Volume 9 Issue 1 | ASME J. of Nuclear Rad Sci.

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Editorial

Igor L. Pioro

ASME J of Nuclear Rad Sci. January 2023, 9(1): 010201. doi: https://doi.org/10.1115/1.4056024

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Topics: China , Nuclear engineering , Nuclear reactors , Radiation (Physics) , Safety , Statistics

Reviewer's Recognition

ASME J of Nuclear Rad Sci. January 2023, 9(1): 010202. doi: https://doi.org/10.1115/1.4056261

Extract

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Guest Editorial

On Eight Years of the NERS and Vision of the Nuclear Engineering Division

Jovica Riznic

ASME J of Nuclear Rad Sci. January 2023, 9(1): 010301. doi: https://doi.org/10.1115/1.4056139

Extract

View articletitled, On Eight Years of the NERS and Vision of the Nuclear Engineering Division

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Topics: Nuclear engineering

Greetings from the Chair of the JSME Power Energy Systems Division

Hitoshi Asano

ASME J of Nuclear Rad Sci. January 2023, 9(1): 010302. doi: https://doi.org/10.1115/1.4056050

Extract

View articletitled, Greetings from the Chair of the JSME Power Energy Systems Division

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Topics: Energy / power systems , Japan Society of Mechanical Engineers , Nuclear engineering

Research Papers

Thermal Hydraulics and CFD

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

Michio Murase, Tomonori Suzuki, Yoichi Utanohara, Toshiya Takaki

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011401. doi: https://doi.org/10.1115/1.4054842

Abstract

View articletitled, Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

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Topics: Flow (Dynamics) , Steam , Temperature , Turbulence , Condensation , Flat plates , Boundary layer turbulence , Computational fluid dynamics , Computation

Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels

Chenguang Li, Krishna Podila, Blair P. Bromley, Yanfei Rao

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011402. doi: https://doi.org/10.1115/1.4054943

Abstract

View articletitled, Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels

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Topics: Computational fluid dynamics , Fuels , Modeling , Pressure , Pressurized water reactors , Manufacturing , Flow (Dynamics) , Small modular reactors

Experimental Evaluation of Two-Phase Heat Transfer Coefficient Under Oscillatory Flow Conditions and Correlation Development

Rakesh Kumar, Dinesh K. Chandraker, Arnab Dasgupta, Arun K. Nayak

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011403. doi: https://doi.org/10.1115/1.4055090

Abstract

View articletitled, Experimental Evaluation of Two-Phase Heat Transfer Coefficient Under Oscillatory Flow Conditions and Correlation Development

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Topics: Flow (Dynamics) , Heat transfer coefficients , Oscillations

Reactor Physics

Neutronic Evaluation of Light Water Reactor-Based Small Modular Reactor With Transuranic Fuel and Comparison With Different Core Configuration of UO₂ and Mixed Oxide Fuel

Sushanta Biswas, Md. Hossain Sahadath, Nazia Rahim Ananya

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011501. doi: https://doi.org/10.1115/1.4054208

Abstract

View articletitled, Neutronic Evaluation of Light Water Reactor-Based Small Modular Reactor With Transuranic Fuel and Comparison With Different Core Configuration of UO2 and Mixed Oxide Fuel

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Topics: Atoms , Fuels , Nuclear fission

Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes

Thanh Mai Vu, Donny Hartanto

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011502. doi: https://doi.org/10.1115/1.4054080

Abstract

View articletitled, Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes

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Topics: Cermets , Uncertainty , Ceramics

Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors

Huiping V. Yan, Blair P. Bromley

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011503. doi: https://doi.org/10.1115/1.4054841

Abstract

View articletitled, Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors

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Topics: Fuels , Heavy water reactors , Uranium

Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors

Daniel T. Wojtaszek, Blair P. Bromley

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011504. doi: https://doi.org/10.1115/1.4055009

Abstract

View articletitled, Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors

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Topics: Fuels , Uranium , Neutrons

Nuclear Safety/Security and Beyond Design Basis Events

Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

M. D. Shah, A. C. Morreale, L. S. Lebel

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011701. doi: https://doi.org/10.1115/1.4055258

Abstract

View articletitled, Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

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Topics: Accidents , Containment , Failure , Pressure , Water

