Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 41-60 of 901
-
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 ... -
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 ... -
Molten Salt Pump Journal-Bearings Dynamic Characteristics Under Hydrodynamic Lubrication Conditions
(The American Society of Mechanical Engineers (ASME), 2024)A reliable high-temperature molten salt pump is critical for the development of Fluoride-salt-cooled, High-temperature Reactors (FHRs). By supporting the rotating journal, the appropriate journal bearing can ensure that ... -
Design and Analysis of a Free-Piston Stirling Engine for Microreactor Applications
(The American Society of Mechanical Engineers (ASME), 2024)With the development of microreactors, a free-piston Stirling engine (FPSE) is an excellent candidate to support the development of microreactors. Based on the advantages of microreactors such as the compact design, ... -
Electrochemical Activity Measurements of UCl3 in Molten NaCl-MgCl2-UCl3
(The American Society of Mechanical Engineers (ASME), 2024)Open circuit potential (OCP) measurements were made to determine uranium chloride (UClx) species activity in NaCl–MgCl2, which is a candidate salt for use in a molten salt reactor fuel. The operating temperature ranged ... -
Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor
(The American Society of Mechanical Engineers (ASME), 2024)Small modular reactors (SMRs) are actively being considered for use in Canada. Some proposed SMRs can make use of solar salt as an intermediate coolant for a heat storage system. The development of thermalhydraulic simulation ... -
Public–Private Partnering in Nuclear Reactor Development—Historical Review and Implications for Today
(The American Society of Mechanical Engineers (ASME), 2024)The dominant nuclear reactor technologies that comprise the current global operating fleet were developed and deployed over a relatively short, midtwentieth century, period spanning the 1950s and 60 s. Four of these ...