Volume 6 Issue 3 | ASME J. of Nuclear Rad Sci.

Guest Editorial

Special Section: Selected Papers From the Ninth International Symposium on Supercritical Water-Cooled Reactors

Laurence Leung, Ph.D., David Guzonas, Ph.D., Thomas Schulenberg, Ph.D.

ASME J of Nuclear Rad Sci. July 2020, 6(3): 030301. doi: https://doi.org/10.1115/1.4046827

View articletitled, Special Section: Selected Papers From the Ninth International Symposium on Supercritical Water-Cooled Reactors

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Topics: Supercritical water reactors , Water

Special Section: Selected Papers from the Ninth International Symposium on Supercritical Water-Cooled Reactors

Formation of Local, Transient “Acid Spikes” in the Fast Neutron Radiolysis of Supercritical Water at 400 °C: A Potential Source of Corrosion in Supercritical Water-Cooled Reactors?

Md Mohsin Patwary, Sunuchakan Sanguanmith, Jintana Meesungnoen, Jean-Paul Jay-Gerin

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031101. doi: https://doi.org/10.1115/1.4044409

Abstract

View articletitled, Formation of Local, Transient “Acid Spikes” in the Fast Neutron Radiolysis of Supercritical Water at 400 °C: A Potential Source of Corrosion in Supercritical Water-Cooled Reactors?

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Topics: Neutrons , Water , Corrosion , Transients (Dynamics) , Protons , Simulation , Chemistry , Density

General Corrosion of Chromium-Coated Zirconium- and Titanium-Based Alloys in Supercritical Water at 500 °C

K. Khumsa-Ang, M. Edwards, S. Rousseau

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031102. doi: https://doi.org/10.1115/1.4045387

Abstract

View articletitled, General Corrosion of Chromium-Coated Zirconium- and Titanium-Based Alloys in Supercritical Water at 500 °C

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Topics: Alloys , Coatings , Corrosion , Titanium , Water , Weight (Mass) , Zirconium

Study on Calculation Difference of the SCWR Core Steady-State Analysis Code

Lianjie Wang, Lei Yao, Ping Yang, Di Lu, Wenbo Zhao

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031103. doi: https://doi.org/10.1115/1.4044408

Abstract

View articletitled, Study on Calculation Difference of the SCWR Core Steady-State Analysis Code

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Topics: Density , Feedback , Steady state , Supercritical water reactors , Thermal hydraulics , Water , Flow (Dynamics)

Numerical Investigation on Heat Transfer of Supercritical Water With a Variable Turbulent Prandtl Number Model

Xiangfei Kong, Dongfeng Sun, Lingtong Gou, Siqi Wang, Nan Yang, Huixiong Li

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031104. doi: https://doi.org/10.1115/1.4046025

Abstract

View articletitled, Numerical Investigation on Heat Transfer of Supercritical Water With a Variable Turbulent Prandtl Number Model

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Topics: Heat transfer , Turbulence , Water , Wall temperature , Prandtl number

Numerical Simulation of a Steam Injector for Passive Residual Heat Removal

Thomas Schulenberg, David Heinze

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031105. doi: https://doi.org/10.1115/1.4045692

Abstract

View articletitled, Numerical Simulation of a Steam Injector for Passive Residual Heat Removal

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Topics: Ejectors , Flow (Dynamics) , Nozzles , Pressure , Shock (Mechanics) , Steam , Condensation , Computer simulation , Water , Two-phase flow

Research on Improved Simplified SCWR Assembly and Core Design

Yao Lei, Xia Bangyang, Lu Di, Wang Lianjie

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031106. doi: https://doi.org/10.1115/1.4046261

Abstract

View articletitled, Research on Improved Simplified SCWR Assembly and Core Design

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Topics: Coolants , Design , Fuels , Manufacturing , Supercritical water reactors , Water , Flow (Dynamics) , Temperature

Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

Attila Kiss, Bence Mervay

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031107. doi: https://doi.org/10.1115/1.4046842

Abstract

View articletitled, Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

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Topics: Flow (Dynamics) , Fuel rods , Geometry , Wire , Wall temperature , Fuels , Corners (Structural elements) , Temperature

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

Attila Kiss, Béla Hegyesi, Patrik Richárd Ujváry, András Szabolcs Ványi, Gyula Csom

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031108. doi: https://doi.org/10.1115/1.4046904

Abstract

View articletitled, About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

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Topics: Computational fluid dynamics , Flow (Dynamics) , Fluids , Fuels , Manufacturing , Supercritical water reactors , Temperature , Fuel rods , Boundary-value problems , Wire

Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C

Bingjie Xiao, Nick Tepylo, Xiao Huang, Zhangjian Zhou, Sami Penttilä

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031109. doi: https://doi.org/10.1115/1.4044530

Abstract

View articletitled, Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C

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Topics: Alloys , Oxidation , Steam , Steel , Superheating , Weight (Mass) , Spallation (Nuclear physics)

Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

Petra Pónya, Gyula Csom, Sándor Fehér

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031110. doi: https://doi.org/10.1115/1.4046354

Abstract

View articletitled, Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

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Topics: Coolants , Flow (Dynamics) , Irradiation (Radiation exposure) , Neutron flux , Neutrons , Reactor vessels , Supercritical water reactors , Design , Fuels , Temperature

A Numerical Study of Turbulent Upward Flow of Super Critical Water in a 2 × 2 Rod Bundle With Nonuniform Heating

Bo Liu, Shuisheng He, Charles Moulinec, Juan Uribe

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031111. doi: https://doi.org/10.1115/1.4046260

Abstract

View articletitled, A Numerical Study of Turbulent Upward Flow of Super Critical Water in a 2 × 2 Rod Bundle With Nonuniform Heating