Plant Systems, O&M, and Life Cycle

Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant

Jindong Zhang, Chongzhi Wu

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011801. doi: https://doi.org/10.1115/1.4054878

Abstract

View articletitled, Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant

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Topics: Construction , Design , Evaluation methods , Nuclear power stations , Failure mechanisms , Nuclear power

RAW Management and Decommissioning

Study of Radium Behavior in Contact With Calcium-Silicate-Hydrates

Jana Kittnerová, Barbora Drtinová, Karel Štamberg, Guido Deissmann, Steve Lange, Nick Evans

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011901. doi: https://doi.org/10.1115/1.4055160

Abstract

View articletitled, Study of Radium Behavior in Contact With Calcium-Silicate-Hydrates

Supplementary data

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Topics: Radium , Sorption , Radioisotopes

Radiation Science

Transient Analysis of Passive Autocatalytic Hydrogen Recombiners Using Computational Fluid Dynamics

Ahsan Khan, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi

ASME J of Nuclear Rad Sci. January 2023, 9(1): 012001. doi: https://doi.org/10.1115/1.4054117

Abstract

View articletitled, Transient Analysis of Passive Autocatalytic Hydrogen Recombiners Using Computational Fluid Dynamics

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Topics: Computational fluid dynamics , Hydrogen , Temperature , Plates (structures)

Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites

A. M. Osman

ASME J of Nuclear Rad Sci. January 2023, 9(1): 012002. doi: https://doi.org/10.1115/1.4054547

Abstract

View articletitled, Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites

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Topics: Composite materials , Density , Neutrons , Polymer composites , Relaxation (Physics) , Photons , Cross section (Physics) , Aluminum , Boron

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

Rofida Hamad Khlifa, Nicolay N. Nikitenkov

ASME J of Nuclear Rad Sci. January 2023, 9(1): 012003. doi: https://doi.org/10.1115/1.4055012

Abstract

View articletitled, Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

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Topics: Boron , Coatings , Fuels , Temperature , Cladding systems (Building) , Neutrons , Accidents

Applicability of the Dose Spiking Electron Paramagnetic Resonance Method for the Quantitative Measurements of Low Doses in Alanine Dosimetry

Lekhnath Ghimire, Edward Waller

ASME J of Nuclear Rad Sci. January 2023, 9(1): 012004. doi: https://doi.org/10.1115/1.4055010

Abstract

View articletitled, Applicability of the Dose Spiking Electron Paramagnetic Resonance Method for the Quantitative Measurements of Low Doses in Alanine Dosimetry

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Topics: Accuracy and precision , Anisotropy , Dosimetry , Electron paramagnetic resonance , Electrons , Errors , Microwaves , Signals , Cavities , Spectra (Spectroscopy)

Technology Reviews

Methodology and Instrumentation for Electron Paramagnetic Resonance Dosimetry With Tooth Enamel

Lekhnath Ghimire, Edward Waller

ASME J of Nuclear Rad Sci. January 2023, 9(1): 014001. doi: https://doi.org/10.1115/1.4055162

Abstract

View articletitled, Methodology and Instrumentation for Electron Paramagnetic Resonance Dosimetry With Tooth Enamel

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Topics: Dosimetry , Electron paramagnetic resonance , Enameling , Signals

Technical Briefs

Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector

Basim Khalaf Rejah

ASME J of Nuclear Rad Sci. January 2023, 9(1): 014501. doi: https://doi.org/10.1115/1.4054619

Abstract

View articletitled, Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector

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Topics: Sensors , Soil , Uranium , Nuclear track detectors , Bridges (Structures) , Rocks , Radiation (Physics) , Water

Characterization of the Degradation of HEPA Filters Protected by Different Spark Arrestors for Various Cutting Means and Cutting Conditions

Bourrous Soleiman, Barrault Mathieu, Ricciardi Laurent

ASME J of Nuclear Rad Sci. January 2023, 9(1): 014502. doi: https://doi.org/10.1115/1.4054942

Abstract

View articletitled, Characterization of the Degradation of HEPA Filters Protected by Different Spark Arrestors for Various Cutting Means and Cutting Conditions

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Topics: Cutting , Filters , Filtration , Plasmas (Ionized gases) , Particle size , HEPA filters , Particulate matter , Tool grinders , Aerosols , Cutting tools