YaBeSH Digital Library: Recent submissions
Now showing items 13221-13240 of 316660
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Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology
(The American Society of Mechanical Engineers (ASME), 2024)This paper presents outcomes from research studies conducted independently at Purdue University as part of a collaborative project with the staff of Pacific Northwest National Laboratory (PNNL). Research work focused on ... -
Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach
(The American Society of Mechanical Engineers (ASME), 2024)The influence of radial neutron reflector on the build-up and propagation of a nuclear fuel burn-up wave in a fast multiplying medium is investigated using a consistent parametric approach. Coupled multigroup neutron ... -
The Transfer of Xenon-135 to Molten Salt Reactor Graphite
(The American Society of Mechanical Engineers (ASME), 2024)The term “Molten salt reactors” refers to a broad class of nuclear reactors that use a molten alkali-halide salt as the primary coolant fluid. This paper pertains to thermal spectrum liquid fuel molten fluoride salt reactors ... -
Reviewing Welding Procedures—Checklists for Nuclear Power Systems
(The American Society of Mechanical Engineers (ASME), 2024)To ensure effective control of the welding process, nuclear power architecture and engineering (AE) companies routinely undertake the review of procedure qualification records (PQRs) and welding procedure specifications ... -
Practical Approach to Nuclear Shelter Wall Thickness Estimation
(The American Society of Mechanical Engineers (ASME), 2024)In the complex situation in which we live, preventive measures are increasingly being taken against the threat of nuclear attack and ionizing radiation, nuclear shelters are being built for private and public purposes. The ... -
Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion
(The American Society of Mechanical Engineers (ASME), 2024)Canadian Nuclear Laboratories (CNL) is collaborating in the Joint European Canadian Chinese Development of Small Modular Reactor Technology (ECC-SMART) project to understand the corrosion behavior of the most promising ... -
Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA
(The American Society of Mechanical Engineers (ASME), 2024)After the nuclear accident at the Fukushima Daiichi nuclear power plant, hydrogen generation has resurfaced as a key issue, with respect to its quantification in the simulation of severe accidents (SAs), because of the ... -
Implant Strength Contributes to the Osseointegration Strength of Porous Metallic Materials
(The American Society of Mechanical Engineers (ASME), 2024)Creating the optimal environment for effective and long term osseointegration is a heavily researched and sought-after design criteria for orthopedic implants. A validated multimaterial finite element (FE) model was developed ... -
Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development
(The American Society of Mechanical Engineers (ASME), 2024)A plate-type nuclear fuel consisting of a solid monolithic foil of U-10 wt. %Mo is under development for use in the United States' high-performance research reactors. In support of developing this fuel, the fuel has been ... -
Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries
(The American Society of Mechanical Engineers (ASME), 2024)A small modular lead-cooled fast spectrum core concept called Advanced lead-cooled modular nuclear reactor (ALMANAR) designed to produce 45 MWth power for 22 years operating without refueling was proposed in a previous ... -
An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition
(The American Society of Mechanical Engineers (ASME), 2024)An improved heat flux partitioning model of pool boiling is proposed in this study to predict the material-conjugated pool boiling curve. The fundamental rationale behind the improved model is that heat convection is only ... -
Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods
(The American Society of Mechanical Engineers (ASME), 2024)Small modular reactors (SMRs) based on high-temperature gas-cooled reactor (HTGR) technology are being developed for providing high-temperature process heat and high-efficiency (>40%) electrical power generation. However, ... -
Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
(The American Society of Mechanical Engineers (ASME), 2024)Thermal molten salt reactors can be designed in many configurations. This paper investigates the optimal geometry of a one fluid molten salt reactor (OFMSR) in a virtual one-and-half fluid configuration with a fixed fuel ... -
Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO2 Fueled Dual Cooled VVER-1000 Assembly
(The American Society of Mechanical Engineers (ASME), 2024)The feasibility of transuranic (TRU) fuel rods has been studied for a dual-cooled VVER-1000 assembly along with the conventional UO2 fuel rods. It has been found that the heterogeneous arrangements of TRU and UO2 fuel rods ... -
Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor
(The American Society of Mechanical Engineers (ASME), 2023)Fluoride-salt-cooled high temperature reactor (FHR) effectively combines the solid fuel and moderator design of high-temperature gas-cooled reactor (HTGR) technology with the fluoride salt coolant (LiF-BeF2, FLiBe) of ... -
Development of Analysis Tools for Heat Pipes Used in the Core Cooling of Small Modular Reactors: Potassium Property Correlations
(The American Society of Mechanical Engineers (ASME), 2023)Alkali metal heat pipes can be used for core cooling in advanced micro- and small modular reactors. This article provides a detailed review of currently available saturation property correlations for potassium that can be ... -
Digital Twin Applied to Predictive Maintenance for Industry 4.0
(The American Society of Mechanical Engineers (ASME), 2024)The major concept of the future Industrial 4.0 framework is the integration of artificial intelligence (AI) and the implementation of digital twin (DT), which avoids serious economic losses caused by unexpected equipment ... -
Gauging and Imaging of Pipes Using a Water-Immersible Ultrasonic Instrumentation System
(The American Society of Mechanical Engineers (ASME), 2024)The purpose of this research work is to establish the functionality of the novel ultrasonic non-destructive inspection system and accurate gauging of pipes and to locate and visualize flaws in the form of B-scan cross-sectional ... -
Injury Risk Functions for the Midsized Male Wrist and Elbow as a Result of Behind Shield Blunt Trauma
(The American Society of Mechanical Engineers (ASME), 2024)Ballistic shields protect users from a variety of threats, including projectiles. Shield back-face deformation (BFD) is the result of the shield deflecting or absorbing a projectile and deforming toward the user. Back-face ... -
Reactive Collision Avoidance Control for Nonholonomic Vehicles and Obstacles of Arbitrary Shape
(The American Society of Mechanical Engineers (ASME), 2024)Potential field-based collision avoidance algorithms for mobile robots frequently assume vehicles and obstacles to have circular or spherical shapes. This assumption not only simplifies the analysis but also limits the ...