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Topics: Flow (Dynamics) , Fuel rods , Turbulence , Water , Buoyancy , Heating , Simulation , Temperature , Heat transfer , Computational fluid dynamics

A Critical Review of the Physics and Modeling of Deteriorated Heat Transfer in Supercritical Fluids

Andrew W. Copping, Metin I. Yaras

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031112. doi: https://doi.org/10.1115/1.4046654

Abstract

View articletitled, A Critical Review of the Physics and Modeling of Deteriorated Heat Transfer in Supercritical Fluids

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Topics: Buoyancy , Flow (Dynamics) , Heat transfer , Modeling , Turbulence

Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR

A. Nava-Dominguez

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031113. doi: https://doi.org/10.1115/1.4046783

Abstract

View articletitled, Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR

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Topics: Flow (Dynamics) , Friction , Pressure drop , Wire , Fuels , Water , Supercritical water reactors , Manufacturing , Pipes

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

A. Nava Domínguez, Y. F. Rao, T. Beuthe

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031114. doi: https://doi.org/10.1115/1.4046843

Abstract

View articletitled, Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

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Topics: Cladding systems (Building) , Coolants , Flow (Dynamics) , Fuels , Heat losses , Heat transfer , Manufacturing , Supercritical water reactors , Temperature , Modeling

Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors

T. Beuthe, A. Vasić, H. Zahlan, A. Nava Domínguez

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031115. doi: https://doi.org/10.1115/1.4047288

Abstract

View articletitled, Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors

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Topics: Heat transfer , Modeling , Pressure , Supercritical water reactors , Temperature , Simulation , Accidents , Testing , Water , Transients (Dynamics)

Research Papers

Next Generation/Advanced Reactors

Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs

Sumit V. Prasad, A. K. Nayak

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031301. doi: https://doi.org/10.1115/1.4044410

Abstract

View articletitled, Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs

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Topics: Boiling , Critical heat flux , Flat plates , Heavy water reactors , Water , Heat , Subcooling

Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

Luis M. Palomino, Mohamed S. El-Genk, Timothy M. Schriener

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031302. doi: https://doi.org/10.1115/1.4045297

Abstract

View articletitled, Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

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Topics: Cladding systems (Building) , Emissions , Fuels , Neutrons , Photons , Steel , Vessels , Storage , Radioactivity , Isotopes

Thermal Hydraulics and CFD

The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors

M. D. Tucker, D. R. Novog

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031401. doi: https://doi.org/10.1115/1.4045485

Abstract

View articletitled, The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors

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Topics: Algorithms , Cross section (Physics) , Feedback , Fuels , Simulation , Uncertainty , Uncertainty analysis , Uranium , Physics , Diffusion (Physics)

Reactor Physics

Simulation of IAEA Reactivity Initiated Transient Benchmarks Using Reactor Dynamics Code “REDAC”

Vivek A. Kale, Obaidurrahman K.

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031501. doi: https://doi.org/10.1115/1.4045394

Abstract

View articletitled, Simulation of IAEA Reactivity Initiated Transient Benchmarks Using Reactor Dynamics Code “REDAC”

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Topics: Coolants , Fuels , Neutrons , Simulation , Temperature , Transients (Dynamics) , Dynamics (Mechanics) , Thermal hydraulics

Determination of β_eff for ININ^'s TRIGA Reactor

J. Galicia-Aragón, R. Raya-Arredondo, H. S. Cruz-Galindo

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031502. doi: https://doi.org/10.1115/1.4046355

Abstract

View articletitled, Determination of βeff for ININ's TRIGA Reactor

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Topics: Fuels , Neutrons , Isotopes , Uranium , Particulate matter

Nuclear Fuels/Cycles and Materials

Mitigation of End-Flux-Peaking in Fresh CANDU Fuel Bundles Using Neutron Absorbers

Dylan J. C. Pierce, Paul K. Chan, Wei Shen

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031601. doi: https://doi.org/10.1115/1.4045673

Abstract

View articletitled, Mitigation of End-Flux-Peaking in Fresh CANDU Fuel Bundles Using Neutron Absorbers

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Topics: Fuels , Neutrons

Plant Systems, O&M, and Life Cycle

Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method

Edward Shitsi, Emmanuel K. Boafo, Felix Ameyaw, H. C. Odoi

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031801. doi: https://doi.org/10.1115/1.4045803

Abstract

View articletitled, Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method

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Topics: Failure , Feedwater , High pressure (Physics) , Pumps , Safety , Valves , Nuclear power stations

Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

Mithil Parekh, Yuan Gao, Mariana Jockenhoevel-Barttfeld, Karl Waedt

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031802. doi: https://doi.org/10.1115/1.4046262

Abstract

View articletitled, Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

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Topics: Computer software , Failure , Instrumentation , Modeling , Nuclear power stations , Safety , Control systems , Hardware , Three-dimensional modeling

Technical Brief

A Resonated and Synchrophased Three Beams Neutron Cancer Therapy Installation

Nassar H. S. Haidar

ASME J of Nuclear Rad Sci. July 2020, 6(3): 034501. doi: https://doi.org/10.1115/1.4045395

Abstract

View articletitled, A Resonated and Synchrophased Three Beams Neutron Cancer Therapy Installation

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Topics: Density , Neutrons , Waves , Neutron beams , Patient treatment , Cancer

Issues

Guest Editorial

Special Section: Selected Papers from the Ninth International Symposium on Supercritical Water-Cooled Reactors

Research Papers

Next Generation/Advanced Reactors

Thermal Hydraulics and CFD

Reactor Physics

Nuclear Fuels/Cycles and Materials

Plant Systems, O&M, and Life Cycle

Technical Brief

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