Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 181-200 of 891
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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 ... -
Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions
(The American Society of Mechanical Engineers (ASME), 2022)Current development on advanced technology fuel (ATF) claddings is aiming at improved high temperature integrity of new candidate materials designed on existing zirconium cladding materials. To assess their performance in ... -
Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction
(The American Society of Mechanical Engineers (ASME), 2022)Canadian Nuclear Laboratories has an on-going Research & -
Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
(The American Society of Mechanical Engineers (ASME), 2022)The paper describes a modified version of the tempa-sc computer program designed to calculate temperature fields in bundles of rods cooled by a supercritical pressure (SCP) fluid. This version of the program is based on ... -
Using the Few-Group Approximation for Calculating Some Neutron-Physical Characteristics of VVER-1000 Core by Means of the Monte Carlo Universal Code
(The American Society of Mechanical Engineers (ASME), 2021)The main purpose of this work is to study the possibility of using the few-group approximation for calculation of some neutron-physical characteristics of VVER-1000 core by means of special version of Monte Carlo Universal ... -
A Short Inroad to Optimized Compactification of Composite Neutronic Shields
(The American Society of Mechanical Engineers (ASME), 2022)Compact neutronic shields for mobile nuclear reactors or accelerator-based neutron beams are known to be optimized multilayered composites. This paper is a simplified short inroad to the complex problem of optimizing the ... -
On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix
(The American Society of Mechanical Engineers (ASME), 2022)The paper discusses specific electromagnetic effects observed in the large circulating masses of liquid metal inherent in the heat transport systems of the commercial fast breeder reactors. It was explained why the criterion ... -
The Incorporation of Human Performance Improvement into Systems Design
(The American Society of Mechanical Engineers (ASME), 2021)Although considerable research has been conducted on the human-machine interface, this is a moving target as industry sprints to keep up with technological advances. Conflicts remain between the optimism of technology ... -
Thermal Soil Radon Mitigation
(The American Society of Mechanical Engineers (ASME), 2021)In this work, consideration is given to the possibility for thermal soil radon mitigation. It is known that the diffusion coefficients of radon through minerals and rocks are characterized by Arrhenius linear plots and ... -
Proactive Human Error Reduction Using the Systems Engineering Process
(The American Society of Mechanical Engineers (ASME), 2021)Many existing simple systems are incapable of meeting current demand and are quickly becoming obsolete, indicating that more challenging systems and designs will exist in the future. If new technologies are not implemented ... -
Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability
(The American Society of Mechanical Engineers (ASME), 2021)This paper discusses the use of self-consolidating concrete (SCC), in a large-scale placement during new nuclear plant construction. SCC has provided cost and labor savings and construction process improvements. Use of SCC ... -
Nuclear Regulatory Acceptance of Certified Process Data Reconciliation
(The American Society of Mechanical Engineers (ASME), 2021)The utility industry is currently undergoing a substantial change from analogue to digital infrastructure. Not only plant performance and utility profits are dependent on accurate plant operational parameters but, more ... -
Utilizing of Spent Fuel Storage Pool in Gamma Irradiation Experiments
(The American Society of Mechanical Engineers (ASME), 2021)The objective of this study is suggesting a new method for gamma irradiating experiment using spent fuel elements (SFEs). An irradiation device was developed to contain the sample during the gamma irradiation process under ... -
Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator
(The American Society of Mechanical Engineers (ASME), 2021)This research presents a numerical study of deposition efficiency and decontamination factor of the radioactive nuclide in steam generator tubes of a typical 325 MWel pressurized water reactor (PWR). To find out the ... -
Post-Test Analyses of the CMMR-4 Test
(The American Society of Mechanical Engineers (ASME), 2021)Understanding the final distribution of core materials and their characteristics is important for decommissioning the Fukushima Daiichi Nuclear Power Station (1F). Such characteristics depend on the accident progression ... -
Hybrid Reactivity-Equivalent Physical Transformation Method on Double-Heterogeneous System Containing Dispersed Fuel Particles and Burnable Poison Particles
(The American Society of Mechanical Engineers (ASME), 2021)Because of the double heterogeneity of particle-dispersed fuel and particle-dispersed burnable poisons in double-heterogeneous (DH) systems, traditional software for reactor neutronics calculation cannot model and calculate ... -
Preliminary Evaluation of the LASSO Method for Prediction of the Relative Power Density Distribution in Mixed Oxide (Pu, DU)O2 Fuel Pellets
(The American Society of Mechanical Engineers (ASME), 2021)Predicting the power distribution within nuclear fuel is essential for predicting reactor fuel performance, since power distributions can impact pellet temperature distributions and fission product transport and migration. ... -
Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium
(The American Society of Mechanical Engineers (ASME), 2021)A study is carried out on the build-up and characterization of ultraslow nuclear burn-up wave in epithermal neutron multiplying medium for slab geometry. Uranium-plutonium fissile medium is considered for the calculation. ... -
Hybrid Nodal Integral/Finite Element Method for Time-Dependent Convection Diffusion Equation
(The American Society of Mechanical Engineers (ASME), 2022)Nodal integral methods (NIM) are a class of efficient coarse mesh methods that use transverse averaging to reduce the governing partial differential equation(s) (PDE) into a set of ordinary differential equations (ODE). ...