Browsing Journal of Nuclear Engineering and Radiation Science by Title
Now showing items 1-20 of 891
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60 Years in Motion: Short History of Nuclear Engineering Division
(The American Society of Mechanical Engineers (ASME), 2017)This paper presents a brief history of the ASME nuclear engineering division (NED) over the past 60 years. The technical interest of the Division naturally mirrored the main stages in nuclear-technology development and ... -
A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7 Rod Bundle
(The American Society of Mechanical Engineers (ASME), 2016)Heat transfer in supercritical water reactors (SCWRs) shows a complex behavior, especially when the temperatures of the water are near the pseudocritical value. For example, a significant deterioration of heat transfer may ... -
A Collaborative Experience: Implementation of an Optimized Tc-99m Generator Assembly Process
(The American Society of Mechanical Engineers (ASME), 2021)Technetium-99m (Tc-99m) has a 6-hr half-life making customer transportation times a challenge. Australian Nuclear Science and Technology Organization (ANSTO) health products group has overcome this by delivering the parent ... -
A Comparative Study of Ten Different Methods on Numerical Solving of Point Reactor Neutron Kinetics Equations
(The American Society of Mechanical Engineers (ASME), 2018)Point reactor neutron kinetics equations describe the time-dependent neutron density variation in a nuclear reactor core. These equations are widely applied to nuclear system numerical simulation and nuclear power plant ... -
A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors
(The American Society of Mechanical Engineers (ASME), 2020)The nuclear safety approach has to cover accident sequences involving core degradation in order to develop reliable mitigation strategies for both existing and future reactors. In particular, the long-term stabilization ... -
A Control Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead Cooled Fast Reactor
(The American Society of Mechanical Engineers (ASME), 2015)The most diffused neutronics modeling approach in controloriented simulators is pointwise kinetics. In the framework of developing control strategies for innovative reactor concepts, such a simplified description is less ... -
A Critical Review of the Physics and Modeling of Deteriorated Heat Transfer in Supercritical Fluids
(The American Society of Mechanical Engineers (ASME), 2020)Modeling of deterioration of heat transfer (DHT) observed in fluid flows at supercritical pressure remains a challenge due to incomplete understanding of the underlying physics. Given the challenges involved in the ... -
A Density Functional Theory Study on the Diffusion of Fission Gas Atoms in Uranium Dioxide
(The American Society of Mechanical Engineers (ASME), 2018)Uranium dioxide (UO2) is the typical fuel that is used in the current nuclear power plant; fission gas atoms are produced during and after the nuclear reactor operation; the fission gas atoms have a significant effect on ... -
A Feasibility Study of Noncontact Ultrasonic Sensor for Nuclear Power Plant Inspection
(The American Society of Mechanical Engineers (ASME), 2017)A pipe-wall thinning measurement is a key inspection to ensure the integrity of the piping system in nuclear power plants. To monitor the integrity of the piping system, a number of ultrasonic thickness measurements are ... -
A Happy New Year…
(The American Society of Mechanical Engineers (ASME), 2019) -
A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications
(The American Society of Mechanical Engineers (ASME), 2021)Hybrid compact heat exchangers (HCHEs) are a potential source of innovation for intermediate heat exchangers in nuclear industry, with HCHEs being designed for generation IV nuclear power applications. Compact heat exchangers ... -
A Methodology to Analyze the Safety of a Coastal Nuclear Power Plant Against Typhoon External Flooding Risks
(The American Society of Mechanical Engineers (ASME), 2017)For the protection of a coastal nuclear power plant (NPP) against external flooding hazard, the risks caused by natural events have to be taken into account. In this article, a methodology is proposed to analyze the risk ... -
A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset
(The American Society of Mechanical Engineers (ASME), 2023)Within an energy system where nuclear reactors will likely play a critical role, it is fundamental to have access to accurate and reliable computational tools that can predict the plants' behavior under different operating ... -
A New Approach to Generalization of Experimental Data on Heat Transfer to Fluids in Supercritical Region
(The American Society of Mechanical Engineers (ASME), 2020)The paper contains the results of analysis of heat transfer regimes in the case of forced turbulent flow of water and modeling fluids in channels of various configurations at supercritical pressures. Two new complex criteria ... -
A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette
(The American Society of Mechanical Engineers (ASME), 2020)With the increase of computer resources and the application of global variance reduction (GVR) method, it is a trend to obtain global distribution using the Monte Carlo (MC) method in deep-penetration shielding calculation. ... -
A Note on Mixture Density Using the Shannak Definition
(The American Society of Mechanical Engineers (ASME), 2015)In this study, a note on mixture density using the Shannak definition of the Froude number is presented (Shannak, B., 2009, “Dimensionless Numbers for TwoPhase and Multiphase Flow,†Proceedings of the International ... -
A Novel Algorithm for Fast Measurement of Material Density in Symmetrical Objects Using X-Ray Radiography
(The American Society of Mechanical Engineers (ASME), 3/13/2023 )X-ray radiography has proved to be essential in medical imaging and examination of material structures because it is noninvasive and generates images based on well-understood attenuation characteristics of materials. For ... -
A Novel Assessment of Delayed Neutron Detector Data in CANDU Reactors
(The American Society of Mechanical Engineers (ASME), 2020)A common opportunity for nuclear power plant operators is ensuring that routinely collected data are fully leveraged. Exploiting data analytics can enable improvements in anomaly detection and condition monitoring by ... -
A Numerical Analysis Method of Impurity Precipitation on Mesh Wire of Cold Trap in Fast Breeder Reactor
(The American Society of Mechanical Engineers (ASME), 2018)A fast breeder reactor (FBR) is considered as the promising technology in terms of load reduction on the environment, because the FBR has capability to improve usage efficiency of uranium resources and can reduce high-level ... -
A Numerical Study of Turbulent Upward Flow of Super Critical Water in a 2 × 2 Rod Bundle With Nonuniform Heating
(The American Society of Mechanical Engineers (ASME), 2020)This work is part of a benchmarking exercise organized by an IAEA in supercritical water-cooled reactor (SCWR) thermal-hydraulics aimed at improving the understanding and prediction accuracy of the thermal-hydraulic phenomena ...