Topics: Energy budget (Physics) , Errors , Flow (Dynamics) , Instrumentation , Temperature measurement , Measurement uncertainty , Uncertainty , Sensors , Temperature , Nuclear power stations

Thermal Hydraulics and CFD

Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates

Michio Murase, Toshiya Takaki

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021401. doi: https://doi.org/10.1115/1.4066343

Abstracts

View articletitled, Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates

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Topics: Condensation , Flat plates , Heat , Heat flux , Natural convection

Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

Armando Nava-Dominguez, Xianmin Huang, Songyu Liu

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021402. doi: https://doi.org/10.1115/1.4066523

Abstracts

View articletitled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

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Topics: Flow (Dynamics) , Fluids , Fuels , Heat transfer , Manufacturing , Pressure , Supercritical water reactors , Wall temperature , Water , Wire

Reactor Physics

TSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept

Eugene Masala, Laura Blomeley, David G. Watts, Blair P. Bromley

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021501. doi: https://doi.org/10.1115/1.4066404

Abstracts

View articletitled, TSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept

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Topics: Design , Fuels , Pressurized water reactors , Water , Boron

Nuclear Fuels/Cycles and Materials

Investigation of Metal–H₂O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions

Olga Y. Palazhchenko, Matthew H. Kaye

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021601. doi: https://doi.org/10.1115/1.4066339

Abstracts

View articletitled, Investigation of Metal–H2O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions

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Topics: Equilibrium (Physics) , Metals , Temperature , Vessels , Water , Instrumentation

Investigation of Metal-H₂O Systems at Elevated Temperatures: Part II. SnO_2(s) Solubility Data and New Sn Pourbaix Diagrams at 298.15 K and 358.15 K

Olga Y. Palazhchenko, Matthew H. Kaye

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021602. doi: https://doi.org/10.1115/1.4066340

Abstracts

View articletitled, Investigation of Metal-H2O Systems at Elevated Temperatures: Part II. SnO2(s) Solubility Data and New Sn Pourbaix Diagrams at 298.15 K and 358.15 K

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Topics: Temperature , Tin , Equilibrium (Physics)

Investigation of Metal–H₂O Systems at Elevated Temperatures: Part III: Solubility Data and New Zr Pourbaix Diagrams at 298.15 K and 373.15 K

Graeme J. Francolini, Matthew H. Kaye

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021603. doi: https://doi.org/10.1115/1.4066341

Abstracts

View articletitled, Investigation of Metal–H2O Systems at Elevated Temperatures: Part III: Solubility Data and New Zr Pourbaix Diagrams at 298.15 K and 373.15 K

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Topics: Temperature , Zirconium , Water

Review of Canadian Experience With the Fabrication of Thoria-Based Fuels for Advanced Reactors and Fuel Cycles for Long-Term Nuclear Energy Sustainability and Security

Germán Cota-Sanchez, Madalena S. Spencer, Kristin Leeder, Ike Dimayuga, Blair P. Bromley

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021604. doi: https://doi.org/10.1115/1.4067304

Abstract

View articletitled, Review of Canadian Experience With the Fabrication of Thoria-Based Fuels for Advanced Reactors and Fuel Cycles for Long-Term Nuclear Energy Sustainability and Security

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Topics: Fuels , Manufacturing , Density , Sintering , Uranium , Milling

Study on Repairing Defects in S32101 Duplex Stainless Steel Clad Plates for Spent Fuel Storage Pools in Nuclear Power Plants Using Underwater Local Dry Laser Fillet Welding With Filler Wire

Chenglu Zhao, Jialei Zhu, Fangtao Guo, Guixin Li, Congwei Li, Yushan Huang

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021605. doi: https://doi.org/10.1115/1.4067263

Abstract

View articletitled, Study on Repairing Defects in S32101 Duplex Stainless Steel Clad Plates for Spent Fuel Storage Pools in Nuclear Power Plants Using Underwater Local Dry Laser Fillet Welding With Filler Wire

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Topics: Lasers , Maintenance , Stainless steel , Welded joints , Welding , Wire , Nuclear power stations , Corrosion , Ferrites (Magnetic materials) , Spent fuel storage

Plant Systems, O&M, and Life Cycle

Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin

Andy Rivas, Gregory K. Delipei, Jason Hou

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021801. doi: https://doi.org/10.1115/1.4066777

Abstract

View articletitled, Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin

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Topics: Electricity (Physics) , Optimization , Probability , Maintenance , Steam , Safety , Temperature , Pumps , Uncertainty , Turbines

RAW Management and Decommissioning

Numerical Analysis of Gas Generation and Migration in a Radioactive Waste Disposal Cell of a Deep Geological Repository

