Journal of Nuclear Engineering and Radiation Science
Browse by
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
-
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 ... -
Spatial Distribution Assay of Active Neutron Counting
(The American Society of Mechanical Engineers (ASME), 2024)In response to the nuclear material accounting and control system, uranium or plutonium mass and also the isotope abundance should be quantified comprehensively. Commonly, in nuclear safeguards and nuclear security field, ... -
Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates
(The American Society of Mechanical Engineers (ASME), 2024)In this study, heat fluxes qc for condensation from steam and air mixtures on vertical flat plates were evaluated by using existing experimental data and qc correlations, in order to provide one of boundary conditions for ... -
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
(The American Society of Mechanical Engineers (ASME), 2024)Ensuring data reliability is becoming increasingly important for further applications of artificial intelligence, internet of things, and digital twins. One promising technology for ensuring data reliability is data ... -
Development of Risk Informed Aging Management Program in Decommissioning
(The American Society of Mechanical Engineers (ASME), 2024)This paper proposes to solve the issues related to aging management program (AMP) during the decommissioning phase by using risk information. The AMP for the decommissioning plants has not been established while the number ... -
K-Edge Measurement Technology Simulation Model Design
(The American Society of Mechanical Engineers (ASME), 2025)The K-edge technique is a nondestructive analysis (NDA) method that provides key data for nuclear material accountancy, mainly for the measurement of U and Pu concentrations in spent fuel reprocessing processes, with an ... -
Investigating the Suitability of Cu2ZnSnS4 Thin Films for Gamma Radiation Dosimetry Applications in Nonmedical Environments
(The American Society of Mechanical Engineers (ASME), 2024)The need for the replacement of cadmium, indium, and tellurium in their compounds for sensor applications is a novel study. The copper zinc tin sulfide (Cu2ZnSnS4) thin films were synthesized from Cu (99.99%), Sn (99.99%), ... -
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
(The American Society of Mechanical Engineers (ASME), 2024)The Zircaloy alloy system (1.2–1.7 wt.% Sn) provides an excellent basis to study the effect of temperature on Pourbaix diagrams, as Zircaloy fuel rods in a CANadian Deuterium UraniumTM (CANDU) reactor are exposed to an ... -
Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation
(The American Society of Mechanical Engineers (ASME), 2025)One of the most critical components of super critical water reactor (SCWR) plant is pipe bend, carrying massive volume of supercritical water. Because of its intense fluctuation of velocity and pressure, it can exhibit ... -
Silicate Glass Reinforced by Bi and B as Efficient Protective Materials Against Gamma Rays and Neutrons
(The American Society of Mechanical Engineers (ASME), 2025)The growing role of nuclear radiation in various domains necessitated a continuous development in enhancing the efficiency of radiation shielding materials. Generally, a shield that can attenuate thermal and fast neutrons ... -
Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin
(The American Society of Mechanical Engineers (ASME), 2024)To meet future energy demand, while producing safe, reliable, and carbon-free energy, nuclear reactors will be needed. To make next-generation reactors more economically competitive, the Artificial Intelligence and Machine ...