Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 141-160 of 891
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Radon Equilibrium Equivalent Concentration Uncertainty of Calibration System With Alpha Self-Absorption Consideration
(The American Society of Mechanical Engineers (ASME), 2022)The measurement of radon decay products level in dwellings or working places separately is not preferable. The estimation of radon equivalent equilibrium concentration (EECRn) is more simple and quick technique. In this ... -
Radiation-Induced Surface Wettability Enhancement of an Indium Tin Oxide and Titanium Oxide Film-Coated Sapphire
(The American Society of Mechanical Engineers (ASME), 2022)Surface wettability is an important parameter that affects nucleate boiling. Irradiation can alter the surface wettability on metal surfaces without altering the surface macrostructure. The wettability characteristics of ... -
Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things
(The American Society of Mechanical Engineers (ASME), 2022)Nuclear newcomers need to verify the support infrastructure development keeps steady with the power plant construction and radioactive materials transportation. European power reactor's (EPR) spent fuel (SF) had been chosen ... -
High Reliability Microgrid for a Nuclear Facility Emergency Power Supply
(The American Society of Mechanical Engineers (ASME), 2022)This paper investigates the use of a high reliability microgrid to supply emergency electrical power to a nuclear facility following loss of offsite power accident. Majority of the nuclear facilities around the world utilize ... -
Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities
(The American Society of Mechanical Engineers (ASME), 2022)Thermal cycling induced fatigue is widely recognized as one of the major contributors to the damage of nuclear plant piping systems, especially at locations where turbulent mixing of flows with different temperature occurs. ... -
Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA
(The American Society of Mechanical Engineers (ASME), 2022)Uncertainty and Sensitivity analysis methods are often used in severe accident analysis for validating the complex physical models employed in the system codes that simulate such scenarios. This is necessitated by the large ... -
Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part I
(The American Society of Mechanical Engineers (ASME), 2022)The general context of this paper is an evaluation of strategies that can be used to mitigate aerosol dispersion during fuel debris or corium retrieval in damaged Fukushima Daiichi reactors. Knowledge of the aerosol source ... -
Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor
(The American Society of Mechanical Engineers (ASME), 2022)The development of advanced fuels and fuel cycles for conventional Generation III+ reactors, advanced reactors (such as Generation IV), and small modular reactors will help ensure the long-term sustainability and safety ... -
Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels
(The American Society of Mechanical Engineers (ASME), 2022)To enable the deployment of small modular reactors (SMRs) in Canada, Canadian Nuclear Laboratories (CNL) is interested in the applicability of zero energy deuterium-2 (ZED-2) experiments for validation of Monte Carlo reactor ... -
Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation
(The American Society of Mechanical Engineers (ASME), 2022)Thermal performance of passive residual heat removal systems and solar heaters is affected by thermal stratification in the pool. There are hardly any studies reported in the literature on the role of seismic excitations ... -
Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications
(The American Society of Mechanical Engineers (ASME), 2022)The objective of this study was to present a prediction method for condensation heat transfer in the presence of noncondensable gas (air or nitrogen) for computational fluid dynamics (CFD) analyses, where physical quantities ... -
Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
(The American Society of Mechanical Engineers (ASME), 2022)The economic simplified boiling water reactor (ESBWR) is a boiling water nuclear reactor of generation III+. The U.S. Nuclear Regulatory Commission (NRC) approved the ESBWR design as the world's best light-water nuclear ... -
Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation
(The American Society of Mechanical Engineers (ASME), 2022)Two-phase flows including a phase change such as liquid–vapor flows play an important role in many industrial applications. A deeper understanding of the phase change phenomena is required to improve performance and safety ... -
Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste
(The American Society of Mechanical Engineers (ASME), 2022)Small modular reactors (SMRs) are a popular topic with a significant number of designs with a wide range of sizes. The motivation of this type of work is to find alternative uses for the SMRs so that the thermal energy is ... -
Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant
(The American Society of Mechanical Engineers (ASME), 2022)This work investigated the thermophysical characteristics of liquid indium–bismuth–tin eutectic alloy also known as Field's Metal for the purposes of use as a similar fluid for liquid metal reactors. The density, specific ... -
Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code
(The American Society of Mechanical Engineers (ASME), 2022)The Research Center Řež (CVŘ) is developing a methodology to simulate nuclear power plants under accidental conditions. A particular effort is focused in the severe accident phenomenology where hydrogen deflagration carries ... -
Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions
(The American Society of Mechanical Engineers (ASME), 2022)Inconel 625 is considered one of the candidate materials for fuel cladding in the Canadian supercritical water reactor. Gas tungsten arc welding (GTAW) is being evaluated as a joining technique for SCWR fuel cladding since ... -
Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components
(The American Society of Mechanical Engineers (ASME), 2022)Zirconium alloys are well-positioned as the material of choice for nuclear in-core structures since they have a low neutron absorption cross section and possess good material properties under elevated neutron flux and ... -
Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles
(The American Society of Mechanical Engineers (ASME), 2022)The analysis of deteriorated heat transfer (DHT) influence on the stress–strain state of a perspective core of small modular reactors with supercritical water (SMR SCWR) fuel assemblies is carried out based on experimental ... -
Concept of a Small Modular SCWR With Horizontal Fuel Assemblies
(The American Society of Mechanical Engineers (ASME), 2022)Based on the concept of the high performance light water reactor (HPLWR), an innovative concept of a small modular reactor is presented, which shall have smaller peak cladding temperatures than the HPLWR due to better ...