Volume 6 Issue 2 | ASME J. of Nuclear Rad Sci.

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Guest Editorial

Professor Jyeshtharaj Bhalchandra Joshi on His 70th Birthday

Mohamed M. Awad, Sanjoy Banerjee, Masahiro Kawaji

ASME J of Nuclear Rad Sci. April 2020, 6(2): 020301. doi: https://doi.org/10.1115/1.4045590

Extract

View articletitled, Professor Jyeshtharaj Bhalchandra Joshi on His 70th Birthday

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Topics: Engineering teachers

Special Section: ICONE-26

Guoqiang Wang, Ph.D., Shripad Revankar, Ph.D., Leon Cizelj, Ph.D., Robert Stakenborghs, Jovica Riznic, Ph.D.

ASME J of Nuclear Rad Sci. April 2020, 6(2): 020302. doi: https://doi.org/10.1115/1.4046121

Extract

View articletitled, Special Section: ICONE-26

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Topics: Nuclear engineering , Radiation (Physics) , China , Governments , Nuclear industry

Special Papers

Performance Simulation to Understand the Effects of Multifluid Scaling of Gas Turbine Components for Generation IV Nuclear Power Plants

Emmanuel O. Osigwe, Arnold Gad-Briggs, Theoklis Nikolaidis, Pericles Pilidis, Suresh Sampath

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021101. doi: https://doi.org/10.1115/1.4044406

Abstract

View articletitled, Performance Simulation to Understand the Effects of Multifluid Scaling of Gas Turbine Components for Generation IV Nuclear Power Plants

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Topics: Design , Fluids , Gas turbines , Nuclear power stations , Simulation , Flow (Dynamics) , Pressure , Mach number , Compressors , Turbines

Performance Analyses and Evaluation of Co₂ and N₂ as Coolants in a Recuperated Brayton Gas Turbine Cycle for a Generation IV Nuclear Reactor Power Plant

Emmanuel O. Osigwe, Arnold Gad-Briggs, Theoklis Nikolaidis, Pericles Pilidis, Suresh Sampath

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021102. doi: https://doi.org/10.1115/1.4043589

Abstract

View articletitled, Performance Analyses and Evaluation of Co2 and N2 as Coolants in a Recuperated Brayton Gas Turbine Cycle for a Generation IV Nuclear Reactor Power Plant

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Topics: Carbon dioxide , Compressors , Cycles , Fluids , Power stations , Pressure , Temperature , Design , Turbines , Generation IV reactors

Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions

René Manthey, Alexander Knospe, Carsten Lange, Christoph Schuster, Antonio Hurtado

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021103. doi: https://doi.org/10.1115/1.4044846

Abstract

View articletitled, Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions

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Topics: Pressure , Principal component analysis , Boiling , Stability , Cooling

Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger

Angel Papukchiev

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021104. doi: https://doi.org/10.1115/1.4045074

Abstract

View articletitled, Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger

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Topics: Flow (Dynamics) , Fluids , Heat exchangers , Heat transfer , Modeling , Simulation , Temperature , Transients (Dynamics) , Turbulence , Computational fluid dynamics

An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor

Indarta Kuncoro Aji, Tokushima Tatsuya, Motoyasu Kinoshita, Tomio Okawa

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021105. doi: https://doi.org/10.1115/1.4045180

Abstract

View articletitled, An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor

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Topics: Cylinders , Molten salt reactors , Temperature , Valves , Brass (Metal) , Thermal conductivity , Melting , Computer simulation , Copper , Fuels

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

Abstract

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

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

External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET

Kai Kosowski, Marcus Seidl

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021107. doi: https://doi.org/10.1115/1.4045034

Abstract

View articletitled, External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET

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Topics: Accidents , Coolants , Cooling , Diesel engines , Emergencies , Flow (Dynamics) , Hazards , Heat , Leakage , Pressure

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

Abstract

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

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

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

Abstract

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

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Topics: Heat transfer , Fluids , Water

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

Abstract

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

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

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

A. M. Shehada, V. M. Golovkov

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021111. doi: https://doi.org/10.1115/1.4045234

Abstract

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

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Topics: Neutrons , Neutron sources , Deuterons

Application of Wireless Technologies in a Nuclear Plant: Evaluation of Electromagnetic Propagation With Different Computational Techniques

Mauro Cappelli, Vanni Lopresto, Riccardo Cecchi, Gaetano Marrocco

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021112. doi: https://doi.org/10.1115/1.4044261

Abstract

View articletitled, Application of Wireless Technologies in a Nuclear Plant: Evaluation of Electromagnetic Propagation With Different Computational Techniques