Lan Sun, Liyan Qiu

ASME J of Nuclear Rad Sci. April 2025, 11(2): 021901. doi: https://doi.org/10.1115/1.4067173

Abstract

View articletitled, Numerical Analysis of Gas Generation and Migration in a Radioactive Waste Disposal Cell of a Deep Geological Repository

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Topics: Carbon dioxide , Pressure , Temperature , Rocks , Safety , Diffusion (Physics) , Computer simulation

Radiation Science

Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy

Valerie E. Nwadeyi, Adam Judy, Tad Whiteside

ASME J of Nuclear Rad Sci. April 2025, 11(2): 022001. doi: https://doi.org/10.1115/1.4066342

Abstracts

View articletitled, Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy

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Topics: Contamination , Filters , Gamma rays , Imaging , Radiation (Physics) , Radiation measurement , Pumps , Spectroscopy

Investigating the Suitability of Cu₂ZnSnS₄ Thin Films for Gamma Radiation Dosimetry Applications in Nonmedical Environments

Chidiebere Ogonnaya Obasi, Abubakar Soje Ahmad, Doris O. Okoroh, Echezona Simon Obi

ASME J of Nuclear Rad Sci. April 2025, 11(2): 022002. doi: https://doi.org/10.1115/1.4067015

Abstracts

View articletitled, Investigating the Suitability of Cu2ZnSnS4 Thin Films for Gamma Radiation Dosimetry Applications in Nonmedical Environments

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Topics: Gamma rays , Thin films , Energy gap , Dosimetry , Electrical properties

Technical Briefs

Spatial Distribution Assay of Active Neutron Counting

Yuqi Zhang, Xiaoming Xu, Yimei Cheng, Lixia He, Xiao Fan, Haocheng Zhao

ASME J of Nuclear Rad Sci. April 2025, 11(2): 024501. doi: https://doi.org/10.1115/1.4066883

Abstract

View articletitled, Spatial Distribution Assay of Active Neutron Counting

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Topics: Neutrons , Nuclear fission , Simulation , Cavities , Fittings

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Evaluation of radiation shielding effectiveness of some metallic alloys used in the nuclear facilities

ASME J of Nuclear Rad Sci

Effect of variable angular piping bends geometry on turbulent flow of supercritical water in an SCWR Plant piping network: a 3-D CFD investigation

ASME J of Nuclear Rad Sci

Uniform thermal expansion reactivity evaluation based on reactivity coefficient for sodium-cooled fast reactor

ASME J of Nuclear Rad Sci

Study on Repairing Defects in S32101 Duplex Stainless Steel Clad Plates for Spent Fuel Storage Pools in Nuclear Power Plants Using Underwater Local Dry Laser Fillet Welding With Filler Wire

ASME J of Nuclear Rad Sci (April 2025)

Review of Canadian Experience With the Fabrication of Thoria-Based Fuels for Advanced Reactors and Fuel Cycles for Long-Term Nuclear Energy Sustainability and Security

ASME J of Nuclear Rad Sci (April 2025)

Research Papers

Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in Pressurized Water Reactor Sub Channel by Direct Numerical Simulation

Impact of the Abrasive Solution Heating Process With Different Techniques on the Etching Parameters for the SSNTD (CN-85)

Special Papers

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Part 2—Extension to the Energy Balance Relation

Thermal Hydraulics and CFD

Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates

Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

Reactor Physics

TSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept

Nuclear Fuels/Cycles and Materials

Investigation of Metal–H₂O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions

Investigation of Metal-H₂O Systems at Elevated Temperatures: Part II. SnO_2(s) Solubility Data and New Sn Pourbaix Diagrams at 298.15 K and 358.15 K

Investigation of Metal–H₂O Systems at Elevated Temperatures: Part III: Solubility Data and New Zr Pourbaix Diagrams at 298.15 K and 373.15 K

Review of Canadian Experience With the Fabrication of Thoria-Based Fuels for Advanced Reactors and Fuel Cycles for Long-Term Nuclear Energy Sustainability and Security

Study on Repairing Defects in S32101 Duplex Stainless Steel Clad Plates for Spent Fuel Storage Pools in Nuclear Power Plants Using Underwater Local Dry Laser Fillet Welding With Filler Wire

Plant Systems, O&M, and Life Cycle

Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin

RAW Management and Decommissioning

Numerical Analysis of Gas Generation and Migration in a Radioactive Waste Disposal Cell of a Deep Geological Repository

Radiation Science

Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy

Investigating the Suitability of Cu₂ZnSnS₄ Thin Films for Gamma Radiation Dosimetry Applications in Nonmedical Environments

Technical Briefs

Spatial Distribution Assay of Active Neutron Counting

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