Plastics , Pyrolysis , Small modular reactors , Heating , Syngas , Temperature , Biochar

Reactor Physics

Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

Ganesh V, Parimal P. Kulkarni, Arun K. Nayak

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031401. doi: https://doi.org/10.1115/1.4053220

Abstract

View articletitled, Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

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Topics: Floods , Temperature , Vessels , Water

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031402. doi: https://doi.org/10.1115/1.4052807

Abstract

View articletitled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

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Topics: Boundary-value problems , Simulation , Wetting , Vapors , Bubbles , Simulation results

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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403. doi: https://doi.org/10.1115/1.4052014

Abstract

View articletitled, 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

Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

Michio Murase, Yoichi Utanohara, Akio Tomiyama

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031404. doi: https://doi.org/10.1115/1.4053051

Abstract

View articletitled, Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

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Topics: Condensation , Heat transfer , Steam , Temperature , Temperature distribution , Computational fluid dynamics , Mass transfer , Flat plates

Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation

S. P. Chauhan, D. K. Chandraker, Naveen Kumar

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031405. doi: https://doi.org/10.1115/1.4053221

Abstract

View articletitled, Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation

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Topics: Excitation , Thermal stratification , Water , Temperature gradient , Temperature , Heat

Nuclear Fuels/Cycles and Materials

Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

D. G. Watts, F. P. Adams, E. Masala, L. Blomeley, B. P. Bromley

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031501. doi: https://doi.org/10.1115/1.4054079

Abstract

View articletitled, Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

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Topics: Fuels , Modeling , Physics , Pressurized water reactors , Water , Neutrons , High temperature

Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor

T. Sinh Nguyen, Xiaolin Wang, Blair P. Bromley

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031502. doi: https://doi.org/10.1115/1.4053691

Abstract

View articletitled, Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor

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Topics: Fuels , Physics , Irradiation (Radiation exposure)

Nuclear Safety/Security and Beyond Design Basis Events

Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels

Ayman M. Bayomy, Blair P. Bromley, Armando Nava Dominguez, Samuel Kelly

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031601. doi: https://doi.org/10.1115/1.4053829

Abstract

View articletitled, Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels

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Topics: Fuels , Manufacturing , Temperature , Water

Plant Systems, O&M, and Life Cycle

Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part I

Emmanuel Porcheron, Yohan Leblois, Thomas Gelain, Christophe Chagnot, Christophe Journeau, Damien Roulet

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031701. doi: https://doi.org/10.1115/1.4051611

Abstract

View articletitled, Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part I

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Topics: Aerosols , Sprays , Particulate matter , Laser cutting , Fuels , Water , Drops

Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part II

Emmanuel Porcheron, Yohan Leblois, Thomas Gelain, Christophe Chagnot, Christophe Journeau, Damien Roulet

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031702. doi: https://doi.org/10.1115/1.4051538

Abstract

View articletitled, Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part II

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Topics: Aerosols , Particulate matter , Sprays , Laser cutting , Drops , Fuels , Water , Computer simulation , Fukushima nuclear disaster, Japan, 2011

Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

Emmanuel K. Boafo, Emmanuel Numapau Gyamfi

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031703. doi: https://doi.org/10.1115/1.4053050

Abstract

View articletitled, Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

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Topics: Accidents , Hydrogen , Sensitivity analysis , Uncertainty , Uncertainty quantification , Uncertainty analysis , Design , Optimization

RAW Management and Decommissioning

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

Yue Zou, Brian Derreberry

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801. doi: https://doi.org/10.1115/1.4053013

Abstract

View articletitled, Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

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Topics: Chemistry , Coolants , Fatigue , Flow (Dynamics) , Outflow , Pipes , Pressurized water reactors , Stress , Temperature , Thermal stratification

High Reliability Microgrid for a Nuclear Facility Emergency Power Supply

Gerard R. Lekhema, Willem A. Cronje, Ian Korir

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031802. doi: https://doi.org/10.1115/1.4046353

Abstract

View articletitled, High Reliability Microgrid for a Nuclear Facility Emergency Power Supply

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Topics: Microgrids , Reliability , Batteries , Diesel generators , Failure , Risk-based design , Emergency power , Probability , Nuclear power stations

Radiation Science

Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things

M. Zorkany, Hassan F. Morsi

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031901. doi: https://doi.org/10.1115/1.4048113

Abstract

View articletitled, Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things

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Topics: Heat , Radioactive substances , Safety , Security , Transportation systems , Internet of things , Embedded systems , Sensors , Vehicles , Radiation (Physics)

Code and Regulatory Issues

Radiation-Induced Surface Wettability Enhancement of an Indium Tin Oxide and Titanium Oxide Film-Coated Sapphire

Kai Wang, Hui Liang, Junya Inoue, Nejdet Erkan, Koji Okamoto

ASME J of Nuclear Rad Sci. July 2022, 8(3): 032001. doi: https://doi.org/10.1115/1.4051791

Abstract

View articletitled, Radiation-Induced Surface Wettability Enhancement of an Indium Tin Oxide and Titanium Oxide Film-Coated Sapphire

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Topics: Gamma rays , Irradiation (Radiation exposure) , Sapphire , Radiation (Physics) , Titanium dioxide , Electron beams , Titanium , Nucleate boiling