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Topics: Electromagnetic fields , Nuclear power stations , Simulation , Waves , Electromagnetic wave propagation , Sensors

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Yuta Abe, Takuya Yamashita, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021113. doi: https://doi.org/10.1115/1.4045450

Abstract

View articletitled, Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

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Topics: Fuels , Heating , Manufacturing , Plasmas (Ionized gases) , Accidents , Temperature , Permeability , Melting , Blades

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

Abstract

View articletitled, Leakage Estimate in Nonuniformly Compressed Packing Rings

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

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

Abstract

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

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

A Study of the Reproducibility and Diversity of the Supply Chain in Manufacturing Hot Isostatically Pressed Type 316L Stainless Steel Components for the Civil Nuclear Sector

William Kyffin, David Gandy, Barry Burdett

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021116. doi: https://doi.org/10.1115/1.4044752

Abstract

View articletitled, A Study of the Reproducibility and Diversity of the Supply Chain in Manufacturing Hot Isostatically Pressed Type 316L Stainless Steel Components for the Civil Nuclear Sector

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Topics: ASTM International , Fracture toughness , Hot pressing , Manufacturing , Materials properties , Oxygen , Stainless steel , Supply chains , Temperature , Tensile strength

Research Papers

Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy

Emmanuel O. Osigwe, Arnold Gad-Briggs, Dodeye Igbong, Theoklis Nikolaidis, Pericles Pilidis

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021201. doi: https://doi.org/10.1115/1.4044260

Abstract

View articletitled, Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy

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Topics: Cycles , Pressure , Stress , Temperature , Flow (Dynamics) , Compressors , Power stations , Heat , Modeling , Closed-cycle gas turbines

General

Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors

Damian E. Ramajo, Santiago F. Corzo, Norberto M. Nigro

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021202. doi: https://doi.org/10.1115/1.4045121

Abstract

View articletitled, Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors

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Topics: Flow (Dynamics) , Fluids , Pipes , Pressure , Simulation , Water , Computational fluid dynamics , Geometry , Drainage , Computer simulation

Plant Systems, O&M, and Life Cycle

Exploring Synergy Among New Generation Technologies—Small Modular Reactor, Energy Storage, and Distributed Generation: A Strong Case for Remote Communities

K. A. Joshi, B. Poudel, R. Gokaraju

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021801. doi: https://doi.org/10.1115/1.4045122

Abstract

View articletitled, Exploring Synergy Among New Generation Technologies—Small Modular Reactor, Energy Storage, and Distributed Generation: A Strong Case for Remote Communities

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Topics: Distributed power generation , Energy storage , Small modular reactors , Stress , Generators , Modeling

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Xinyu Zhou, Zhouyu Liu, Lu Cao, Liangzhi Cao, Hongchun Wu, Yu Han, Chuntao Tang

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021901. doi: https://doi.org/10.1115/1.4045035

Abstract

View articletitled, Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

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Topics: Errors , Geometry , Interpolation , Polynomials , Octrees , Sampling methods , Virtual reality

Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor

Hai Quan Ho, Yuki Honda, Shimpei Hamamoto, Toshiaki Ishii, Shoji Takada, Nozomu Fujimoto, Etsuo Ishitsuka

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021902. doi: https://doi.org/10.1115/1.4044529

Abstract

View articletitled, Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor

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Topics: Irradiation (Radiation exposure) , Neutrons , Silicon , Solar cells , High temperature , Particulate matter

Guest Editorial

Professor Jyeshtharaj Bhalchandra Joshi on His 70th Birthday

Special Section: ICONE-26

Special Papers

Performance Simulation to Understand the Effects of Multifluid Scaling of Gas Turbine Components for Generation IV Nuclear Power Plants

Performance Analyses and Evaluation of Co₂ and N₂ as Coolants in a Recuperated Brayton Gas Turbine Cycle for a Generation IV Nuclear Reactor Power Plant

Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions

Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger

An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor

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

External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET

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

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

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

Application of Wireless Technologies in a Nuclear Plant: Evaluation of Electromagnetic Propagation With Different Computational Techniques

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Leakage Estimate in Nonuniformly Compressed Packing Rings

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

A Study of the Reproducibility and Diversity of the Supply Chain in Manufacturing Hot Isostatically Pressed Type 316L Stainless Steel Components for the Civil Nuclear Sector

Research Papers

Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy

General

Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors

Plant Systems, O&M, and Life Cycle

Exploring Synergy Among New Generation Technologies—Small Modular Reactor, Energy Storage, and Distributed Generation: A Strong Case for Remote Communities

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor

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