Journal of Nuclear Engineering and Radiation Science
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EISSN:2332-8975|ISSN:2332-8983|Disc:The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government|Priority:4|Publisher:American Society of Mechanical Engineers|
Recent Submissions
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Adjuster Absorber Rods Return to Service at PLNGS
(The American Society of Mechanical Engineers (ASME), 2025)The original CANDU® 600 design utilizes adjuster absorber (AA) rods to flatten the flux shape in the reactor core optimize power output, compensate for fuel burnup, provide excess reactivity to overcome 135Xe buildup ... -
Radiological Diversification in Indoor Radon and Thoron Levels in Correlations With Various Factors in Residential Dwellings
(The American Society of Mechanical Engineers (ASME), 2025)Human exposure to indoor radon, thoron, and their progenies has become a serious problem throughout the world. In the current research, assessment of indoor radon and thoron and their effect on human beings have been ... -
Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code
(The American Society of Mechanical Engineers (ASME), 2025)Nuclear reactor startup and shutdown procedures must be carried out with great care and efficiency. To ensure correct reactor operation, it is crucial to make and maintain the reactor critical during startup and subcritical ... -
Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor
(The American Society of Mechanical Engineers (ASME), 2025)The supercritical water-cooled reactor (SCWR) is one of the six concepts selected by the generation-IV international forum (GIF) for future research. This technology is a natural evolutionary step of the current water-cooled ... -
Research on the Impact of Cosmic Ray Induced Neutron Background Based on Nuclear Safeguards Equipment
(The American Society of Mechanical Engineers (ASME), 2025)Neutron detection technology is one of the most commonly used techniques for nondestructive analysis of nuclear materials in nuclear safeguards and verification. During the neutron detection measurement of nuclear materials, ... -
Master (Spark Plasma) Sintering Curve of UO2 and UO2-10 Vol. % Mo Fuel Material
(The American Society of Mechanical Engineers (ASME), 2025)UO2-molybdenum (Mo) composites are being considered for accident tolerant fuel (ATF) applications in commercial nuclear reactors. In this study, UO2-10 vol. % Mo was fabricated using spark plasma sintering (SPS), where the ... -
Mechanical Properties and Radon Gas Emanation Analysis of Composite Bricks Reinforced With Cellulose Nanofibrils and Graphene Oxide
(The American Society of Mechanical Engineers (ASME), 2025)Graphene oxide (GO) and cellulose nanofibrils from pineapple leaf (PLCNF) and sugarcane bagasse (SCBCNF) have been utilized to observe the mechanical enhancement in composite bricks and radon reduction levels. The cellulose ... -
Resolving of Transportation Issue With High Activity Positron Emission Tomography Radiotracer Source to Long Distance Medical Imaging Centers
(The American Society of Mechanical Engineers (ASME), 2025)In Indian scenario, single positron emission tomography (PET) radiotracer isotope production center is catering PET radiopharmaceuticals to multiple medical imaging centers, located far away from the production center. ... -
A Mathematical Model Design for Pu Content Analyzed by 244Cm in Spent Fuel of Fast Reactors
(The American Society of Mechanical Engineers (ASME), 2025)Pyroprocessing is employed in the reprocessing of integral fast reactors (IFRs). According to China's domestic regulations of nuclear material control, analysis of the content of uranium (U) and plutonium (Pu) should be ... -
Evaluation of Radiation Shielding Effectiveness of Some Metallic
(The American Society of Mechanical Engineers (ASME), 2025)Several nuclear shielding parameters were evaluated for surgical stainless steel -
Development of an Artificial Intelligence-Based Predictive Anomaly Detection System to Nuclear Power Plant
(The American Society of Mechanical Engineers (ASME), 2024)In a large-scale plant such as a nuclear power plant, thousands of process values are measured for the purpose of monitoring the plant performance and the system health. It is difficult for plant operators to constantly ... -
Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
(The American Society of Mechanical Engineers (ASME), 2024)Gamma-ray imaging is a tool that has grown in importance in the applications of non-destructive assay (NDA) for radioactive survey and analysis of nuclear facilities. Imaging techniques have shown great promise in providing ... -
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
(The American Society of Mechanical Engineers (ASME), 2024)To address the deficiencies in the fillet welding position of the clad plates in the simulated spent fuel pool, an underwater test platform was designed for local dry laser fillet welding under both normal and high-pressure ... -
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
(The American Society of Mechanical Engineers (ASME), 2024)The fuel bundles in coolant systems of CANDU™ reactors operate between 250 and 310 °C (523 and 583 K). Given these extreme conditions and because of its neutronic properties, zirconium and Zircaloy-4 are used in these ... -
Numerical Analysis of Gas Generation and Migration in a Radioactive Waste Disposal Cell of a Deep Geological Repository
(The American Society of Mechanical Engineers (ASME), 2024)In a deep geological repository (DGR) for the long-term disposal of radioactive waste, gases (e.g., hydrogen (H2), carbon dioxide (CO2) and methane (CH4)) can be generated through a number of processes, such as corrosion ... -
Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in Pressurized Water Reactor Sub Channel by Direct Numerical Simulation
(The American Society of Mechanical Engineers (ASME), 2024)Subchannel analysis codes are presently a requirement for design and safety analysis of nuclear reactors. Among the crucial inputs for these codes, the turbulent mixing factor holds particular significance. However, acquiring ... -
Use of Modeling as an Enabler for Cross-Topic Knowledge Management and Ontologies to Support Return of Experience and Replicability of Large Nuclear Projects
(The American Society of Mechanical Engineers (ASME), 2024)Nuclear projects often produce and consume a large amount of knowledge. Capitalization on this knowledge constitutes a significant way to increase efficiency on subsequent projects for any stakeholder. In this study, ... -
Survey Analysis of Potential Nuclear Safety Research of Thailand for International Research Collaborative Reinforcement in the 2020s
(The American Society of Mechanical Engineers (ASME), 2024)To achieve the long-term challenge of nuclear energy public acceptance in Thailand, nuclear safety research needed to be properly determined in both domestic and international directions, especially in the 2020s which was ... -
Investigation of Metal–H2O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions
(The American Society of Mechanical Engineers (ASME), 2024)Metals used in aqueous environments where high temperatures and pressures are present are susceptible to corrosion. This is the case for nuclear power plants, especially CANDUTM reactors, where the liquid water systems can ... -
Impact of the Abrasive Solution Heating Process With Different Techniques on the Etching Parameters for the SSNTD (CN-85)
(The American Society of Mechanical Engineers (ASME), 2024)The presented work aims to compare and analyze the impact of the abrasive solution heating process using three different techniques on the etching parameters for the solid-state nuclear track detector (SSNTD) (CN-85). Water ...