Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 21-40 of 891
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Review of Canadian Experience With the Fabrication of Thoria-Based Fuels for Advanced Reactors and Fuel Cycles for Long-Term Nuclear Energy Sustainability and Security
(The American Society of Mechanical Engineers (ASME), 2024)Advanced fuels and fuel cycles are important for the current and next generation of advanced reactors, small modular reactors, and microreactors, in order to maximize the utilization of fissile and fertile nuclear fuel ... -
Neutron Activation Analysis of Environmental Samples at the Training Reactor VR-1
(The American Society of Mechanical Engineers (ASME), 2025)Described research work is focused on the study of environmental pollution in the Czech Republic using an instrumental neutron activation analysis (INAA). The samples of mosses and alluvial soils were irradiated at the ... -
Analysis of Stakeholders' Trust Level in the Nuclear Energy Domain in Japan
(The American Society of Mechanical Engineers (ASME), 2024)In discussions on the nuclear restart policy in Japan, trust among stakeholders in nuclear power is often raised as an issue. However, the discussion has progressed without analyzing the trust demanded by the Japanese ... -
Legal Issues of Fusion Technologies
(The American Society of Mechanical Engineers (ASME), 2024)A comprehensive regulatory framework for fusion must consider the unique characteristics and challenges of fusion technology, including safety, environmental protection, waste management, export/import control, and nuclear ... -
TSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept
(The American Society of Mechanical Engineers (ASME), 2024)This paper presents the findings of studies conducted at Canadian Nuclear Laboratories (CNL) to support the development of small modular reactor (SMR) designs. The primary focus of this research was to evaluate the suitability ... -
Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
(The American Society of Mechanical Engineers (ASME), 2024)Over the last decade, several international thermalhydraulics benchmarking efforts have been carried out to support the development of the Generation IV supercritical water-cooled reactor (SCWR) concept. These benchmarking ... -
Modeling of N and P-Type of Coaxial Ge Detectors Using MCNPX and the Effect of Dead Layer Variation on Its Response Function
(The American Society of Mechanical Engineers (ASME), 2024)This study assessed the response function of a p-type and n-type coaxial high-purity germanium (HPGe) detector via Monte Carlo N-Particle eXtended (MCNPX). MCNPX was employed to model the Coaxial Ge detectors, and for a ... -
Performance of Borated Centrifugally Tensioned Metastable Fluid Detector Versus Ludlum 42-49B, Fuji NSN3 Detectors for Fission Energy Spectrum Neutron Detection With the Source Within Lead/Concrete Shielded Configurations
(The American Society of Mechanical Engineers (ASME), 2024)This paper presents the results of neutron detection efficiency and dosimetry between a borated centrifugally tensioned metastable fluid detector (B-CTMFD) configured to detect thermal to fast neutrons versus two widely ... -
Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations
(The American Society of Mechanical Engineers (ASME), 2024)This paper presents the results of neutron detection efficiency and dosimetry between a nonborated centrifugally tensioned metastable fluid detector (NB-CTMFD) configured to detect fast (>0.1 MeV) versus two widely used ... -
Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results
(The American Society of Mechanical Engineers (ASME), 2024)Accident analysis and ensuring power plant safety are pivotal in the nuclear energy sector. Significant strides have been achieved over the past few decades regarding fire protection and safety, primarily centered on design ... -
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 ...