Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 41-60 of 891
-
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 ... -
Technical Brief: Safeguardability Analysis of a Molten Salt Sampling System Design
(The American Society of Mechanical Engineers (ASME), 2024)Challenges with safeguarding molten salt reactor (MSR) designs have prompted the search for enhanced safeguards technologies and revised safeguards materials control & accountancy (MC&A) approaches. A molten salt ... -
Fabrication Aspects and Performance Characterization of α-Al2O3/AlPO4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications
(The American Society of Mechanical Engineers (ASME), 2024)Liquid metals (LMs) exhibit several key characteristics justifying their utilization as coolants and breeders for nuclear fusion reactors and advanced fission reactors. In fusion reactors, the LMs confront an exorbitantly ... -
Interactions Between Molten Sodium and Standard Pipe Insulation
(The American Society of Mechanical Engineers (ASME), 2024)Safety system design and implementation are critical to the operation of any nuclear plant. For sodium-cooled nuclear reactors, hazards external to the reactor core are present in the form of molten sodium that leaks through ... -
Cold Crucible Facility for Severe Accident Research at Canadian Nuclear Laboratories
(The American Society of Mechanical Engineers (ASME), 2023)The properties and behavior of corium are important factors in the progression and ultimate consequences of a severe nuclear reactor accident. Canadian Nuclear Laboratories (CNL) is developing a cold crucible facility to ... -
Application of Level 3 Probabilistic Safety Analysis in UK HPR1000
(The American Society of Mechanical Engineers (ASME), 2024)A Level 3 probabilistic safety assessment (L3 PSA) is required in United Kingdom (UK) generic design assessment (GDA) to demonstrate that a new nuclear power plant is suitable to be built in UK. L3 PSA is used to assess ... -
Experimental Study of Helium Stratification in Multi-Compartment Containment Studies Facility
(The American Society of Mechanical Engineers (ASME), 2023)A significant amount of hydrogen may be released inside the containment of water-cooled nuclear power reactor under postulated accident conditions. Its distribution in the multicompartment containment geometry must be known ... -
Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding
(The American Society of Mechanical Engineers (ASME), 2023)Performance of two distinct fuel systems, U-7Mo fuel in Zircaloy (Zry-4) cladding and U-10Mo fuel in aluminum (Al6061-O) cladding was studied. First, a mini plate with Zry-4 cladding from a previous irradiation experiment ... -
Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor
(The American Society of Mechanical Engineers (ASME), 2024)200 MWth lead-cooled fast reactor (LOTUS) reactor core is a small modular lead-cooled fast reactor with designed power of 200 MWth under development at Vietnam National University (VNU) University of Science, Hanoi for a ... -
On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave
(The American Society of Mechanical Engineers (ASME), 2023)Optimization of dynamical multibeam neutron cancer therapy has recently been shown to be possible via employment of the beam frequencies of neutron waves as a control variable. The concepts of transfer functions (TF), ... -
Development and Testing of a System Thermal-Hydraulics Model for a 50-MWel-Class Pressurized Water Reactor–Small Modular Reactor
(The American Society of Mechanical Engineers (ASME), 2024)This paper describes the development, analysis, testing of a RELAP5-3D system thermal-hydraulics model for a 50-MWel-class pressurized water reactor–small modular reactor (PWR–SMR), similar to that by NuScale Power. This ...